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Sample records for radioactive goods proposed

  1. Study on radioactivity in consumer goods

    International Nuclear Information System (INIS)

    1976-01-01

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

  2. Approval of radioactive consumer goods

    International Nuclear Information System (INIS)

    Paynter, R.A.

    1992-01-01

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

  3. The safety of consumer goods containing radioactive substances

    International Nuclear Information System (INIS)

    Wrixon, A.D.

    1980-01-01

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

  4. Different training programs for the transport of radioactive goods proposed by the INSTN

    International Nuclear Information System (INIS)

    Kimmel, O.

    2004-01-01

    To meet the statutory requirements of the ADR pertaining to training, the INSTN (National Institute for Nuclear Sciences and Technology) proposes different courses on the transport of radioactive materials

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

    International Nuclear Information System (INIS)

    1980-05-01

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

  6. Derivation of the Radioactivity Index for Consumer Goods Containing NORM

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Mee; Chung, Kun Ho; Ji, Young Yong; Kim, Chang Jong; Kang, Mun Ja [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    Some consumer goods to promote health such as anion bracelets, necklace and mats contain naturally occurring radioactive material (NORM). Some of them can cause problems because of high radioactivity. In the regulations, there is an annual effective dose limit of 1mSv for products, but the activity concentration limits and radioactivity index for products is not established yet. Although there are few researches for consumer goods containing NORM in foreign countries, in Japan, for the consumer goods. To regulate the NORM in consumer goods, it is necessary to derive activity concentration limits corresponding to the annual limits of 1mSv. In this research, we calculated the activity concentration limits according to the usage quantities of consumer goods. Using these results, it is possible to suggest several radioactivity indexes to apply to a lot of consumer goods.

  7. Derivation of the Radioactivity Index for Consumer Goods Containing NORM

    International Nuclear Information System (INIS)

    Jang, Mee; Chung, Kun Ho; Ji, Young Yong; Kim, Chang Jong; Kang, Mun Ja

    2016-01-01

    Some consumer goods to promote health such as anion bracelets, necklace and mats contain naturally occurring radioactive material (NORM). Some of them can cause problems because of high radioactivity. In the regulations, there is an annual effective dose limit of 1mSv for products, but the activity concentration limits and radioactivity index for products is not established yet. Although there are few researches for consumer goods containing NORM in foreign countries, in Japan, for the consumer goods. To regulate the NORM in consumer goods, it is necessary to derive activity concentration limits corresponding to the annual limits of 1mSv. In this research, we calculated the activity concentration limits according to the usage quantities of consumer goods. Using these results, it is possible to suggest several radioactivity indexes to apply to a lot of consumer goods

  8. Radioactivity of and exposure by the consumer's goods containing NORM

    International Nuclear Information System (INIS)

    Yoshida, M.; Ohhata, T.; Sato, S.; Ohyama, R.; Furuya, H.

    2005-01-01

    It is so important from the view of point of regulation to know the radioactive concentration or radioactivity in the consumer's goods containing naturally occurring radioactive materials (NORM) and the radiation exposure when they are used in the daily living life. In this study, 20 consumer's goods containing NORM were collected. After chemically processing them, the radioactive concentrations in them were measured by an inductively coupled plasma attached with mass spectrometer (ICP-MS) and a γ-ray spectrometer of Ge(li). In addition, the radiation exposures were calculated in four typical cases where the consumer' goods are generally used in the daily living life. (J.P.N.)

  9. The application of dangerous goods regulations to the transport of radioactive wastes

    International Nuclear Information System (INIS)

    Blenkin, J.J.; Darby, W.P.; Heywood, J.D.; Wikinson, H.L.; Carrington, C.K.; Murray, M.A.

    1998-01-01

    Some radioactive materials to be transported, including certain radioactive wastes, contain materials that qualify as dangerous goods as defined by the United Nations Recommendations on the Transport of Dangerous Goods (United Nations 1997). The regulations governing the transport of radioactive and dangerous goods in the UK are largely based on the IAEA Regulations for the Safe Transport of Radioactive Material (IAEA 1990) and the UN Recommendations (United Nations 1993). Additional legislation will also apply including the Carriage of Dangerous Goods by Road (Driver Training) Regulations 1996 (UK 1996). The IAEA Transport Regulations are clear that where radioactive materials have other dangerous properties the requirements of other relevant transport regulations for dangerous goods must also be met. They require that consignments are appropriately segregated from other dangerous goods, in accordance with relevant legislation, and that dangerous properties such as explosiveness, flammability etc. are taken into account in packing, labelling, marking, placarding, storage and transport. In practice, however, it requires a clear understanding of the relationship between the IAEA Transport Regulations and other dangerous goods legislation in order to avoid a number of problems in the approval of package design. This paper discusses the regulations applying to the transport of dangerous goods and explores practical problems associated with implementing them. It highlights a number of opportunities for developing the regulations, to make them easier to apply to radioactive materials that also have other potentially dangerous properties. (authors)

  10. Proposals for radioactive material by rail (packaging, labelling and carriage) regulations (Northern Ireland) 1996

    International Nuclear Information System (INIS)

    1996-01-01

    The proposed Radioactive Material by Rail (Packaging, Labelling and Carriage Regulations (Northern Ireland) are presented in this consultation document. The proposals establish a new system of safety controls which implement the requirements of two European Directives. These are the ADR and RID Framework Directives which relate to the transport of dangerous goods by road and rail respectively. (UK)

  11. Proposed goals for radioactive waste management

    International Nuclear Information System (INIS)

    Bishop, W.P.; Frazier, D.H.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.; Watson, R.A.

    1977-04-01

    Goals are proposed for the national radioactive waste management program to establish a policy basis for the guidance and coordination of the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations, and analyses of selected primary literature and interviews of personnel concerned with waste management. Public concerns are identified, their relevance assessed, and a conceptual framework is developed that facilitates understanding of the dimensions and demands of the radioactive waste management problem. The nature and scope of the study are described along with the approach used to arrive at a set of goals appropriately focused on waste management

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

    International Nuclear Information System (INIS)

    Paynter, R.A.

    1992-01-01

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

  13. Proposed goals for radioactive waste management

    International Nuclear Information System (INIS)

    Bishop, W.P.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.

    1978-05-01

    A special, seven member, interdisciplinary task group of consultants was established in January 1976 to propose goals for the national waste management program. This is the report of that group. The proposed goals are intended as a basis for the NRC to establish a policy by which to guide and coordinate the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations and analysis by the authors who examined selected primary literature and interviewed many individuals concerned with waste management. The authors extended the scope of their inquiry and proposed goals to cover 'all technical and societal aspects necessary to an operating waste management system, rather than dealing with the regulatory process alone.' The waste management goals as developed are simple statements of principles which appear to the authors to be important conditions to insure the proper establishment and operation of a system to manage radioactive wastes.' In brief, the goals are designed to protect people and things of value in an equitable manner

  14. A proposed classification system for high-level and other radioactive wastes

    International Nuclear Information System (INIS)

    Kocher, D.C.; Croff, A.G.

    1987-06-01

    This report presents a proposal for quantitative and generally applicable risk-based definitions of high-level and other radioactive wastes. On the basis of historical descriptions and definitions of high-level waste (HLW), in which HLW has been defined in terms of its source as waste from reprocessing of spent nuclear fuel, we propose a more general definition based on the concept that HLW has two distinct attributes: HLW is (1) highly radioactive and (2) requires permanent isolation. This concept leads to a two-dimensional waste classification system in which one axis, related to ''requires permanent isolation,'' is associated with long-term risks from waste disposal and the other axis, related to ''highly radioactive,'' is associated with shorter-term risks due to high levels of decay heat and external radiation. We define wastes that require permanent isolation as wastes with concentrations of radionuclides exceeding the Class-C limits that are generally acceptable for near-surface land disposal, as specified in the US Nuclear Regulatory Commission's rulemaking 10 CFR Part 61 and its supporting documentation. HLW then is waste requiring permanent isolation that also is highly radioactive, and we define ''highly radioactive'' as a decay heat (power density) in the waste greater than 50 W/m 3 or an external radiation dose rate at a distance of 1 m from the waste greater than 100 rem/h (1 Sv/h), whichever is the more restrictive. This proposal also results in a definition of Transuranic (TRU) Waste and Equivalent as waste that requires permanent isolation but is not highly radioactive and a definition of low-level waste (LLW) as waste that does not require permanent isolation without regard to whether or not it is highly radioactive

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

    International Nuclear Information System (INIS)

    Serradell, Vicente; Ballesteros, Luisa; Ortiz, Josefina

    2008-01-01

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

  16. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    International Nuclear Information System (INIS)

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

  17. A proposed classification system for high-level and other radioactive wastes

    International Nuclear Information System (INIS)

    Kocher, D.C.; Croff, A.G.

    1989-01-01

    On the basis of the definition of high-level wastes (HLW) in the Nuclear Waste Policy Act of 1982 and previous descriptions of reprocessing wastes, a definition is proposed based on the concept that HLW is any waste which is highly radioactive and requires permanent isolation. This conceptual definition of HLW leads to a two-dimensional waste classification system in which one axis, related to 'highly radioactive', is associated with shorter-term risks from waste management and disposal due to high levels of decay heat and external radiation, and the other axis, related to 'requires permanent isolation', is associated with longer-term risks from waste disposal. Wastes that are highly radioactive are defined quantitatively as wastes with a decay heat (power density) greater than 50 W/m 3 or an external dose-equivalent rate greater than 100 rem/h (1 Sv/h) at a distance of 1 m from the waste, whichever is more restrictive. Wastes that require permanent isolation are defined quantitatively as wastes with concentrations of radionuclides greater than the Class-C limits that are generally acceptable for near-surface land disposal, as obtained from the Nuclear Regulatory Commission's 10 CFR Part 61 and its associated methodology. This proposal leads to similar definitions of two other waste classes: transuranic (TRU) waste and equivalent is any waste that requires permanent isolation but is not highly radioactive; and low-level waste (LLW) is any waste that does not require permanent isolation, without regard to whether or not it is highly radioactive. 31 refs.; 3 figs.; 4 tabs

  18. EPA proposes options for control of industrial radioactivity

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

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

  19. Nuclear waste: good news

    International Nuclear Information System (INIS)

    Gay, Michel

    2014-01-01

    The author states that the problem of nuclear wastes is solved. He states that 90 per cent of radioactive wastes are now permanently managed and that technical solutions for deep geological storage and for transmutation will soon solve the problem for the remaining 10 pc. He states that geological storage will be funded (it is included in electricity price). He denounces why these facts which he consider as good news, do not prevail. He proposes several documents in appendix: a text explaining the nuclear fuel cycle in France, and an extract of a report made by the national inventory of radioactive materials and wastes

  20. A Scenario Proposal For A Radioactive Waste Transport Accident

    International Nuclear Information System (INIS)

    Salama, M.A.; Rashad, S.M.

    1999-01-01

    In spite of all precautions that being taken during radioactive materials transport accidents to ensure safe transportation of these materials; there is still a probability for accidents to occur which, may be accompanied by injury or death of persons and damage of property So, in response to the increasing possibilities of accidents in Egypt, the government had prepared an emergency response plan for radiological accidents to coordinate the response efforts of all the national agencies. Trends for use of the radioactive materials and sources inside the country for the purpose of medical diagnosis and treatment as well as in industrial applications, are increasing. The radioactive waste resulted from these activities are transported from the centres where these materials being used to the waste management facility where they are treated and finally disposed safely at disposal site. The aim of the emergency exercise scenario is to test not only the main components of the emergency plan but also the level of emergency preparedness; that is the effectiveness with which the actions or combined actions of the different organizations involved in an emergency can be put into practice. The motivation of the present paper was undertaken to give a scenario proposal for the radiological emergency actions taken in case of a transport accident for a radioactive waste material (type A- package ) transported by a vehicle from one of the medical centers to a disposal site, 40 km northeast of cairo

  1. A proposal of materials for the storage of radioactive wastes

    International Nuclear Information System (INIS)

    Carlsson, R.

    1978-01-01

    On the basis of a literature study concerning the chemical stability of ceramics as well as of different experiencies of persons working with ceramics in Sweden a proposal of candidate materials for the storage of radioactive wastes is presented. Advantages and disadvantages in connection with the use of different ceramics have been tabulated. (E.R.)

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

    International Nuclear Information System (INIS)

    2000-01-01

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

  3. No 2906. Proposal of law with the aim of organizing the durable management of radioactive wastes

    International Nuclear Information System (INIS)

    2006-02-01

    This proposal of law is the result of a long thinking enriched by 15 years of reports preparation, workshops and exchange with foreign organizations in charge of radioactive waste management, mainly carried out in the framework of the December 30, 1991 law. This proposal of law deals with the following points: general conditions of the management of radioactive wastes, rules relative to the reprocessing of foreign wastes, national plan for the management of radioactive wastes, creation of a national commission of evaluation of the research work on the management of high-activity and long-lived radioactive wastes, creation of a funds for the financing of the research and the industrial management of radioactive wastes, the three complementary methods of waste management for the high-activity and long-lived wastes, date lines for the implementation of a first experimental reactor for transmutation, for a long duration surface or sub-surface storage facility and for a reversible disposal center, concerting obligation with people's representatives and creation of a public interest group, financial contribution allocated to territory authorities, radioactive wastes proprietorship, creation of a local information and follow-up committee for radioactive waste facilities, and eventual charge compensations relative to the implementation of this law. (J.S.)

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

    International Nuclear Information System (INIS)

    2012-01-01

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

  5. Measurement of the radioactive concentration in consumer's goods containing natural uranium and thorium and evaluation of the exposure by their utilization

    International Nuclear Information System (INIS)

    Yoshida, Masahiro; Satou, Shigerou; Ohhata, Tsutomu; Watanabe, Masatoshi; Ohyama, Ryutaro; Furuya, Hirotaka; Endou, Akira

    2005-01-01

    A number of consumer's goods which contain natural uranium and thorium are circulated in the familiar living environment. Based on various kinds of information sources, 20 kinds of these consumer's goods were collected and their radioactive concentrations were measured by using ICP-MS and Ge semiconductor detector. As this result, it was found that the concentrations of uranium and thorium in the consumer's goods used at home and industries were below 34 Bq/g and below 270 Bq/g, respectively. Next, the concentrations of daughter nuclides were not so different from the ones of uranium or thorium, which showed that the secular radioactive equilibrium held between both concentrations. In addition, the radiation exposures for public consumer were evaluated when four kinds of typical consumer's goods frequently used in daily life are utilized. The results computed by MCNP-4C code were below 250 μSv/y. (author)

  6. Proposal for a questionnaire to assess risk perception concerning a radioactive waste repository

    International Nuclear Information System (INIS)

    Tanimoto, Katia Suemi

    2011-01-01

    One of the key features for public acceptance of nuclear energy is the belief that radioactive waste can be managed safely, in order to protect human beings from its possible harmful effects in present and future generations. In this sense, it is essential to understand how people perceive the risk associated with radioactive waste and which the main factors driving their attitudes toward its disposal are. One of the ways to achieve this understanding is through opinion polls. In this study, a questionnaire focused on the nuclear energy acceptability issue and its association with radioactive waste management was proposed, covering the following aspects: attitudes towards radioactive waste and nuclear power, credibility on institutions and sectors responsible by the nuclear safety, identification of perceived benefits, risk perception of specific technologies and activities, perception of real risk, emotional reaction comprehension and precautionary principle. Results obtained from a pilot questionnaire application are presented and discussed in this paper. (author)

  7. Radioactive waste vitrification offgas analysis proposal

    International Nuclear Information System (INIS)

    Nelson, C.W.; Morrey, E.V.

    1993-11-01

    Further validation of the Hanford Waste Vitrification Plant (HWVP) feed simulants will be performed by analyzing offgases during crucible melting of actual waste glasses and simulants. The existing method of vitrifying radioactive laboratory-scale samples will be modified to allow offgas analysis during preparation of glass for product testing. The analysis equipment will include two gas chromatographs (GC) with thermal conductivity detectors (TCD) and one NO/NO x analyzer. This equipment is part of the radioactive formating offgas system. The system will provide real-time analysis of H 2 , O 2 , N 2 , NO, N 2 O, NO 2 , CO, CO 2 , H 2 O, and SO 2 . As with the prior melting method, the product glass will be compatible with durability testing, i.e., Product Consistency Test (PCT) and Material Characterization Center (MCC-1), and crystallinity analysis. Procedures have been included to ensure glass homogeneity and quenching. The radioactive glass will be adaptable to Fe +2 /ΣFe measurement procedures because the atmosphere above the melt can be controlled. The 325 A-hot cell facility is being established as the permanent location for radioactive offgas analysis during formating, and can be easily adapted to crucible melt tests. The total costs necessary to set up and perform offgas measurements on the first radioactive core sample is estimated at $115K. Costs for repeating the test on each additional core sample are estimated to be $60K. The schedule allows for performing the test on the next available core sample

  8. Management of radioactive contaminated foodstuffs and consumer goods in Spain. Establishment of a common framework

    Energy Technology Data Exchange (ETDEWEB)

    Trueba, C.; Montero, M.; Oltra, C.; Sala, R. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas - CIEMAT (Spain); Gallego, E. [Escuela Tecnica Superior de Ingenieros Industriales - UPM-ETSII (Spain)

    2014-07-01

    In the event of a nuclear accident with radiological consequences affecting the quality of foodstuffs, feed-stuffs and in general, consumer goods, the European Union and its Member States, have developed radiation protection general guidelines to manage such situations. In this context, there are recommendations and standards, at international (Codex Alimentarius -FAO/OMS-, IAEA) and regional levels (EURATOM Directives) based on activity concentrations in different products and maximum permitted levels of radioactive contamination of foodstuffs. These levels are based on certain assumptions about the consumption of contaminated products. However, the application of these guidelines is not easy, as shown after the Chernobyl and Fukushima accidents. Several factors converge in this situation. First, is the national regulation of each country, that can decide on the maximum radioactivity levels in food consumed within the country. Other is the misinterpretation of the guidelines that where originally developed for specific conditions. Finally, rejection attitudes of consumers and general public towards foodstuffs, feed-stuffs and goods according to their provenience, must also be taken into account. Aware of this reality, the European Union is funding within its 7. Framework Programme for R and D projects to help optimize European response to radiological emergencies, including those involving contaminated foodstuffs and consumer goods. Specifically, this is the overall objective of the PREPARE Project (Innovative Integrative Tools and Platforms to be Prepared for Radiological Emergencies and Post-Accident Response in Europe) within the framework of NERIS Platform (European Platform on Preparedness for Nuclear and Radiological Emergency Response and Recovery). PREPARE project is intended to develop strategies, guidelines and tools for the management of foodstuffs and consumer goods contaminated with radioactivity, considering not only the Public Administration, as

  9. Risk communication on the construction of radioactive waste treatment facility

    International Nuclear Information System (INIS)

    Okoshi, Minoru

    2005-01-01

    In this paper, risk communications among the Japan Radioisotope Association (JRIA), a local government and the general public which were carried out during the development process of a radioactive waste treatment facility in Takizawa Village, Iwate Prefecture are analyzed based on the articles of newspapers and the interviews with the concerned people. The analysis results show good risk communications were not carried out because of the absence of the confidence to the JRIA, decision making rules and the merits. In order to make good use of this experience for the future development of radioactive waste management facilities, the lessons learned from this case are summarized and the check lists for good risk communication are proposed. (author)

  10. Proposal for basic safety requirements regarding the disposal of high-level radioactive waste

    International Nuclear Information System (INIS)

    1980-04-01

    A working group commissioned to prepare proposals for basic safety requirements for the storage and transport of radioactive waste prepared its report to the Danish Agency of Environmental Protection. The proposals include: radiation protection requirements, requirements concerning the properties of high-level waste units, the geological conditions of the waste disposal location, the supervision of waste disposal areas. The proposed primary requirements for safety evaluation of the disposal of high-level waste in deep geological formations are of a general nature, not being tied to specific assumptions regarding the waste itself, the geological and other conditions at the place of disposal, and the technical methods of disposal. It was impossible to test the proposals for requirements on a working repository. As no country has, to the knowledge of the working group, actually disposed of hifg-level radioactive waste or approved of plans for such disposal. Methods for evaluating the suitability of geological formations for waste disposal, and background material concerning the preparation of these proposals for basic safety requirements relating to radiation, waste handling and geological conditions are reviewed. Appended to the report is a description of the phases of the fuel cycle that are related to the storage of spent fuel and the disposal of high-level reprocessing waste in a salt formation. It should be noted that the proposals of the working group are not limited to the disposal of reprocessed fuel, but also include the direct disposal of spent fuel as well as disposal in geological formations other than salt. (EG)

  11. Radiological consequences of proposed landfilling of low-level radioactive waste

    International Nuclear Information System (INIS)

    Drake, P.

    1991-01-01

    A proposal for landfilling of low-level radioactive waste (100 GBq in 10 000 m 3 ) at Ringhals Nuclear Power Plants was sent to the Swedish Radiation Protection Institute (SRPI) in 1989. In 1990, slight changes were made to the proposal to overcome the conventional risks of landfilling. In the proposed method, most of the low-level wastes is compacted and put into sealed plastic packages. The waste is then placed on a sand-moraine bed above a level-blasted rock surface. The area above and between the waste packages is filled with a sand-seashell mixture for pH adjustment of any waster infiltrating into the site. The whole deposit is covered with a least 50 cm of moraine in order to attenuate most of the radiation form the waste and to prevent rainwater from reaching the waste. Downstream from the deposit, there is a retention bed made of seashells and seaweed. Any small quantities of water from the deposit passing through the retention bed, as well as rainwater, will continue out to the sea. Use of this method will most probably not lead to an increase in the radiation dose to people outside the site. In the rather improbable case of intrusion into the deposit after 50 years, a maximum dose of 10 μSv per year would be received. If all the radioactivity were to be transported to the sea in one year, as a results of the breakdown of all the barrier, an individual eating fish caught in the vicinity of the site would receive less than 25 μSv during the following year. In the worst case, if the waste ignites prior to, or during landfilling, individuals living at a distance of 1 km from the fire could receive a dose of less than 20 μSv. (au)

  12. Experimental and numerical study of the degradation of radioactive measurements in the filters of airborne radioactive surveillance systems

    International Nuclear Information System (INIS)

    Geryes, Tony

    2009-01-01

    The measurement of radioactivity in the filters of airborne radioactive surveillance systems is a major metrology difficulty due to the fact that the absorption of a radiation in the filter media and the mass of aerosols accumulated distort the nuclear counting response. This thesis focuses on the determination of correction factors for the radioactivity loss in the survey filters. In a first step, radioactive filters representing the atmospheric samples have been prepared using the nuclear test bench ICARE. The experimental study on reference filters provided a database to determine correction factors for various filtration conditions. The second part proposes a new numerical method developed to determine the correction factors. It consists of coupling GeoDict for particles filtration simulations and MCNPX simulations for a transport in matter. The good agreement obtained by comparing the numerical and experimental correction factors has permitted to validate the numerical model

  13. The art of writing good research proposals.

    Science.gov (United States)

    van Ekelenburg, Henk

    2010-01-01

    Whilst scientists are by default motivated by intellectual challenges linked to the area of their interest rather than have an interest in the financial component related to their work, the reality of today is that funding for their work does not come automatically More and more governments provide project-related funding rather than multipurpose funding that covers the total annual costs of a research performing entity (such as a university department). So, like it or not, researchers have to present their research ideas and convince funding bodies about the usefulness and importance of their intended research work. Writing the research proposal is not simply typing words and punctuation. It requires succinctly and clearly chronicling the facts, as well as crafting a convincing line of reasoning for funding the project. For the best result, both the logical, verbal left side of the brain and the intuitive, creative right side of the brain need to work as a team. This article covers the process of writing a proposal, from research idea to submission to the funding body. The key to good writing is linking the text into a logical project flow. Therefore, in the early stage of writing an RTD proposal, developing the chain of reasoning and creating a flow chart is recommended to get a clear overview of the entire project and to visualise how the many work packages are connected.

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  15. 76 FR 9025 - Agency Information Collection Activities; Proposed Collection; Comment Request; Good Laboratory...

    Science.gov (United States)

    2011-02-16

    ...; (3) equipment inspection, maintenance, calibration, and testing records; (4) documentation of feed...] Agency Information Collection Activities; Proposed Collection; Comment Request; Good Laboratory Practice... for public comment in response to the notice. This notice solicits comments on the good laboratory...

  16. Risk communication on the siting of radioactive waste management facility

    International Nuclear Information System (INIS)

    Okoshi, Minoru; Torii, Hiroyuki; Fujii, Yasuhiko

    2007-01-01

    Siting of radioactive waste management facilities frequently raise arguments among stakeholders such as a municipal government and the residents. Risk communication is one of the useful methods of promoting mutual understanding on related risks among stakeholders. In Finland and Sweden, siting selection procedures of repositories for spent nuclear fuels have been carried out successfully with risk communication. The success reasons are analyzed based on the interviews with those who belong to the regulatory authorities and nuclear industries in both countries. Also, in this paper, risk communication among the Japan Radioisotope Association (JRIA), a local government and the general public, which was carried out during the establishment process of additional radioactive waste treatment facilities in Takizawa Village, Iwate Prefecture, is analyzed based on articles in newspapers and interviews with persons concerned. The analysis results showed that good risk communication was not carried out because of the lack of confidence on the JRIA, decision making rules, enough communication chances and economic benefits. In order to make good use of these experiences for the future establishment of radioactive waste management facilities, the lessons learned from these cases are summarized and proposals for good risk communication (establishment of exploratory committee and technical support system for decision making, and measurements to increase familiarity of radioactive waste) are discussed. (author)

  17. Managing radioactive waste safely. Proposals for developing a policy for managing solid radioactive waste in the UK

    International Nuclear Information System (INIS)

    2001-09-01

    More than 10,000 tonnes of radioactive waste are safely stored in the UK, but await a decision on their long-term future. This will increase to 250,000 tonnes when nuclear material currently in use is converted into solid waste. Even if no new nuclear power plants are built and reprocessing of spent nuclear fuel ends when existing plants reach the end of their working lives, about another 250,000 tonnes of waste will arise during the clean-up of those plants over the next century. Most of this waste results from the work of Government agencies or publicly owned companies since the 1940s. Some of the substances involved will be radioactive and potentially dangerous for hundreds of thousands of years. There are much larger amounts of low-level (less radioactive) waste. Currently, these are disposed of at a special surface repository in Cumbria. But again, much larger amounts will arise as existing nuclear facilities are cleaned up. We must decide how to manage this waste in the long term. Implementing that decision will take decades. So now is the time to start planning for our future. In this paper, the UK Government and the Devolved Administrations for Scotland, Wales and Northern Ireland are launching a national debate which will lead up to that decision, and beyond it. The aim is to develop, and implement, a UK nuclear waste management programme which inspires public support and confidence. To do this, we propose a major programme of research and public discussion, using many techniques - some traditional, some relatively new - to stimulate informed discussion, and to involve as many people and groups as possible. We want to inspire public confidence in the decisions and the way in which they are implemented. To do that, we have to demonstrate that all options are considered; that choices between them are made in a clear and logical way; that people's values and concerns are fully reflected in this process; and that information we provide is clear, accurate

  18. Design of good manufacturing facility for sterile radioactive pharmaceuticals

    International Nuclear Information System (INIS)

    Shin, B.C.; Choung, W.M.; Park, S.H.; Lee, K.I.; Park, J.H.; Park, K.B.

    2002-01-01

    Based on the GMP codes for radiopharmaceuticals in U.K. and some advanced countries, suitable guidelines for the production facility have been established and followed them up. The facility designs were fairly modified to maintain cleanliness criteria for installation in the existing radioisotope production facilities which are installed only in radiation safety points of view. Detailed design brief was drawn up by the Hyundai Engineering staffs, on the basis of initial planning and conceptual design was carried out by authors. Hot cells were installed in preparation room for radioactive handling. As hot cells under negative air pressure are not properly airtight, the surrounding environment was designed to keep less than class 10,000. Hot cells were designed to maintain less than class 1 0,000 and partially less than class 1 00 for production of sterile products. Final products will be autoclaved for sterilization after filling. To avoid contamination by microorganisms and particles of surrounding area, air curtain with vertical laminar flow will be installed between anteroom and corridor. In a pharmaceutical environment, the main consideration is the protection of the product. Thus, work station is held above ambient pressure. However, when handling radioactive materials, air pressure for work station should be lower than in surrounding areas to protect the operators and the remainder of the facility from airborne radioactive contamination. As Radiopharmaceuticals are radioactive materials for medical use, changing room could be held higher pressure than any other zones. It is expected that the facility will be effectively used for both routine preparation and research for sterile radiopharmaceuticals. (Author)

  19. Preliminary shielding estimates for the proposed Oak Ridge National Laboratory (ORNL) Radioactive Ion Beam Facility (RIBF)

    International Nuclear Information System (INIS)

    Johnson, J.O.; Gabriel, T.A.; Lillie, R.A.

    1996-01-01

    The Oak Ridge National Laboratory (ORNL) has proposed designing and implementing a new target-ion source for production and injection of negative radioactive ion beams into the Hollifield tandem accelerator. This new facility, referred to as the Radioactive Ion Beam Facility (RIBF), will primarily be used to advance the scientific communities' capabilities for performing state-of-the-art cross-section measurements. Beams of protons or other light, stable ions from the Oak Ridge Isochronous Cyclotron (ORIC) will be stopped in the RIBF target ion source and the resulting radioactive atoms will be ionized, charge exchanged, accelerated, and injected into the tandem accelerator. The ORIC currently operates with proton energies up to 60 MeV and beam currents up to 100 microamps with a maximum beam power less than 2.0 kW. The proposed RIBF will require upgrading the ORIC to generate proton energies up to 200 MeV and beam currents up to 200 microamps for optimum performance. This report summarizes the results of a preliminary one-dimensional shielding analysis of the proposed upgrade to the ORIC and design of the RIBF. The principal objective of the shielding analysis was to determine the feasibility of such an upgrade with respect to existing shielding from the facility structure, and additional shielding requirements for the 200 MeV ORIC machine and RIBF target room

  20. Dealing with presumed radioactive contamination - a modest proposal

    International Nuclear Information System (INIS)

    Austerlitz, C.; Campos, D.; Villar, H.P.

    2009-01-01

    Reports concerning the occurrence of malignancies and cancer cases among the population caused by the presence of radioactive materials in the environment are not unusual in Brazil. The country's Nuclear Energy Commission, CNEN, is always assigned to launch an investigation in such cases. As a result, human and financial resources are usually committed in operations that, more often than not, end up by discovering that claims are riot related to radiation. This time it was based on some uranium prospecting that has been made near a small town, Lajes Pintadas, RN. Alarmist reports concerning occurrence of stillborn and malformed children and of cancer cases among the adult population, reached the state capital. A team from CNEN was dispatched to Lajes Pintadas to look for the effective presence of environmental radionuclides and to investigate the reported occurrence of malignancies caused by radiation. Due to the well-known dangers related to launching an investigation on a subject so controversial and prone to misinterpretation by the media and the public, a novel approach, both in technical and philosophical terms, was attempted and that proved to be crucial for the success of the whole undertaking: eight years on, no more reports on health problems in Lajes Pintadas were publicised. It was concluded that standard procedures towards claims concerning health problems related to the presence of radioactive materials in the environment need to be re-evaluated. A more realistic approach towards nuclear activities and their risks should be established and the guidelines proposed herein (thorough survey of available data, involvement of local officials and of the affected community, and careful handling of the media) should be closely followed. (author)

  1. Modular glovebox connector and associated good practices for control of radioactive and chemically toxic materials

    International Nuclear Information System (INIS)

    Hoover, M.D.; Mewhinney, C.J.; Newton, G.J.

    1999-01-01

    Design and associated good practices are described for a modular glovebox connector to improve control of radioactive and chemically toxic materials. The connector consists of an anodized aluminum circular port with a mating spacer, gaskets, and retaining rings for joining two parallel ends of commercially available or custom-manufactured glovebox enclosures. Use of the connector allows multiple gloveboxes to be quickly assembled or reconfigured in functional units. Connector dimensions can be scaled to meet operational requirements for access between gloveboxes. Options for construction materials are discussed, along with recommendations for installation of the connector in new or retrofitted systems. Associated good practices include application of surface coatings and caulking, use of disposable glovebags, and proper selection and protection of gasket and glove materials. Use of the connector at an inhalation toxicology research facility has reduced the time and expense required to reconfigure equipment for changing operational requirements, the dispersion of contamination during reconfigurations, and the need for decommissioning and disposal of contaminated enclosures

  2. 75 FR 62412 - Notice of Proposed Information Collection: Comment Request; HUD-Owned Real Estate-Good Neighbor...

    Science.gov (United States)

    2010-10-08

    ... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5380-N-36] Notice of Proposed Information Collection: Comment Request; HUD- Owned Real Estate-Good Neighbor Next Door Program AGENCY: Office... information: Title of Proposal: HUD-Owned Real Estate-Good Neighbor Next Door Program. OMB Control Number, if...

  3. Proposed classification scheme for high-level and other radioactive wastes

    International Nuclear Information System (INIS)

    Kocher, D.C.; Croff, A.G.

    1986-01-01

    The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level (radioactive) waste (HLW) as (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel...that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission...determines...requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph B. The approach also results in definitions of other wastes classes, i.e., transuranic (TRU) and low-level waste (LLW). The basic waste classification scheme that results from the quantitative definitions of highly radioactive and requires permanent isolation is depicted. The concentrations of radionuclides that correspond to these two boundaries, and that may be used to classify radioactive wastes, are given

  4. Transport of radioactive materials

    International Nuclear Information System (INIS)

    Huck, W.

    1992-01-01

    The book presents a systematic survey of the legal provisions governing the transport of radioactive materials, placing emphasis on the nuclear licensing provisions of sections 4, 4b of the Atomic Energy, Act (AtG) and sections 8-10 of the Radiation Protection Ordinance (StrlSchV), also considering the provisions of the traffic law governing the carriage of hazardous goods. The author's goal is to establish a systematic basis by comparative analysis of the licensing regulations under atomic energy law, for the purpose of formulating a proposed amendment to the law, for the sake of clarity. The author furthermore looks for and develops criteria that can be of help in distinguishing the regulations governing the carriage of hazardous goods from the nuclear regulatory provisions. He also examines whether such a differentiation is detectable, particularly in those amendments to the StrlSchV which came after the Act on Carriage of Hazardous Goods. The regulations governing the transport of radioactive materials under the AtG meet with the problem of different classification systems being applied, to radioactive materials in the supervisory regulations on the one hand, and to nuclear materials in Annex 1 to the AtG on the other hand. A classification of natural, non-nuclear grade uranium e.g. by the financial security provisions is difficult as a result of these differences in the laws. The author shows that the transport regulations of the StrlSchV represent an isolated supervisory instrument that has no connecting factor to the sections 28 ff StrlSchV, as radiation protection is provided for by the regulations of the Act on Carriage of Hazardous Goods. The author suggests an amendment of existing law incorporating the legal intent of sections 8-10 StrlSchV and of sections 4, 4b AtG into two sections, and abolishing the supervisory provisions of the StrlSchV altogether. (orig./HP) [de

  5. Essential Ingredients of a Good Research Proposal for Undergraduate and Postgraduate Students in the Social Sciences

    Directory of Open Access Journals (Sweden)

    Raymond Talinbe Abdulai

    2014-08-01

    Full Text Available As part of the requirements for the award of degrees in higher education institutions, students at undergraduate and postgraduate levels normally carry out research, which they report in the form of dissertations or theses. The research journey commences with the selection of a research topic and the preparation of a proposal on the selected topic. Experience has shown that students tend to encounter difficulties in writing research proposals for their supervisors because they do not fully comprehend what constitutes a research proposal. The purpose of this article is to take students through a step-by-step process of writing good research proposals by discussing the essential ingredients of a good research proposal. Thus, it is not a didactic piece—the aim is to guide students in research proposal writing. In discussing these ingredients, relevant examples are provided where necessary for ease of understanding. It is expected that on reading this article, students should be able to: (a demonstrate knowledge and understanding of what research is all about and its challenging nature; (b display an enlarged comprehension of research gap(s, problem or question(s, aim, objectives, and hypotheses as well as their distinguishing characteristics; (c demonstrate a good understanding of the relevant elements to be considered in the constituent sections of a good research proposal; and (d comprehend the elements of a research proposal that should feature in the final written dissertation or thesis.

  6. Salinity, can be indicator for radioactivity

    International Nuclear Information System (INIS)

    Patrascu, V.

    2006-01-01

    Radioactivity being within nature is an incontestable reality. Less than a century, man have diversified and intensified its presence, especially after nuclear weapons and peaceful use of fission power. Secondary, the risks of ionizing radiation effects on live matter have increased. The need of environmental radioactivity assessment and knowledge development in the field is and remains actually in follow time. The nuclear techniques are generally expensive and the radioanalytical methods are no so fast. Sometimes it is necessary to make the rapid and cheapest estimation, without to replace them. This is possible by finding of some accessible correlated parameters and easy to be analyzed. These parameters could indicate the availability of radionuclides in different ecosystems or the availability of ecosystems for different radionuclides. K-40 is a remarkable presence in marine natural radioactivity and plays an important role for euphotic and deep levels. As nutrient it can influence coastal ecosystems and its radiation power can be significant for microbiological processes. This present work analyzed the correlation between salinity and water K-40 radioactivity (beta, gamma) and proposes an empirical connection formula on the base of the good correlation that has been identified

  7. Proposal of threshold levels for the definition of non-radioactive wastes

    International Nuclear Information System (INIS)

    Yoshida, Yoshikazu

    1979-01-01

    With increasing amounts of radioactive wastes along with the advances of nuclear power generation and radioactive material utilizations, the needs for management cost reduction and resource saving have arisen. Under the situation, the threshold levels for the definition of non-radioactive solid wastes are required. The problem has been studied by an ad hoc committee in Nuclear Safety Research Association, by the request of the Science and Technology Agency. The matters described are the procedures of deriving the threshold levels, the feasibility studies of the management of waste threshold-level with several enterprises, and future subjects of study. The threshold levels are grouped in two, i.e. the unconditional level and the conditional level. According to the unconditional threshold level, solid wastes are separated definitely into radioactive and non-radioactive ones. According to the conditional threshold level, under certain conditions, some radioactive solid wastes according to the unconditional level are regarded as non-radioactive ones. (J.P.N.)

  8. Proposals of new basic concepts on safety and radioactive waste and of new High Temperature Gas-cooled Reactor based on these basic concepts

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Masuro, E-mail: ogawa.masuro@jaea.go.jp

    2016-11-15

    Highlights: • The author proposed new basic concepts on safety and radioactive waste. • A principle of ‘continue confining’ to realize the basic concept on safety is also proposed. • It is indicated that only a HTGR can attain the conditions required from the principle. • Technologies to realize the basic concept on radioactive waste are also discussed. • A New HTGR system based on the new basic concepts is proposed. - Abstract: A new basic concept on safety of ‘Not causing any serious catastrophe by any means’ and a new basic concept on radioactive waste of ‘Not returning any waste that possibly affects the environment’ are proposed in the present study, aiming at nuclear power plants which everybody can accept, in consideration of the serious catastrophe that happened at Fukushima Japan in 2011. These new basic concepts can be found to be valid in comparison with basic concepts on safety and waste in other industries. The principle to realize the new basic concept on safety is, as known well as the inherent safety, to use physical phenomena such as Doppler Effect and so on which never fail to work even if all equipment and facilities for safety lose their functions. In the present study, physical phenomena are used to ‘continue confining’, rather than ‘confine’, because the consequence of emission of radioactive substances to the environment cannot be mitigated. To ‘continue confining’ is meant to apply natural correction to fulfill inherent safety function. Fission products must be detoxified to realize the new basic concept on radioactive waste, aiming at the final processing and disposal of radioactive wastes as same as that in the other wastes such as PCB, together with much efforts not to produce radioactive wastes and to reduce their volume nevertheless if they are emitted. Technology development on the detoxification is one of the most important subjects. A new High Temperature Gas-cooled Reactor, namely the New HTGR

  9. Proposals of new basic concepts on safety and radioactive waste and of new High Temperature Gas-cooled Reactor based on these basic concepts

    International Nuclear Information System (INIS)

    Ogawa, Masuro

    2016-01-01

    Highlights: • The author proposed new basic concepts on safety and radioactive waste. • A principle of ‘continue confining’ to realize the basic concept on safety is also proposed. • It is indicated that only a HTGR can attain the conditions required from the principle. • Technologies to realize the basic concept on radioactive waste are also discussed. • A New HTGR system based on the new basic concepts is proposed. - Abstract: A new basic concept on safety of ‘Not causing any serious catastrophe by any means’ and a new basic concept on radioactive waste of ‘Not returning any waste that possibly affects the environment’ are proposed in the present study, aiming at nuclear power plants which everybody can accept, in consideration of the serious catastrophe that happened at Fukushima Japan in 2011. These new basic concepts can be found to be valid in comparison with basic concepts on safety and waste in other industries. The principle to realize the new basic concept on safety is, as known well as the inherent safety, to use physical phenomena such as Doppler Effect and so on which never fail to work even if all equipment and facilities for safety lose their functions. In the present study, physical phenomena are used to ‘continue confining’, rather than ‘confine’, because the consequence of emission of radioactive substances to the environment cannot be mitigated. To ‘continue confining’ is meant to apply natural correction to fulfill inherent safety function. Fission products must be detoxified to realize the new basic concept on radioactive waste, aiming at the final processing and disposal of radioactive wastes as same as that in the other wastes such as PCB, together with much efforts not to produce radioactive wastes and to reduce their volume nevertheless if they are emitted. Technology development on the detoxification is one of the most important subjects. A new High Temperature Gas-cooled Reactor, namely the New HTGR

  10. Managing low-level radioactive wastes: a proposed approach

    International Nuclear Information System (INIS)

    Peel, J.W.; Levin, G.B.

    1980-01-01

    In 1978, President Carter established the Interagency Review Group on Nuclear Waste Management (IRG) to review the nation's plans and progress in managing radioactive wastes. In its final report, issued in March 1979, the group recommended that the Department of Energy (DOE) assume responsibility for developing a national plan for the management of low-level wastes. Toward this end, DOE directed that a strategy be developed to guide federal and state officials in resolving issues critical to the safe management of low-level wastes. EG and G Idaho, Inc. was selected as the lead contractor for the Low-Level Waste Management Program and was given responsibility for developing the strategy. A 25 member task force was formed which included individuals from federal agencies, states, industry, universities, and public interest groups. The task force identified nineteen broad issues covering the generation, treatment, packaging, transportation, and disposal of low-level wastes. Alternatives for the resolution of each issue were proposed and recommendations were made which, taken together, form the draft strategy. These recommendations are summarized in this document

  11. Study of radioactivity and radiation attenuation of a new heavy weight concrete

    International Nuclear Information System (INIS)

    Ramadan, A.B.; Fouda, S.; EL-Mongy, S.; Hodhod, O.; Yousef, M.

    2005-01-01

    The present study is concerned with studying the radioactivity levels and efficiency of proposed heavy weight concrete as a shielding material for low and intermediate level radioactive wastes. Effect of elevated temperatures on radiation attenuation characteristics of proposed materials was also studied. Three types of local natural aggregates (iron ores) namely magnetite, limonite and hematite have been prepared, analyzed for their radioactivity and tested to determine their suitability for the manufacture of heavy weight concrete, which can be used for shielding. Hematite was excluded and two types of concrete have been prepared by using magnetite and limonite. The gamma spectrometry and neutron activation have been used to determine both uranium and thorium contents in the investigated materials. The results obtained by the two methods showed that uranium and thorium were within the acceptable low levels. It was observed that the two types of concrete have good attenuation properties

  12. Teaching good communication/proposal-writing skills: Overcoming one deficit of our educational system

    Science.gov (United States)

    Reif-Lehrer, Liane

    1992-09-01

    Good communication skills require: (1) an understanding of one's audience and the subtle interactions between writer and reader, (2) organizational skills to methodically progress through the necessary stages of a project (e.g., writing a proposal), and (3) certain basic communication (writing/speaking) skills, i.e., a facility with the basic elements of transmitting information clearly. The task of writing a grant proposal in response to a specific set of instructions is used to illustrate the analysis and responses necessary to complete a major written communication project. The concept of focusing on—and writing for—the reader (in this case, the proposal reviewer) is emphasized. Although good communication skills affect life-styles, productivity, and economics in our society, the communication skills of the American pubic are sorely lacking—even among people with high levels of education—because students receive little training in these skills in the United States educational system. However, such skills can be taught to younger students as well as to adults.

  13. 76 FR 6488 - Notice of Submission of Proposed Information Collection to OMB; HUD-Owned Real Estate-Good...

    Science.gov (United States)

    2011-02-04

    ... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5480-N-11] Notice of Submission of Proposed Information Collection to OMB; HUD-Owned Real Estate--Good Neighbor Next Door Program AGENCY... Lists the Following Information Title of Proposal: HUD-Owned Real Estate--Good Neighbor Next Door...

  14. Proposal for radioactive liquid waste management in a brachytherapy sealed sources development laboratory

    International Nuclear Information System (INIS)

    Souza, C.D.; Peleias Jr, F.S.; Rostelato, M.E.C.M.; Zeituni, C.A.; Benega, M.A.G.; Tiezzi, R.; Mattos, F.R.; Rodrigues, B.T.; Oliveira, T.B.; Feher, A.; Moura, J.A.; Costa, O.L.

    2014-01-01

    The radioactive waste management is addressed in several regulations. Literature survey indicates limited guidance on liquid waste management in Brachytherapy I-125 seeds production. Laboratories for those seeds are under implementation not only in Brazil but in several countries such as Poland, South Korea, Iran, China, and others. This paper may be used as reference to these other groups. For the correct implementation, a plan for radiological protection that has the management of radioactive waste fully specified is necessary. The proposal is that the waste will be deposited in a 20 L and 60 L containers which will take 2 years to fill. For glove box 1, the final activity of this container is 1.91 x 10 10 Bq (3.19 years to safe release in the environment). For glove box 3, the final activity of this container is 1.28 x 10 10 Bq (2.85 years to safe release in the environment). (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

    Pallier, Lucien

    1961-11-20

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

  16. The new context for transport of radioactive and nuclear material

    International Nuclear Information System (INIS)

    Anne, C.; Galtier, J.

    2002-01-01

    The transportation of radioactive and nuclear materials involves all modes of transportation with a predominance for road and for air. It is but a minute fraction dangerous good transportation. Around 10 millions of radioactive packages are shipped annually all over the world of which ninety percent total corresponds to shipments of radioisotopes. In spite of the small volume transported, experience, evolution of transport means and technologies, the trend to constantly improve security and safety and public acceptance have modified the transport environment. During the last few years, new evolutions have applied to the transport of radioactive and nuclear materials in various fields and especially: - Safety - Security - Logistics means - Public acceptance - Quality Assurance. We propose to examine the evolution of these different fields and their impact on transportation methods and means. (authors)

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

    International Nuclear Information System (INIS)

    1984-01-01

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

  18. Proposed classification scheme for high-level and other radioactive wastes

    International Nuclear Information System (INIS)

    Kocher, D.C.; Croff, A.G.

    1986-01-01

    The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level radioactive waste (HLW) as: (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel....that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission....determines....requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph (B). The approach also results in definitions of other waste classes, i.e., transuranic (TRU) and low-level waste (LLW). A basic waste classification scheme results from the quantitative definitions

  19. Study Circles as a Method of Informing the Adult Population on Radioactivity

    International Nuclear Information System (INIS)

    Kralj, M.

    2002-01-01

    Public acceptance of the radioactive waste disposal facilities is difficult to achieve. Analysis of the reasons that underlie public rejection of radioactive waste disposal facilities shows that people are not adequately informed about the proposal. They also have a lot of prejudices due to the lack of knowledge and understanding about basic facts on radioactivity and environmental processes. ARAO has proposed that the topic of radioactivity and radioactive waste be included in the program of study circles in order to promote knowledge and understanding of these issues among the adult population in several Slovenian communities. Study circles are self-organized adult learning groups in the local community environment. Two study circles were initially proposed: one in Krsko, the community with a nuclear facility, and one in Radovljica, a community without a nuclear facility. Because of troubles with the unexpected politicization of nuclear issues, the study circle in Krsko was postponed to the later term, so that only the study circle in the community without the nuclear installation was active. The members were found by personal invitations. They worked on different issues dealing with radiation, mainly with the application of radiation and radioactive substances in medicine. Through the study circle activities the interest in radiation issues increased. The members reported that they disseminated their interest and acquired knowledge to their family members and friends. Our experience shows that self-learning in small groups, promoting discussions and the confrontation of different opinions, results in an increase in objective knowledge. Therefore, study circles can provide a good basis for confidence building in the nuclear technology.(author)

  20. Transport of hazardous goods

    International Nuclear Information System (INIS)

    1989-01-01

    The course 'Transport of hazardous goods' was held in Berlin in November 1988 in cooperation with the Bundesanstalt fuer Materialforschung und -pruefung. From all lecturs, two are recorded separately: 'Safety of tank trucks - requirements on the tank, development possibiities of active and passive safety' and 'Requirements on the transport of radioactive materials - possible derivations for other hazardous goods'. The other lectures deal with hazardous goods law, requirements on packinging, risk assessment, railroad transport, hazardous goods road network, insurance matters, EC regulations, and waste tourism. (HSCH) [de

  1. ILK statement about the proposed EU directives on nuclear safety and the management of radioactive waste

    International Nuclear Information System (INIS)

    2003-01-01

    In November 2002, the European Commission proposed a package of measures for a community concept of the EU on nuclear safety. It includes a proposed directive on the safety of nuclear installations during operating and decommissioning, and a proposed directive on the management of radioactive waste. In the opinion of the International Nuclear Committee (ILK), the competences and obligations of the member states and their safety authorities must be preserved in the future. Primary responsibility for plant safety rests with the operator. This objective is served by transparent, harmonized EU-wide safety standards. New standards and definitions are not generally required. Harmonized safety standards to be developed should initially be limited to nuclear power plants because of the fundamental differences in design of nuclear facilities. The Commission should obtain the technical competence required to perform the duties arising from the application of the proposed directive. Formal inspections by the Commission of the national regulatory authorities are not necessary. Instead, a peer review process will be the better solution. A reporting system at three-year intervals is generally regarded as the most effective approach. The ILK considers the tight schedule for final storage, especially of high-level waste, problematic. Joint repository projects, also for countries with low waste arisings, are suitable approaches. The envisaged reports about the state of radioactive waste management should be integrated into the reporting systems under other international agreements. The Commission's intention to intensify cooperation in the field of research is welcomed. (orig.) [de

  2. Assessment of the Proposed Design of a New Spent Sealed Radioactive Sources Storage Facility at Novi Han

    International Nuclear Information System (INIS)

    Alardin, J.M.; Lacroix, J.P.; Glibert, R.; Marneffe, L. de

    2001-09-01

    The NOVI HAN radioactive waste repository (NHRWR) in Bulgaria, built according to a Soviet design, was commissioned in 1964. The State Committee on the Use of Atomic Energy for Peaceful Purposes (CUAEPP) temporarily stopped operations at the repository from October 1994 until measures for improvement of the facility are undertaken. Since 1994, the Spent Sealed Radioactive Sources (SSRS) have been temporarily stored at the facilities at IRT-2000 research reactor of the Bulgarian Academy of Sciences (BAS) in Sofia. In view of the importance of the radiological risks associated with the present management of the SSRS in Bulgaria, the present study contract has been launched to critically review the proposal to provide a new interim storage facility for SSRS at NHRWR. A comprehensive critical review was performed of the feasibility study for the construction of a new SSRS facility at Novi Han, carried out by the local consultant engineering company (EQE), and detailed recommendations were made concerning the proposed new development at the site. The authors think that new concepts and procedures in the management of all categories of SSRS including smoke detectors have to be introduced, taking into account the regulatory framework and the inventories of existing and anticipated SSRS. This should be the basis for the technical specification of the new facilities for conditioning and storage of spent sealed radioactive sources (not only SHARS). (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-01

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

  4. Modelling magma-drift interaction at the proposed high-level radioactive waste repository at Yucca Mountain, Nevada, USA

    NARCIS (Netherlands)

    Woods, Andrew W.; Sparks, Steve; Bokhove, Onno; Lejeune, Anne-Marie; Connor, Charles B.; Hill, Britain E.

    2002-01-01

    We examine the possible ascent of alkali basalt magma containing 2 wt percent water through a dike and into a horizontal subsurface drift as part of a risk assessment for the proposed high-level radioactive waste repository beneath Yucca Mountain, Nevada, USA. On intersection of the dike with the

  5. Proposal of a monitoring program of occupational exposure by incorporation of radioactive material for nuclear medicine services in the Caja Costarricense del Seguro Social

    International Nuclear Information System (INIS)

    Badilla Segura, Mirta

    2013-01-01

    A monitoring program of the occupational exposure by incorporation of radioactive material is proposed. Nuclear medicine services of the Caja Costarricense del Seguro Social (CCSS) are evaluated. The monitoring program is based on the provisions of the International Atomic Energy Agency and of study of nuclear medicine services of the CCSS. Radionuclides are determined for monitoring of the occupational exposure, according to the radioactive material that is worked in nuclear medicine services of the CCSS. The appropriate and alternative techniques are established for the monitoring of the occupational exposure by incorporation of radioactive material, depending on the type of radionuclide that is worked in nuclear medicine services. The worker occupationally exposed (TOE) should be subject of monitoring and how often should be realized the monitoring of the occupational exposure. The monitoring of the radiation by radioactive material must be applied to personnel working in radiopharmacies and the worker has carried out therapeutic procedures for handling of significant amounts of 13 1 I. The calculation of the committed effective dose is proposed by incorporation of radioactive material with the TOE [es

  6. Contribution to Radioactive Waste Management in Croatia

    International Nuclear Information System (INIS)

    Hudec, M.; Frgic, L.; Sunjerga, S.

    2002-01-01

    The problem of dangerous waste disposal in Croatia is not more only technical problem; it grew over to political one of the first degree. Nobody likes to have the repository in own courtyard. Some five hundred institutions and factories produce in Croatia low, intermediate or high level radioactive waste. Till now all the dangerous waste is keeping in basements of the institute Rudjer Boskovic in Zagreb, just one kilometre form the city centre. This temporary solution is working fore some fifty years, but cannot be conserved forever. In the paper are presented some of the solutions for radioactive waste deposition, known from the references. The deep, impermeable layers in Panonian area have conserved petroleum and gas under pressure of more hundred bars for few dozens millions of years. Therefore, we propose the underground deposition of radioactive waste in deep boreholes. The liquid waste can be injected in deep isolated layers. In USA and Russia, for many years such solutions are realised. In USA exist special regulations for this kind of waste management. In the paper is described the procedure of designing, execution and verification of deposition in Russia. In northern part of Croatia exist thousand boreholes with known geological data. The boreholes were executed for investigation and exploitation of oil and gas fields. This data can make good use to define safe deep layers capable to be used for repositories of liquid waste. For the high level radioactive waste we propose the deep boreholes of greater diameter, filled with containers. One borehole with 50 cm diameter and 1000 m deep can be safe deposition for c/a 50 m3 of solid high level radioactive waste. Croatia has not big quantity of waste and some boreholes can satisfy all the quantities of waste in Croatia. This is not the cheapest solution, but it can satisfy the strongest conditions of safety. (author)

  7. Transport of radioactive sources-an environmental problem

    International Nuclear Information System (INIS)

    Merckaert, G.

    1996-01-01

    Full text: The transport of dangerous goods is submitted to various regulations. These can be international, national or regional and they can differ from country to country. The basis for the regulations for dangerous goods can be found in the recommendations on the transport of dangerous goods, issued by the United Nations committee of experts on the transport of dangerous goods (orange book). For radioactive material the regulations for the safe transport of radioactive material, issued by the International Atomic Energy Agency (IAEA), are applied. The UN recommendations provide for 9 classes of dangerous goods. With regard to class 7, specifically related to the transport of radioactive material special recommendation relating to class 70, the IAEA regulations are referred to. These IAEA regulations for their part provide for 13 schedules, varying between weakly and highly radioactive. The radioactive sources which are used for non-destructive testing or for medical purposes are mostly sealed sources, i.e. the radioactive material is contained in a metallic shell. According to the nature of the isotope and their activity, the sources are transported either in industrial packagings, type A or type B packagings. According to the mode of transport, either air, sea, rail or road, various specific rules are applied, which however, are fortunately nearly completely harmonized. Special attention is paid to radiation protection, heat removal and the testing and fabrication of packagings. As a general rule, the safety of transport is based on the safety of the packagings, i.e. their ability to maintain, even in accident conditions, their capacity of tightness, shielding against radiation and removing the heat generated by the transported material

  8. A Remote Radioactivity Experiment

    Science.gov (United States)

    Jona, Kemi; Vondracek, Mark

    2013-01-01

    Imagine a high school with very few experimental resources and limited budgets that prevent the purchase of even basic laboratory equipment. For example, many high schools do not have the means of experimentally studying radioactivity because they lack Geiger counters and/or good radioactive sources. This was the case at the first high school one…

  9. The problem of final storage of radioactive waste - ethical considerations of the goods and evils

    International Nuclear Information System (INIS)

    Korff, W.; Feldhaus, S.

    1996-01-01

    The handling of radioactive remains proves to be separate, by now increasingly dominating problem in the discussion about nuclear energy. The application of the practical and concrete-ethical methodology of deliberation on goods and evils to the problems of permanent disposal, which is systematically expounded in the text, was able to show the following: 1. In the judgement on permanent disposal of nuclear waste we have to do with a prcedural-ethical process of deliberation as well. A morally justifiable and therefore responsible handling of our options has to be carried out in context of the individual, social and ecological requirements of the day as a continuous process of optimisation. Everywhere findable, on principle orientated attitudes of refusal against deliberation don't constitute an adequate solution of the problem. 2. The problems of permanent disposal have to be considered in the all-embracing context of the problems of waste disposal, in that occasion the waste disposal form of reprocessing has to be included into deliberation apart from that one of interim diposal, which is normally placed before permanent disposal. 3. The issue of permanent disposal can be discussed only in the extensive context of nuclear energy use and the problems of its ethical legitimation. 4. The problems of social acceptance of the nuclear energy use, fixed today essentially to the issue of permanent disposal of radioactive remains, cannot be easily equated with the question for its ehtical justification. (orig.) [de

  10. The issue of safety in the transports of radioactive materials

    International Nuclear Information System (INIS)

    Pallier, Lucien

    1961-01-01

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

  11. Calibration method based on direct radioactivity measurement for radioactive gas monitoring instruments

    International Nuclear Information System (INIS)

    Yoshida, Makoto; Ohi, Yoshihiro; Chida, Tohru; Wu, Youyang.

    1993-01-01

    A calibration method for radioactive gas monitoring instruments was studied. In the method, gaseous radioactivity standards were provided on the basis of the direct radioactivity measurement by the diffusion-in long proportional counter method (DLPC method). The radioactivity concentration of the gas mixture through a monitoring instrument was determined by sampling the known volume of the gas mixture into the proportional counter used for the DLPC method. Since oxygen in the gas mixture decreased the counting efficiency in a proportional counter, the influence on calibration was experimentally estimated. It was not serious and able to be easily corrected. By the present method, the relation between radioactivity concentration and ionization current was determined for a gas-flow ionization chamber with 1.5 l effective volume. It showed good agreement with the results in other works. (author)

  12. Siting Criteria for Low and Intermediate Level Radioactive Waste Disposal in Egypt (Proposal approach)

    International Nuclear Information System (INIS)

    Abdellatif, M.M.

    2012-01-01

    The objective of radioactive waste disposal is to isolate waste from the surrounding media so that it does not result in undue radiation exposure to humans and the environment. The required degree of isolation can be obtained by implementing various disposal methods and suitable criteria. Near surface disposal method has been practiced for some decades, with a wide variation in sites, types and amounts of wastes, and facility designs employed. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components or barriers: the site, the disposal facility and the waste form. The site selection process for low-level and intermediate level radioactive waste disposal facility addressed a wide range of public health, safety, environmental, social and economic factors. Establishing site criteria is the first step in the sitting process to identify a site that is capable of protecting public health, safety and the environment. This paper is concerning a proposal approach for the primary criteria for near surface disposal facility that could be applicable in Egypt.

  13. Recommendations from the SoFRa (Societe francaise de radiopharmacie) for transporting radiopharmaceuticals: How to apply the decree on the transport of radioactive goods

    International Nuclear Information System (INIS)

    Barre, E.; Rizzo-Padoin, N.; Delolmo, S.; Debordeaux, F.; Beco, V. de; El Deeb, G.; Gupta, S.; Nguyen, M.L.; Sigrist, S.

    2016-01-01

    In France, road transport of dangerous goods is regulated by the May 29, 2009 'TMD decree', which enforces the European Agreement concerning the international carriage of dangerous goods by road, known as the 'ADR Agreement' or 'ADR'. This regulation allows packages containing radioactive material to be transported on the French territory, including packages that contain radiopharmaceutical products intended for medical use (radiopharmaceuticals, generators, precursors). However, this regulation is poorly known by radio-pharmacists and nuclear medicine personnel who have to either send or receive these goods on a daily basis. This article aims to set out a summary of the key provisions that apply to radiopharmacy and to make recommendations regarding the reception and shipment of radiopharmaceutical packages. (authors) [fr

  14. Managing low-level radioactive wastes: a proposed approach

    International Nuclear Information System (INIS)

    1983-04-01

    Chapters are devoted to the following: introduction; a brief description of low-level radioactive wastes and their management; system-side issues; waste reduction and packaging; transportation; disposal; issues for further study; and summary of recommendations. Nine appendices are included

  15. Enhancing usability of augmented-reality-based mobile escape guidelines for radioactive accidents

    International Nuclear Information System (INIS)

    Tsai, Ming-Kuan; Yau, Nie-Jia

    2013-01-01

    When radioactive accidents occur, modern tools in information technology for emergency response are good solutions to reduce the impact. Since few information-technology-based applications were developed for people during radioactive accidents, a previous study (Tsai et al., 2012) proposed augmented-reality-based mobile escape guidelines. However, because of the lack of transparent escape routes and indoor escape guidelines, the usability of the guidelines is limited. Therefore, this study introduces route planning and mobile three-dimensional (3D) graphics techniques to address the identified problems. The proposed approach could correctly present the geographical relationship from user locations to the anticipated shelters, and quickly show the floor-plan drawings as users are in the buildings. Based on the testing results, in contrast to the previous study, this study offered better escape routes, when the participants performed self-evacuation in outdoor and indoor environments. Overall, this study is not only a useful reference for similar studies, but also a beneficial tool for emergency response during radioactive accidents. -- Highlights: ► Enhancing the efficiency when people escape from radioactive accidents. ► The spatial relationship is transparently displayed in real time. ► In contrast to a previous study, this study offers better escape guidelines

  16. Monte Carlo Library Least Square (MCLLS) Method for Multiple Radioactive Particle Tracking in BPR

    Science.gov (United States)

    Wang, Zhijian; Lee, Kyoung; Gardner, Robin

    2010-03-01

    In This work, a new method of radioactive particles tracking is proposed. An accurate Detector Response Functions (DRF's) was developed from MCNP5 to generate library for NaI detectors with a significant speed-up factor of 200. This just make possible for the idea of MCLLS method which is used for locating and tracking the radioactive particle in a modular Pebble Bed Reactor (PBR) by searching minimum Chi-square values. The method was tested to work pretty good in our lab condition with a six 2" X 2" NaI detectors array only. This method was introduced in both forward and inverse ways. A single radioactive particle tracking system with three collimated 2" X 2" NaI detectors is used for benchmark purpose.

  17. Natural radioactivity measurements at the proposed nuclear power plant site

    International Nuclear Information System (INIS)

    Cojuangco, J.G.; Salomon, A.Ph.

    1976-01-01

    Natural radioactivity measurement in the Philippines aims to establish baseline radioactivity levels in the environment of items essential to man. In this article, results of the environmental surveillance conducted in Bagac, Bataan from 1973 to 1974 are presented. Analyses were made on air parti-culates, sea and fresh water, grass, and soil samples for gross beta-gamma activities. Results obtained showed activity levels below the maximum permissible concentration recommended by the International Committee on Radiation Protection (ICRP)

  18. 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.)

  19. Order of 21 May 1979 on Transport of Radioactive Materials by Road or by Inland Waterway (Dangerous Goods 1979, No.5)

    International Nuclear Information System (INIS)

    1979-01-01

    This Order lays down in connection with radioactive materials (class IVb) to be carried by road or inland waterway that Section 32 of the Order of 15 April 1945 approving the transport of dangerous goods by rail, land or inland waterway will come into force on 1 October 1980. The Order prescribes that drivers of land vehicles and on inland waterways, persons responsible on board must carry a certificate concerning their cargo in accordance with the above Section. (NEA) [fr

  20. Chemical decontamination of radioactive waste

    International Nuclear Information System (INIS)

    Mohamed, H.I.

    2006-01-01

    Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. There is also a variety of alternatives for treatment and conditioning of the wastes prior disposal. The importance of treatment of radioactive waste for protection of human and environment has long been recognized and considerable experience has gained in this field. Generally, the methods used for treatment of radioactive wastes can be classified into three type's biological, physical and chemical treatment this physical treatment it gives good result than biological treatment. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. In chemical treatment there are different procedures, solvent extraction, ion exchange, electro dialysis but solvent extraction is best one because high purity can be optioned on the other hand the disadvantage that it is expensive. Beside the solvent extraction technique one can be used is ion exchange which gives reasonable result, but requires pretreatment that to avoid in closing of column by colloidal and large species. Electro dialysis technique gives quite result but less than solvent extraction and ion exchange technique the advantage is a cheep.(Author)

  1. Radioactive materials' transportation main routes in Brazil. Radiation protection aspects about radioactive materials transportation

    International Nuclear Information System (INIS)

    Vaz, Solange dos Reis e; Andrade, Fernando de Menezes; Aleixo, Luiz Claudio Martins

    2007-01-01

    The heavy transportation in Brazil is generally done by highways. The radioactive material transportation follow this same rule. Whenever a radioactive material is carried by the road, by the sea or by the air, in some cases, a kind of combination of those transportation ways, the transport manager has to create a Transportation Plan and submit it to CNEN. Only after CNEN's approval, the transportation can be done. The plan must have the main action on Radiation Protection, giving responsibilities and showing all the directing that will be take. Although, the Brazilian's highways are not in good conditions, one could say that some of them are not good enough for any kind of transportation. But we are facing radioactive material use increase but the hospitals and industries, that the reason it's much more common that kind of transportation nowadays. So, because of that, a special attention by the governments must be provide to those activities. This paper goal is to show the real conditions of some important highways in Brazil in a radioactive protection's perspective and give some suggestions to adjust some of those roads to this new reality. (author)

  2. Dossier: transport of radioactive materials

    International Nuclear Information System (INIS)

    Mignon, H.; Brachet, Y.; Turquet de Beauregard, G.; Mauny, G.; Robine, F.; Plantet, F.; Pestel Lefevre, O.; Hennenhofer, G.; Bonnemains, J.

    1997-01-01

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

  3. Proposal of conditioning of the not-in-use sealed sources which are stored in the Radioactive Wastes Treatment Facility

    International Nuclear Information System (INIS)

    Jova, L.; Garcia, N.; Benitez, J.C.; Salgado, M.; Hernandez, A.

    1996-01-01

    There is a considerable number of sealed sources which are no longer in use at the radioactive wastes treatment facility. In the present work a methodology is proposed for the final conditioning of these sources, based on their immobilization in a cement matrix. This cementation is accomplished within a 200-liter tank

  4. Radioactive waste (disposal)

    International Nuclear Information System (INIS)

    Jenkin, P.

    1985-01-01

    The disposal of low- and intermediate-level radioactive wastes was discussed. The following aspects were covered: public consultation on the principles for assessing disposal facilities; procedures for dealing with the possible sites which the Nuclear Industry Radioactive Waste Executive (NIREX) had originally identified; geological investigations to be carried out by NIREX to search for alternative sites; announcement that proposal for a site at Billingham is not to proceed further; NIREX membership; storage of radioactive wastes; public inquiries; social and environmental aspects; safety aspects; interest groups; public relations; government policies. (U.K.)

  5. Transport and handling of dangerous goods. Training of persons in charge of vehicles or vessels carrying dangerous goods by road or by inland waterways (Dangerous Goods 1979 No.1)

    International Nuclear Information System (INIS)

    1979-01-01

    This Order supplements the Regulations of 15 April 1945 on the transport of dangerous goods by rail, land and inland waterways. It deals with the training of persons in charge of vehicles or boats carrying dangerous goods by road or by inland waterways. It refers in particular to transport of radioactive materials. (NEA) [fr

  6. Transportation of hazardous goods

    CERN Multimedia

    TS Department

    2008-01-01

    A general reminder: any transportation of hazardous goods by road is subject to the European ADR rules. The goods concerned are essentially the following: Explosive substances and objects; Gases (including aerosols and non-flammable gases such as helium and nitrogen); Flammable substances and liquids (inks, paints, resins, petroleum products, alcohols, acetone, thinners); Toxic substances (acids, thinners); Radioactive substances; Corrosive substances (paints, acids, caustic products, disinfectants, electrical batteries). Any requests for the transport of hazardous goods must be executed in compliance with the instructions given at this URL: http://ts-dep.web.cern.ch/ts-dep/groups/he/HH/adr.pdf Heavy Handling Section TS-HE-HH 73793 - 160364

  7. Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste (Volume 1) Introduction

    International Nuclear Information System (INIS)

    R.A. Levich; J.S. Stuckless

    2006-01-01

    Yucca Mountain in Nevada represents the proposed solution to what has been a lengthy national effort to dispose of high-level radioactive waste, waste which must be isolated from the biosphere for tens of thousands of years. This chapter reviews the background of that national effort and includes some discussion of international work in order to provide a more complete framework for the problem of waste disposal. Other chapters provide the regional geologic setting, the geology of the Yucca Mountain site, the tectonics, and climate (past, present, and future). These last two chapters are integral to prediction of long-term waste isolation

  8. Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste (Volume 1) Introduction

    Energy Technology Data Exchange (ETDEWEB)

    R.A. Levich; J.S. Stuckless

    2006-09-25

    Yucca Mountain in Nevada represents the proposed solution to what has been a lengthy national effort to dispose of high-level radioactive waste, waste which must be isolated from the biosphere for tens of thousands of years. This chapter reviews the background of that national effort and includes some discussion of international work in order to provide a more complete framework for the problem of waste disposal. Other chapters provide the regional geologic setting, the geology of the Yucca Mountain site, the tectonics, and climate (past, present, and future). These last two chapters are integral to prediction of long-term waste isolation.

  9. Bioenergy good practice

    Energy Technology Data Exchange (ETDEWEB)

    Birse, J.; Chambers, K.

    2000-07-01

    This report gives details of a project to make the Good Practice Guidelines, which were developed to help the UK Bioenergy industry, the national and local governments, and the public, more widely available. Details concerning the designing of a Good Practice Programme, and the proposed codes of Good Practice programme are given, and general relevant good practice guidance documents are discussed. The stakeholder survey and workshop, and the proposed codes of a Good Practice Programme are presented in Annexes. (UK)

  10. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  11. Proposed sale of radioactively contaminated nickel ingots located at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    International Nuclear Information System (INIS)

    1995-10-01

    The U.S. Department of Energy (DOE) proposes to sell 8,500 radioactively contaminated nickel ingots (9.350 short tons), currently in open storage at the Paducah Gaseous Diffusion Plant (PGDP), to Scientific Ecology Group, Inc. (SEG) for decontamination and resale on the international market. SEG would take ownership of the ingots when they are loaded for transport by truck to its facility in Oak Ridge, Tennessee. SEG would receive approximately 200 short tons per month over approximately 48 months (an average of 180 ingots per month). The nickel decontamination process specified in SEG's technical proposal is considered the best available technology and has been demonstrated in prototype at SEG. The resultant metal for resale would have contamination levels between 0.3 and 20 becquerel per gram (Bq/g). The health hazards associated with release of the decontaminated nickel are minimal. The activity concentration of the end product would be further reduced when the nickel is combined with other metals to make stainless steel. Low-level radioactive waste from the SEG decontamination process, estimated to be approximately 382 m 3 (12,730 ft), would be shipped to a licensed commercial or DOE disposal facility. If the waste were packaged in 0.23 m 3 -(7.5 ft 3 -) capacity drums, approximately 1,500 to 1,900 drums would be transported over the 48-month contract period. Impacts from the construction of decontamination facilities and the selected site are minimal

  12. Training of personnel in the field of radioactive materials transport

    International Nuclear Information System (INIS)

    Fasten, Ch.

    1997-01-01

    Training of personnel in the whole nuclear fuel cycle and also in the other fields of the use of radioactivity is one of the essentials with respect to compliance assurance. The transport of radioactive material is the only activity that takes place outside a facility: on roads, on railways, on the sea or in the air. A high level of safety is therefore an absolute requirement for all transport operations. To ensure this high level the training of the personnel involved in these activities plays an important role. Many studies show that most of the incidents in radioactive materials transport are caused by man-made errors: even so there have been no events with serious radiological consequences anywhere worldwide. There are many requirements in the various national and international regulations for the safe transport of radioactive material with regard to training. An overview is given of the special regulations, e.g. for road transport drivers, for safety advisers in the whole field of the transport of dangerous goods, for specially educated personnel in sea and air transports. In addition, the newest developments in the European Community in this field are discussed. An evaluation of the present regulations and proposals for further rules are also given. (Author)

  13. Transport of hazardous goods. Befoerderung gefaehrlicher Gueter

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The course 'Transport of hazardous goods' was held in Berlin in November 1988 in cooperation with the Bundesanstalt fuer Materialforschung und -pruefung. From all lecturs, two are recorded separately: 'Safety of tank trucks - requirements on the tank, development possibiities of active and passive safety' and 'Requirements on the transport of radioactive materials - possible derivations for other hazardous goods'. The other lectures deal with hazardous goods law, requirements on packinging, risk assessment, railroad transport, hazardous goods road network, insurance matters, EC regulations, and waste tourism. (HSCH).

  14. Assessment of the environmental impact of the FAA proposed rule making affecting the conditions of transport of radioactive materials on aircraft

    International Nuclear Information System (INIS)

    Hall, R.J.; Hendrickson, P.L.; King, J.C.; McSweeney, T.I.; Shipler, D.B.; Brown, C.L.; Davis, D.K.; Watson, E.C.

    1975-01-01

    Amendments to Federal Aviation Administration (FAA) regulations relating to the transporting of radioactive materials on commercial aircraft are presented. Potential effects of the proposed changes are examined in the environmental impact statement, which is presented in the 10 sections and 5 appendices of this document. (JGB)

  15. Analogues to features and processes of a high-level radioactive waste repository proposed for Yucca Mountain, Nevada

    Science.gov (United States)

    Simmons, Ardyth M.; Stuckless, John S.; with a Foreword by Abraham Van Luik, U.S. Department of Energy

    2010-01-01

    Natural analogues are defined for this report as naturally occurring or anthropogenic systems in which processes similar to those expected to occur in a nuclear waste repository are thought to have taken place over time periods of decades to millennia and on spatial scales as much as tens of kilometers. Analogues provide an important temporal and spatial dimension that cannot be tested by laboratory or field-scale experiments. Analogues provide one of the multiple lines of evidence intended to increase confidence in the safe geologic disposal of high-level radioactive waste. Although the work in this report was completed specifically for Yucca Mountain, Nevada, as the proposed geologic repository for high-level radioactive waste under the U.S. Nuclear Waste Policy Act, the applicability of the science, analyses, and interpretations is not limited to a specific site. Natural and anthropogenic analogues have provided and can continue to provide value in understanding features and processes of importance across a wide variety of topics in addressing the challenges of geologic isolation of radioactive waste and also as a contribution to scientific investigations unrelated to waste disposal. Isolation of radioactive waste at a mined geologic repository would be through a combination of natural features and engineered barriers. In this report we examine analogues to many of the various components of the Yucca Mountain system, including the preservation of materials in unsaturated environments, flow of water through unsaturated volcanic tuff, seepage into repository drifts, repository drift stability, stability and alteration of waste forms and components of the engineered barrier system, and transport of radionuclides through unsaturated and saturated rock zones.

  16. Radioactive Mapping Contaminant of Alpha on The Air in Space of Repair of Hot Cell and Medium Radioactivity Laboratory in Radio metallurgy Installation

    International Nuclear Information System (INIS)

    Yusuf-Nampira; Endang-Sukesi; S-Wahyuningsih; R-Budi-Santoso

    2007-01-01

    Hot cell and space of acid laboratory medium activity in Radio metallurgy Installation are used for the examination preparation of fuel nuclear post irradiation. The sample examined is dangerous radioactive material representing which can disseminate passing air stream. The dangerous material spreading can be pursued by arranging air stream from laboratory space to examination space. To know the performance the air stream arrangement is hence conducted by radioactive mapping contaminant of alpha in laboratory / space of activity place, for example, medium activity laboratory and repair space. This mapping radioactivity contaminant is executed with the measurement level of the radioactivity from sample air taken at various height with the distance of 1 m, various distance and from potential source as contaminant spreading access. The mapping result indicate that a little spreading of radioactive material happened from acid cupboard locker to laboratory activity up to distance of 3 m from acid cupboard locker and spreading of radioactive contaminant from goods access door of the hot cell 104 to repair space reach the distance of 2 m from goods door access. Level of the radioactive contamination in the space was far under maximum limitation allowed (20 Bq / m 3 ). (author)

  17. Sealed radioactive source management

    International Nuclear Information System (INIS)

    2005-01-01

    Sealed radioactive sources have been used in a wide range of application in medicine, agriculture, geology, industry and other fields. Since its utilization many sources have become out of use and became waste but no proper management. This has lead to many accidents causing deaths and serious radiation injuries worldwide. Spent sources application is expanding but their management has seen little improvements. Sealed radioactive sources have become a security risk calling for prompt action. Source management helps to maintain sources in a good physical status and provide means of source tracking and control. It also provides a well documented process of the sources making any future management options safe, secure and cost effective. Last but not least good source management substantially reduces the risk of accidents and eliminates the risk of malicious use. The International Atomic Energy Agency assists Member States to build the infrastructure to properly manage sealed radioactive sources. The assistance includes training of national experts to handle, condition and properly store the sources. For Member States that do not have proper facilities, we provide the technical assistance to design a proper facility to properly manage the radioactive sources and provide for their proper storage. For Member States that need to condition their sources properly but don't have the required infrastructure we provide direct assistance to physically help them with source recovery and provide an international expert team to properly condition their sources and render them safe and secure. We offer software (Radioactive Waste Management Registry) to properly keep a complete record on the sources and provide for efficient tracking. This also helps with proper planning and decision making for long term management

  18. No 2906. Proposal of law with the aim of organizing the durable management of radioactive wastes; No 2906. Proposition de loi tendant a organiser la gestion durable des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

    This proposal of law is the result of a long thinking enriched by 15 years of reports preparation, workshops and exchange with foreign organizations in charge of radioactive waste management, mainly carried out in the framework of the December 30, 1991 law. This proposal of law deals with the following points: general conditions of the management of radioactive wastes, rules relative to the reprocessing of foreign wastes, national plan for the management of radioactive wastes, creation of a national commission of evaluation of the research work on the management of high-activity and long-lived radioactive wastes, creation of a funds for the financing of the research and the industrial management of radioactive wastes, the three complementary methods of waste management for the high-activity and long-lived wastes, date lines for the implementation of a first experimental reactor for transmutation, for a long duration surface or sub-surface storage facility and for a reversible disposal center, concerting obligation with people's representatives and creation of a public interest group, financial contribution allocated to territory authorities, radioactive wastes proprietorship, creation of a local information and follow-up committee for radioactive waste facilities, and eventual charge compensations relative to the implementation of this law. (J.S.)

  19. Uncertainty and sensitivity analysis in performance assessment for the proposed high-level radioactive waste repository at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Helton, Jon C.; Hansen, Clifford W.; Sallaberry, Cédric J.

    2012-01-01

    Extensive work has been carried out by the U.S. Department of Energy (DOE) in the development of a proposed geologic repository at Yucca Mountain (YM), Nevada, for the disposal of high-level radioactive waste. As part of this development, a detailed performance assessment (PA) for the YM repository was completed in 2008 and supported a license application by the DOE to the U.S. Nuclear Regulatory Commission (NRC) for the construction of the YM repository. The following aspects of the 2008 YM PA are described in this presentation: (i) conceptual structure and computational organization, (ii) uncertainty and sensitivity analysis techniques in use, (iii) uncertainty and sensitivity analysis for physical processes, and (iv) uncertainty and sensitivity analysis for expected dose to the reasonably maximally exposed individual (RMEI) specified the NRC’s regulations for the YM repository. - Highlights: ► An overview of performance assessment for the proposed Yucca Mountain radioactive waste repository is presented. ► Conceptual structure and computational organization are described. ► Uncertainty and sensitivity analysis techniques are described. ► Uncertainty and sensitivity analysis results for physical processes are presented. ► Uncertainty and sensitivity analysis results for expected dose are presented.

  20. Antiprotonic Radioactive Atom for Nuclear Structure Studies

    International Nuclear Information System (INIS)

    Wada, M.; Yamazaki, Y.

    2005-01-01

    A future experiment to synthesize antiprotonic radioactive nuclear ions is proposed for nuclear structure studies. Antiprotonic radioactive nuclear atom can be synthesized in a nested Penning trap where a cloud of antiprotons is prestored and slow radioactive nuclear ions are bunch-injected into the trap. By observing of the ratio of π+ and π- produced in the annihilation process, we can deduce the different abundance of protons and neutrons at the surface of the nuclei. The proposed method would provide a unique probe for investigating the nuclear structure of unstable nuclei

  1. Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant

    International Nuclear Information System (INIS)

    Makgae, Mosidi E.

    2009-01-01

    The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice. The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by utilising processes that minimize, reduce, recover and recycle without exposing employees, the public and the environment to unacceptable impacts. Both International Atomic Energy Agency (IAEA) and Department of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams, for example gaseous, liquid or solid wastes.

  2. Survey on non-nuclear radioactive waste

    International Nuclear Information System (INIS)

    2003-11-01

    On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden

  3. Radioactive material air transportation

    International Nuclear Information System (INIS)

    Pader y Terry, Claudio Cosme

    2002-01-01

    As function of the high aggregated value, safety regulations and the useful life time, the air transportation has been used more regularly because is fast, reliable, and by giving great security to the cargo. Based on the International Atomic Energy Agency (IAEA), the IATA (International Air Transportation Association) has reproduced in his dangerous goods manual (Dangerous Goods Regulations - DGR IATA), the regulation for the radioactive material air transportation. Those documents support this presentation

  4. Management of radioactive wastes of iodine therapy

    International Nuclear Information System (INIS)

    Silva, Andre R.M.; Santos, Helena C.

    2015-01-01

    The main objective of waste radioactive management is to ensure the protection of man and the preservation of the environment. The regulation that established the basis for the good radioactive waste management was elaborated by the Comissao Nacional de Energia Nuclear (CNEN), in 1985. It is the CNEN-NE-6:05: 'Management radioactive waste in radioactive facilities', which although it an important standard related to radioactive waste management and help largely in the design of a management system in radioactive facilities of radioisotope users, covers the topics in a general way and does not consider individuals aspects of the different plants, as is the case of nuclear medicine units. The main objective of this study is to show the segregation and safe packaging, avoiding unnecessary exposure of professionals involved and public individuals in general

  5. Radioactivity - superstition and science

    International Nuclear Information System (INIS)

    Hinsch, Hermann

    2010-01-01

    Fairy-tales, myths, superstition - how was it fair, when we could still be afraid for witches and goblins. Where demons floated and nicks danced, the dry science has spreaded and disenchanted the life. If there would not be things like radioactivity, against which can be struggled in the collective well being. Then it is bad, clear, or good, it heals sicks, also clear. But what is now correct? In his usual humorous way the author, Dr. Hermann Hinsch, explains by means of numerous examples the phenomenon ''radioactivity'' and its effects on life. Provocantly but illustratively he illuminates, which position radioactive radiation has in our life and how and where we have already met it wantedly or unwantedly. Perhaps we must then something less shudder, but something more realism at such theme is surely not harmful.

  6. Management of radiation protection aspects in the recycling of metallurgical scrap: the report of UNECE team of specialists on radioactive contaminated scrap

    International Nuclear Information System (INIS)

    Deckers, B.

    2001-01-01

    Complete text of publication follows: In 1999, the United Nations Economic Commission for Europe (UNECE) has created a Team of Specialists on Radioactive Contaminated Metal Scrap: technically qualified representatives of the steel industry, government representatives and competent international organizations representatives have studied the problem of radioactively contaminated scrap and steel, and have proposed solutions in this context acceptable at the international level in order to harmonize the legislation, the systems of measurement of radioactivity, the levels of detection. This team has established a document which will be published by the United Nations, and where good practices on managing radioactive metal scrap are presented, and which also contains numerous recommendations in order to harmonize legislations. The paper presents the content of the document and the main recommendations of the team. (author)

  7. Transports of radioactive materials. Legal regulations, safety and security concepts, experience

    International Nuclear Information System (INIS)

    Schwarz, Guenther

    2012-01-01

    In Germany, approximately 650,000 to 750,000 units containing radioactive materials for scientific, medical and technical applications are shipped annually by surface, air and water transports. Legally speaking, radioactive materials are dangerous goods which can cause hazards to life, health, property and the environment as a result of faulty handling or accidents in transit. For protection against these hazards, their shipment therefore is regulated in extensive national and international rules of protection and safety. The article contains a topical review of the international and national transport regulations and codes pertaining to shipments of radioactive materials, and of the protection concepts underlying these codes so as to ensure an adequate standard of safety and security in shipping radioactive materials in national and international goods traffic. (orig.)

  8. Radioactive waste: show time? - 16309

    International Nuclear Information System (INIS)

    Codee, Hans; Verhoef, Ewoud

    2009-01-01

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

  9. The amended regulations for the safe transport of radioactive materials in Japan

    International Nuclear Information System (INIS)

    Takemura, Yoshio

    1978-01-01

    To cope with the inadequacies of the laws and regulations including the Law Concerning Prevention of Radiation Injuries Due to Radioisotopes, Etc., the Amended Regulations for the Safe Transport of Radioactive Materials in Japan has been issued. It is based on the Regulations of IAEA for the Safe Transport of Radioactive Materials and the Technical Standards for the Transport of Radioactive Materials decided by the AEC of Japan. In the amended regulations, emphasis is placed on the safety design of transporting goods. They are classified in Types L, A and B according to shock resistance and fire resistance, and the quantities of radioisotopes allowed to be contained in respective types are specified. The following matters are described: basic ideas concerning the types of transporting goods, test standards for the goods, transport standards for the goods, and nondestructive test apparatuses in transport. (Mori, K.)

  10. Determination of environmental radioactivity, 8

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  11. Radioactive waste management and regulation

    International Nuclear Information System (INIS)

    Willrich, M.; Lester, R.K.; Greenberg, S.C.; Mitchell, H.C.; Walker, D.A.

    1977-01-01

    Purpose of this book is to assist in developing public policy and institutions for the safe management of radioactive waste, currently and long term. Both high-level waste and low-level waste containing transuranium elements are covered. The following conclusions are drawn: the safe management of post-fission radioactive waste is already a present necessity and an irreversible long-term commitment; the basic goals of U.S. radioactive waste policy are unclear; the existing organization for radioactive waste management is likely to be unworkable if left unchanged; and the existing framework for radioactive waste regulation is likely to be ineffective if left unchanged. The following recommendations are made: a national Radioactive Waste Authority should be established as a federally chartered public corporation; with NRC as the primary agency, a comprehensive regulatory framework should be established to assure the safety of all radioactive waste management operations under U.S. jurisdiction or control; ERDA should continue to have primary government responsibility for R and D and demonstration of radioactive waste technology; and the U.S. government should propose that an international Radioactive Waste Commission be established under the IAEA

  12. A proposal for an international tagging system for radioactive materials

    International Nuclear Information System (INIS)

    Bahran, M.

    2001-01-01

    Full text: In an earlier paper based on our experience with lost or abundant radiation sources, we have discussed the need of an international tagging system for radioactive materials for the purpose of insuring trackability, accountability and safety. In this paper we take our discussion further by presenting a proposal of establishing such an international tagging system for radioactive materials which we call ITS-RM. The elements of ITS-RM: IAEA is to be the international authority in charge of ITS-RM; Each 'significant' radiation source is to be labeled with a unique number at the point of production. This number is identified as ITS-RM number; The term 'significant' can be defined in light of current international standards; As each source is naturally possessed by some legal notion or international entity, each time this entity is changed (e.g. the source is sold, resold, transported, decommissioned etc.) the process of changing hand is registered at IAEA via the ITS-RM number; No source is to change hands without triggering ITS-RM; Even if a source finds its way to a waste facility it will remain tagged indefinitely. The requirement for ITS-RM: Legal requirement: this issue needs to be studied to find out weather anew international treaty needs to be established or ITS-RM can be applied under existing treaties; Organizational requirements: This can be easily done with the framework if IAEA and national counterparts; Consultation requirements: ITS-RM can only work if it is done through complete consultation and cooperation with manufactures. Old and current sources: An effort is to be made to survey and tag current sources; Priorities will be given as follows: first to new sources second to current sources the comes last old sources, particularly those in storage facilities; ITS-RM is not to compete with any existing safety system, national or internationally, to the contrary is to support safety. ITS-RM advantages are many but in particular we have

  13. Proposal of traceability chain for direct measurements of radioactive contamination in Cuba

    International Nuclear Information System (INIS)

    Walwyn Salas, Gonzalo; Tamayo Garcia, Jose A.; Cornejo Diaz, Nestor

    2008-01-01

    The measurements of the radioactive surface contamination are common used to demonstrate the compliance with safety regulations at national level. It is mandatory that those measurements are traceable to national standards through the suitable calibration of the monitors used for survey. In Cuba, there is not a harmonized methodology for evaluation of contamination from direct measurements and no standardized calibration service for portable monitors is routinely provided to users. The Secondary Standard Dosimetry Laboratory of Cuba has recently established the calibration service of contamination monitors in terms of instrument efficiency using the reference sources of known emission rate per unit area in accordance with international normative ISO 8769. In the present paper, is proposed a traceable scheme of direct measurements of contamination that involve the calibration at the laboratory level using multi-source method and the evaluation of contaminations at user level in terms of activity per unit area. Some improvements from the previous single-source method of calibration are explained in order to support the advantages that offer the new chain for those measurements in the country. (author)

  14. Radioactive liquid containing vessel

    International Nuclear Information System (INIS)

    Sakurada, Tetsuo; Kawamura, Hironobu.

    1993-01-01

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

  15. Radioactive facilities classification criteria

    International Nuclear Information System (INIS)

    Briso C, H.A.; Riesle W, J.

    1992-01-01

    Appropriate classification of radioactive facilities into groups of comparable risk constitutes one of the problems faced by most Regulatory Bodies. Regarding the radiological risk, the main facts to be considered are the radioactive inventory and the processes to which these radionuclides are subjected. Normally, operations are ruled by strict safety procedures. Thus, the total activity of the radionuclides existing in a given facility is the varying feature that defines its risk. In order to rely on a quantitative criterion and, considering that the Annual Limits of Intake are widely accepted references, an index based on these limits, to support decisions related to radioactive facilities, is proposed. (author)

  16. Proposal for the establishment of an emergency radioactive waste task force in Brazil

    International Nuclear Information System (INIS)

    Tello, C.C.O.; Silva, E.M.P.; Prado, M.A.S.

    1998-01-01

    A radioactive waste task force set up specifically for emergency situations would act immediately following the report of a radiological accident in order to avoid or minimize the possible radioactive waste arising from these situations. The aims of this group of specialists would be to alleviate the environmental, economical, and social impacts imposed by these situations on present and future generations. (author)

  17. Performance Improvement of a Radioactive Forced Circulation Evaporator System

    International Nuclear Information System (INIS)

    Zaki, A.A.; Hala, A.A.; Othman, E.A.

    2016-01-01

    Evaporation is a proven method for treatment of liquid radioactive wastes providing both good decontamination and high concentration. In a radioactive waste treatment plant a forced circulation evaporator is used to reduce the volume of radioactive liquid wastes arising from different applications of nuclear industries. The safe operation, limiting the composition of the liquid radioactive waste at a prescribed value, with high performance efficiency, requires good control for the evaporator operating pressure and the level of liquid waste inside the separator part of the evaporator. The aim of this work was to improve the safety and performance of a forced-circulation evaporator used in a liquid radioactive wastes treatment plant. In this respect, a level controller system for this type of evaporator was designed, where proportional (P), proportional Integral (PI) and deadbeat response controllers for the separator level system were suggested. More over, an ideal 2×2(2 inputs and 2 outputs )de coupler controller for controlling the operating pressure and the product composition was developed. Computer results demonstrated that the deadbeat response has been success fully obtained from the developed separator control system. The maximum over shoot in the unit-step response curve was reduce d to 25 % and the settling time also was reduced to more than the half; about 26 minutes using Ziegler-Nichols tuning technique.The designed de coupling controller has been found effective in achieving a good trade-off between stability and performance

  18. Piling up technology of goods irradiated by single plate source

    International Nuclear Information System (INIS)

    Xia Hezhou; Chen Yuxia; Cao Hongyun; Lin Yong; Zhou guoquan

    1999-01-01

    In the irradiation process of piling up goods in static state, four irradiation working sites and single plate source was adopted. The results showed that piling up in this way remarkably raised the irradiation quality of goods. The utilization rate of radioactive ray reached 22.27%

  19. Processing method for radioactive sludge

    International Nuclear Information System (INIS)

    Shoji, Yuichi; Kaneko, Masaaki.

    1993-01-01

    The concentration of radioactive sludges contained in a storage tank is controlled, thereafter, a filter is charged into a processing vessel to continuously conduct dewatering. Then, the radioactive sludges and an oxidizer are mixed by stirring using a stirring impeller and by vibrations using a vibrator. At the same time, thermic rays are irradiated by using infrared ray lamps to heat and decompose them. Since thermic rays reach the center of the radioactive sludges by the infrared ray lamps, ion exchange resins are sufficiently decomposed and carbonized into inorganic material. Then, a filling hardener such as mortar cement having a good flowability is charged to solidify the wastes. With such procedures, radioactive sludges can be stored under a stable condition for a long period of time by decomposing organic materials into inorganic materials and solidifying them. Further, an operator's radiation exposure dose can remarkably be reduced by applying a predetermined and a stabilization treatment in an identical processing vessel. (N.H.)

  20. Interim Action Proposed Plan for the old radioactive waste burial ground (643-E)

    International Nuclear Information System (INIS)

    McFalls, S.

    1995-12-01

    This Interim Action Proposed (IAPP) is issued by the U.S. Department of Energy (DOE), which functions as the lead agency for SRS remedial activities, and with concurrence by the U.S. Environmental Protection Agency (EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC). The purpose of this IAPP is to describe the preferred interim remedial action for addressing the Old Radioactive Waste Burial Ground (ORWBG) unit located in the Burial Ground Complex (BGC) at the Savannah River Site (SRS) in Aiken, South Carolina. On December 21, 1989, SRS was included on the National Priorities List (NPL). In accordance with Section 120 of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), DOE has negotiated a Federal Facility Agreement (FFA, 1993) with EPA and SCDHEC to coordinate remedial activities at SRS. Public participation requirements are listed in Sections 113 and 117 of CERCLA. These requirements include establishment of an Administrative Record File that documents the selection of remedial alternatives and allows for review and comment by the public regarding those alternatives. The SRS Public Involvement Plan (PIP) (DOE, 1994) is designed to facilitate public involvement in the decision-making process for permitting closure, and the selection of remedial alternatives. Section 117(a) of CERCLA, 1980, as amended, requires publication of a notice of any proposed remedial action

  1. The disposal of high level radioactive wastes. Proposed solutions and uses in Brazil

    International Nuclear Information System (INIS)

    Toledo, J.F.A.

    1992-06-01

    The characteristics of high level radioactive waste produced in nuclear plants similar to that used in Brazil is presented. Subsequently it is described the international experience, and the way to apply such knowledge to the Brazilian situation, defining the magnitude of the problem, applying a methodology to select sites, and choosing areas for the location of a repository. Once such areas are defined, it is presented the behaviour of rock mass, similar to those found in the brazilian territory, based on the requirements for a high radioactive waste repository site. Finally, two Projects are presented for countries with lithologies similar to that of Brazil. The first one is choosing sites for a high radioactive waste repository program, and the second is an investigation of rock mass responses program. (author)

  2. User's manual for applicants proposing on-site burial of self-generated radioactive waste

    International Nuclear Information System (INIS)

    Tolbert, M.E.M.; Loretan, P.A.

    1987-01-01

    This document describes, for medical and research institutions as well as industrial generators of low-level radioactive waste, the NRC or state submittal requirements for authorizing the on-site burial of self-generated radioactive waste. An important part of completing the license application for operation justifying this alternative for waste disposal over other alternatives. Reasons that might be considered acceptable might include the need to dispose of large volumes of low activity waste that would otherwise take up valuable space in commercial sites; the ability to demonstrate that this method of disposal will result in reduced exposures to the public; the ability to show that the prohibitive costs of other methods of disposal would be detrimental to the progress of significant research which generates radioactive waste. 19 refs., 3 figs., 4 tabs

  3. Radioactive Waste Repositories Administration - SURAO

    International Nuclear Information System (INIS)

    Kucerka, M.

    1998-01-01

    The Atomic Act specifies, among other things, responsibilities of the government in the field of safe disposal of radioactive wastes. To satisfy this responsibility, the Ministry of Industry and Trade has established the Radioactive Waste Repositories Administration (SURAO). SURAO's major responsibilities include: (a) the preparation, construction, commissioning, operation, and decommissioning of radioactive waste repositories and the monitoring of their environmental impacts; (b) radioactive waste management; (c) spent or irradiated nuclear fuel processing into a form suitable for storage/disposal or reuse; (d) record-keeping of received radioactive wastes and their producers; (e) administration of fund transfers as stipulated by the Atomic Act, Article 27; (f) development of proposals for specification of fees to be paid to the Nuclear Account; (g) responsibility for and coordination of research and development in the field of radioactive waste handling and management; (h) supervision of licensees' margin earmarked for the decommissioning of their facilities; (i) providing services in radioactive waste handling and management; (j) handling and management of radioactive wastes that have been transferred to the Czech Republic from abroad and cannot be sent back; (k) interim administration of radioactive wastes that have become state property. The Statute of the Administration is reproduced in full. (P.A.)

  4. The safe transport of radioactive materials

    International Nuclear Information System (INIS)

    Swindell, G.E.

    1975-01-01

    In the course of transport by road, rail, sea and air, consignments of radioactive material are in close proximity to ordinary members of the public and in most cases they are loaded and unloaded by transport workers who have no special training or experience in the handling of radioactive substances. The materials being transported cover a wide variety - ranging from small batches of short-lived radionuclides used in medical practice which can be transported in small sealed lead pots in cardboard boxes, to large, extremely radioactive consignments of irradiated nuclear fuel in flasks weighing many tons. With the growing development of nuclear power programmes the transport of irradiated fuel is likely to increase markedly. It is clear that unless adequate regulations concerning the design and assembly of the packages containing these materials are precisely set down and strictly carried out, there would be a high probability that some of the radioactive contents would be released, leading to contamination of other transported goods and the general environment, and to the delivery of a radiation dose to the transport workers and the public. An additional requirement is that the transport should proceed smoothly and without delay. This is particularly important for radioactive materials of short half-life, which would lose significant amounts of their total activity in unnecessary delays at international boundaries. Therefore, it is essential that the regulations are also enforced, to ensure that the radioactive material is contained and the surrounding radiation level reduced to a value which poses no threat to other sensitive goods such as photographic film, or to transport workers and other passengers. These regulations should be as uniform as possible on an international basis, so that consignments can move freely from one country to another with as little delay as possible at the frontiers. (author)

  5. Low-Activity Radioactive Wastes

    Science.gov (United States)

    In 2003 EPA published an Advance Notice of Proposed Rulemaking (ANPR) to collect public comment on alternatives for disposal of waste containing low concentrations of radioactive material ('low-activity' waste).

  6. A model for absorption determination of radioactive materials: application in the radio dosimetry and nutrition study

    International Nuclear Information System (INIS)

    Mesquita, C.H. de.

    1991-01-01

    A three-parameter model of the sigmoidal relationship is proposed to explain the food passage by intestinal tube. These parameters are: U = intestinal non-absorbed radioactivity; d parameter related to intestinal food dispersion; and t 50 = time to maximal appearance of material from the intestinal lumen. In order to illustrate the applications of this model and its validity, the absorption of 65 Zn from casein semi-purified diet was evaluated in rats. There was a good agreement between the predicted values and the experimental data when the sigmoidal component was added to the conventional multicompartimental equations. With this kind of model the time to maximal appearance (hours), the true absorption level, the fecal concentration and the intestinal dispersion of the ingested radioactivity material may be determined. (author)

  7. National Centre for Radioactive Ion Beams (NCRIB)

    International Nuclear Information System (INIS)

    Chintalapudi, S.N.

    1999-01-01

    A dedicated National Centre for RIB (NCRIB) proposed discussed at several forums is presented. The production of (RIB) radioactive ion beams and applications of beams leading to competitive studies in nuclear structure, nuclear reactions, condensed matter, bio-science and radioactive isotope production etc. are mentioned

  8. Radioactive waste and civil society: Toward confidence and efficiency

    International Nuclear Information System (INIS)

    Ferte, Jacques de la

    2001-01-01

    Radioactive waste management is a typical area where a confident and efficient relationship between decision makers and civil society is required to achieve progress. The Radioactive waste management community must now learn the lessons and borrow from the good and bad experiences of government and industry in the area of good governance. Key ingredients include not only good science and technology, but also an early association of stakeholders with the waste management development process, so as to care for social values and generate confidence in the public, notably at the local level. The new NEA Forum will now organise its future work around this concept, collecting and sharing the experience among its members, and working together in an on-going multi-year programme

  9. Hydrogeologic modelling in support of a proposed Deep Geologic Repository in Canada for low and intermediate level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Sykes, J.F.; Normani, S.D.; Yin, Y. [Waterloo Univ., ON (Canada). Dept. of Civil and Environmental Engineering; Sykes, E.A.; Jensen, M.R. [Nuclear Waste Management Organization, Toronto, ON (Canada)

    2009-07-01

    Ontario Power Generation (OPG) has proposed the construction of a Deep Geologic Repository (DGR) for low and intermediate level radioactive waste at the Bruce site on the shore of Lake Huron near Tiverton, Ontario. The DGR is to be excavated at a depth of about 680 m within argillaceous limestones of Ordovician age. A saturated regional-scale and site-scale numerical modelling study has been completed in order to evaluate the safety of storing radioactive waste at the site and to better understand the geochemistry and hydrogeology of the formations surrounding the proposed DGR. This paper reported on the regional-scale base-case modelling and analysis of the measured pressure profile in deep boreholes at the DGR site. The numerical modelling study provided a framework to investigate the groundwater flow system as it relates to, and potentially affects, the safety and long-term performance of the DGR. A saturated groundwater flow model was also developed using FRAC3DVS-OPG. The objective of regional-scale groundwater modelling of the Paleozoic sedimentary sequence underlying southwestern Ontario was to provide a basis for the assembly and integration of site-specific geoscientific data and to explain the influence of parameter and scenario uncertainty on predicted long-term geosphere barrier performance. The base-case analysis showed that solute transport in the Ordovician and lower Silurian is diffusion dominant. For the base-case parameters, the estimated mean life expectancy for the proposed DGR is more than 8 million years. The possible presence of a gas phase in the rock between the Cambrian and the Niagaran was not considered in the analyses of this paper. 9 refs., 2 tabs., 10 figs.

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

    International Nuclear Information System (INIS)

    Bengtsson, Gunnar.

    1989-01-01

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

  11. Estimates of surface deposition of radioactivity and radiation doses resulting from proposed NNTRP activities

    International Nuclear Information System (INIS)

    Gudiksen, P.H.; Peterson, K.R.

    1975-04-01

    The National Nuclear Test Readiness Program (NNTRP) has been developed by the AEC (now ERDA) and DOD to maintain a state of readiness for the prompt resumption of atmospheric nuclear testing if circumstances warrant such resumption. Such proposed tests would be conducted at the Pacific Test Site. The environmental consequences of the program were assessed. Estimations were made of the magnitude and distribution of radioactive debris deposited on the surface waters of the Pacific Ocean as a result of the test and of the total person-rem to the Continental U.S. and Hawaiian Islands populations. Since the proposed test series consists of a wide range of weapon yields to be detonated at various altitudes and the specific number and types of tests change with time according to national defense needs, a set of seven representative tests were selected for performing a parametric yield analysis at various burst locations and heights. The yields were selected to cover the low intermediate, intermediate, and low megaton ranges. The respective yields, detonation heights, and ground zero locations of the seven bursts were considered. The atmospheric transport and diffusion models that were used are described and the meteorological and radiological input data used, and the results of the calculations are included. (U.S.)

  12. Evaluation of radioactive inventory of nuclear ship MUTSU

    International Nuclear Information System (INIS)

    Adachi, M.

    1995-01-01

    The operation of the Nuclear Ship MUTSU was terminated in January 1992. Radioactivities and dose rates on the surfaces of reactor components were measured in order to estimate the residual radioactive inventory in the MUTSU. The predicted radioactive inventory due to neutron activation was calculated by using a computer code systems. The results show good correlation between predicted and measured values radioactivities in the core baffle plate. The radioactive inventory was estimated to be 8.4 x 10 14 Bq as of 1.5 years from the final shutdown of reactor operation. The contamination in reactor components was estimated from the contamination level measured in the Japan Power Demonstration Reactor (JPDR), from which the dose rates in the reactor room were calculated. The radioactive inventory due to contamination was estimated at 3.4 x 10 10 Bq. Some difference was found between these calculations and measurements. (Author)

  13. Technical regulations for road transport of radioactive materials

    International Nuclear Information System (INIS)

    Juul-Jensen, P.; Ulbak, K.

    1990-01-01

    The technical regulations for the transport of radioactive materials in Denmark are set down by the (Danish) National Board of Health in collaboration with the (Danish) National Institute for Radiation Hygiene in accordance with paragraph 3 of the Danish Ministry of Justice's Executive Order no. 2 of 2, January 1985 on the national road transport of dangerous goods by road, as amended by exutive order no. 251 of April 29th 1987 and no. 704 of November 1989. These regulations are presented here. They are almost identical, with only very few exceptions indicated in the publication, with the rules for Class 7 of the European convention on international transport of dangerous goods by road (ADR). In addition to the aforementioned regulations for national road transport of radioactive materials the general rules for the transport of radioactive materials found in the National Board of Health's executive order no. 721 of November 27th 1989 on the transport of radioactive materials are valid. The abovementioned executive orders, with the exception of certain supplements which are not part of the technical regulations, are also contained in this publication. (AB)

  14. Staff analysis of public comments on proposed rule 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories

    International Nuclear Information System (INIS)

    1983-12-01

    On February 25, 1981, the Nuclear Regulatory Commission published rules which establish procedures for the licensing of geologic disposal, by the US Department of Energy, of high-level radioactive wastes. On July 8, 1981, proposed technical criteria which would be used in the evaluation of license applications under those procedural rules were published in the Federal Register. The Commission received 93 comment letters on the proposed technical criteria, 89 of which were received in time for the Commission to consider in preparing the final technical criteria which were published on June 21, 1983. This document presents a detailed analysis of the comments received on the proposed rule by the Commission's staff and also contains the Rationale for the Performance Objectives of 10 CFR Part 60

  15. Proposed nomination of Yucca Mountain as a potential high-level radioactive waste repository. Correspondence and request for oral presentations for US Department of Energy public hearings

    International Nuclear Information System (INIS)

    1983-01-01

    This volume contains correspondence and requests by the public citizens for oral presentation at the public hearings for the proposed nomination of Yucca Mountain as a potential high-level radioactive waste repository. Written comments are also included on: the proposed nomination; the issues to be addressed in the Environmental Assessment; and the issues to be addressed by any Site Characterization Plan, if developed

  16. Preliminary evaluation of the activity concentration limits for consumer goods containing NORM

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Mee; Chung, Kun Ho; Ji, Young Yong; Lim, Jong Myung; Kang, Mun Ja; Choi, Guen Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-06-15

    To protect the public from natural radioactive materials, the 'Act on safety control of radioactive rays around living environment' was established in Korea. There is an annual effective dose limit of 1 mSv for products, but the activity concentration limit for products is not established yet. To suggest the activity concentration limits for consumer goods containing NORM, in this research, we assumed the 'small room model' surrounding the ICRP reference phantom to simulate the consumer goods in contact with the human bodies. Using the Monte Carlo code MCNPX, we evaluate the effective dose rate for the ICRP reference phantom in a small room with dimension of phantom size and derived the activity concentration limit for consumer goods. The consumer goods have about 1600, 1200 and 19000 Bq·kg{sup -1} for {sup 226}Ra, {sup 232}Th and {sup 40}K, and the activity concentration limits are about six times comparing with the values of building materials. We applied the index to real samples, though we did not consider radioactivity of {sup 40}K, indexes of the some samples are more than 6. However, this index concept using small room model is very conservative, for the consumer goods over than index 6, it is necessary to reevaluate the absorbed dose considering real usage scenario and material characteristics. In this research, we derived activity concentration limits for consumer goods in contact with bodies and the results can be used as preliminary screening tool for consumer goods as index concept.

  17. Preliminary evaluation of the activity concentration limits for consumer goods containing NORM

    International Nuclear Information System (INIS)

    Jang, Mee; Chung, Kun Ho; Ji, Young Yong; Lim, Jong Myung; Kang, Mun Ja; Choi, Guen Sik

    2016-01-01

    To protect the public from natural radioactive materials, the 'Act on safety control of radioactive rays around living environment' was established in Korea. There is an annual effective dose limit of 1 mSv for products, but the activity concentration limit for products is not established yet. To suggest the activity concentration limits for consumer goods containing NORM, in this research, we assumed the 'small room model' surrounding the ICRP reference phantom to simulate the consumer goods in contact with the human bodies. Using the Monte Carlo code MCNPX, we evaluate the effective dose rate for the ICRP reference phantom in a small room with dimension of phantom size and derived the activity concentration limit for consumer goods. The consumer goods have about 1600, 1200 and 19000 Bq·kg -1 for 226 Ra, 232 Th and 40 K, and the activity concentration limits are about six times comparing with the values of building materials. We applied the index to real samples, though we did not consider radioactivity of 40 K, indexes of the some samples are more than 6. However, this index concept using small room model is very conservative, for the consumer goods over than index 6, it is necessary to reevaluate the absorbed dose considering real usage scenario and material characteristics. In this research, we derived activity concentration limits for consumer goods in contact with bodies and the results can be used as preliminary screening tool for consumer goods as index concept

  18. Irradiation with x-rays of the energy 18 MV induces radioactivity in transfusion blood: Proposal of a safe method using 6 MV.

    Science.gov (United States)

    Frentzel, Katharina; Badakhshi, Harun

    2016-12-01

    To prevent a fatal transfusion-associated graft-versus-host disease, it is recommended to irradiate transfusion blood and blood components with ionizing radiation. Using x-rays from a linear accelerator of the radiotherapy department is an accepted alternative to gamma irradiation devices of the blood bank and to the orthovoltage units that are replacing the gamma irradiators today. However, the use of high energy x-rays may carry a potential risk of induced radioactivity. The objective of this study was to investigate the effect of two different energy levels, 6 and 18 MV, which are executed in routine clinical settings. The research question was if induced radioactivity occurs at one of these standard energy levels. The authors aimed to give a proposal for a blood irradiation procedure that certainly avoids induced radioactivity. For this study, the authors developed a blood bag phantom, irradiated it with x-ray energies of 6 and 18 MV, and measured the induced radioactivity in a well counter. Thereafter, the same irradiation and measuring procedure was performed with a unit of packed red blood cells. A feasible clinical procedure was developed using 6 MV and an acrylic box. With the irradiation planning system XiO, the authors generated an irradiation protocol for the linear accelerator Siemens ONCOR Anvant-Garde. Both measurement setups showed that there was induced radioactivity for 18 MV but not for 6 MV. The induced radioactivity for 18 MV was up to 190 times the background. This is significant and of clinical relevance especially since there are newborn and fetal blood recipients for whom every radiation exposure has to be strictly avoided. The irradiation of blood with x-rays from a linear accelerator of the radiotherapy department is safe and feasible, but by the current state of scientific knowledge, the authors recommend to use an x-ray energy of 6 MV or less to avoid induced radioactivity in transfusion blood.

  19. The management and disposal of radioactive waste

    International Nuclear Information System (INIS)

    Ginniff, M.E.; Blair, I.M.

    1986-01-01

    After an introduction on how radioactivity and radiation can cause damage, the three main types of radioactive wastes (high level (HLW), intermediate level (ILW) and low level (LLW)) are defined and the quantities of each produced, and current disposal method mentioned. The Nuclear Industry Radioactive Waste Executive (NIREX) was set up in 1982 to make proposals for the packaging, transportation and disposal of ILW and, if approved, to manage their implementation. NIREX has also taken over some aspects of the LLW disposal programme, and keeps an inventory of the radioactive waste in the country. The NIREX proposals are considered. For ILW this is that ILW should be immersed in a matrix of concrete, then stored in a repository, the design of which is discussed. The transportation of the concrete blocks is also mentioned. Possible sites for a suitable repository are discussed. Efforts are being made to gain public acceptance of these sites. (U.K.)

  20. Planning and consultation procedures for low-level radioactive waste disposal: a comparative analysis of overseas experience

    International Nuclear Information System (INIS)

    Kemp, R.

    1989-03-01

    The results are presented of a study the purpose of which was to learn from experience in countries other than the UK, of planning and public consultation procedures associated with the establishment of low-level radioactive waste (LLW) disposal sites. Information on LLW developments in the United States, Canada, France, Holland, Switzerland, Sweden, and West Germany was sought. Particular regard was given to the efficacy of public consultation and negotiation procedures; the key aspects bearing on the public acceptability of LLW proposals; and the form and effect of any compensation mechanisms in operation. The main findings include: (i) Public acceptability of radioactive waste proposals depends upon a combination of basic understanding, trust, consultation and negotiation. (ii) There is no overall correct approach. (iii) The greatest success overseas appears to be linked to some combination of the following elements: authority and clarity in the exposition of radioactive waste management policy; the early involvement of local authority organisations in site selection; careful attention to the potential contribution of authoritative independent advisory groups; the development and nurturing of local liaison committees to establish good communications at the local level; careful consideration of means of devolving some power to local authority level for safety reassurance; and the development of an incremental, openly negotiated approach to compensation. (author)

  1. Essays on issues relevant to the regulation of radioactive waste management

    International Nuclear Information System (INIS)

    Bishop, W.P.; Hoos, I.R.; Hilberry, N.; Metlay, D.S.; Watson, R.A.

    1978-05-01

    This document contains a collection of essays prepared by the individuals who participated in a Special Task Group for the U.S. Nuclear Regulatory Commission (NRC) for the purpose of identifying and proposing goals (or guiding principles) for the regulation of radioactive waste management. The report of the Special Task group to the NRC is contained in 'Proposed Goals for Radioactive Waste Management'. The titles of the essays are as follows: History and interpretation of radioactive waste management in the United States; The credibility issue; Assessment of methodologies for radioactive waste management; Remarks on managerial errors and public participation; Observations and impressions on the nature of radioactive waste management problems; and Goals for nuclear waste management

  2. Radioactive waste below regulatory concern

    International Nuclear Information System (INIS)

    Neuder, S.M.

    1987-01-01

    The U.S. Nuclear Regulatory Commission (NRC) published two notices in the Federal Register concerning radioactive waste below regulatory concern. The first, a Commission Policy Statement and Implementation Plan published August 29, 1986, concerns petition to exempt specific radioactive waste streams from the regulations. The second, an Advanced Notice of Proposed Rulemaking published Decemger 2, 1986, addresses the concept of generic rulemaking by the NRC on radioactive wastes that are below regulatory concern. Radioactive waste determined to be below regulatory concern would not be subject to regulatory control and would not need to go to a licensed low-level radioactive waste disposal site. The Policy Statement and Implementation Plan describe (1) the information a petitioner should file in support of a petition to exempt a specific waste stream, (2) the decision criteria the Commission intends to use for judging the petition, and (3) the internal administrative procedures to use be followed in order to permit the Commission to act upon the petition in an expedited manner

  3. Transport of radioactive materials. 2. rev. ed.

    International Nuclear Information System (INIS)

    Vogt, H.W.; Falkhof, W.; Heibach, K.; Ungermann, N.; Hungenberg, H.

    1991-01-01

    With the last changes in the Ordinance Concerning the Transport of Hazardous Goods two regulations which are important for the carrying trade were introduced: 1. The conveyer must train the driver. He must only employ reliable drivers. 2. The driver must participate in a training course (as of July 1, 1991). These obligations, which already existed in the past in regard to the transport of nuclear fuel, have been extended to include the transport of other radioactive materials. In part I the book deals with basic training courses for parcelled goods, and part II goes into the special knowledge which is required of drivers of radioactive materials. The parts consist of the following sections: 1. General regulations, 2, Responsibility when transporting hazardous goods, 3. General danger features, 4. Information on dangers and their designation, 5. The vehicle's equipment and carrying out the transport, 6. Measures for avoiding accidents. At the end of each section the participant in the course finds a series of questions which pertain to the subject matter just treated so that he can test his own learning performance. So as to make things easier for the trainee, the corect answers are listed in the appendix. As a supplementary section on radioactive materials, part II offers additional detailed explanations by experts in the field on the features of radioactive materials and the dangers they pose. In the margin - next to the instructory text - the key words are given so that the right place in the text of the instruction manual can be readily found. These key words are compiled in the appendix to form an index. (orig./HP) [de

  4. Regulation of naturally occurring radioactive materials in non-nuclear industries

    International Nuclear Information System (INIS)

    Scott, L.M.

    1997-01-01

    The volume and concentrations of naturally occurring radioactive material is large across a variety of industries commonly thought not to involve radioactive material. The regulation of naturally occurring radioactive material in the United States is in a state of flux. Inventory of naturally occurring radioactive materials is given, along with a range of concentrations. Current and proposed regulatory limits are presented. (author)

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

    International Nuclear Information System (INIS)

    Adi Abimanyu; Dwi Yuliansari N

    2013-01-01

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

  6. 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)

  7. Radioactive materials in ashes from peat fired plants

    International Nuclear Information System (INIS)

    Erlandsson, B.; Hedvall, R.

    1984-11-01

    Measurements of the gamma radiation have been used for determination of radioactive materials in peat ashes from five Swedish heating plants. The results show that the amount of radioactive materials was almost the same in all samples. The concentration of 125 Sb, 137 Cs, 144 Cs and 155 Eu were in good conformity with the concentrations found in the environment. The 235 U-concentration was hardly possible to measure. (Edv)

  8. Analysis of the Institutional Framework for Radioactive Waste Management in Bangladesh

    OpenAIRE

    Mollah, A. S.; Sattar, S.; Hossain, M. A.; Jahangir, M.H.; Salahuddin, A.Z. M.

    2016-01-01

    Bangladesh utilizes radioactive materials and radiation sources for a wide variety of peaceful purposes in industry, medicine, agriculture, research and education. At present, Bangladesh does not have nuclear power plant (NPP), so that the radioactive waste is mainly coming from above mentioned fields. Although Bangladesh has quite good infrastructure for the management of present radioactive waste, it needs improvement especially for the disposal program of the existing and future radioactiv...

  9. Radioactive waste management from nuclear facilities

    International Nuclear Information System (INIS)

    2005-06-01

    This report has been published as a NSA (Nuclear Systems Association, Japan) commentary series, No. 13, and documents the present status on management of radioactive wastes produced from nuclear facilities in Japan and other countries as well. Risks for radiation accidents coming from radioactive waste disposal and storage together with risks for reactor accidents from nuclear power plants are now causing public anxiety. This commentary concerns among all high-level radioactive waste management from nuclear fuel cycle facilities, with including radioactive wastes from research institutes or hospitals. Also included is wastes produced from reactor decommissioning. For low-level radioactive wastes, the wastes is reduced in volume, solidified, and removed to the sites of storage depending on their radioactivities. For high-level radioactive wastes, some ten thousand years must be necessary before the radioactivity decays to the natural level and protection against seismic or volcanic activities, and terrorist attacks is unavoidable for final disposals. This inevitably results in underground disposal at least 300 m below the ground. Various proposals for the disposal and management for this and their evaluation techniques are described in the present document. (S. Ohno)

  10. Radioactivity in school lunch. Concrete proposal for protecting children from unnecessary internal exposure

    International Nuclear Information System (INIS)

    Nakagawa, Naoko; Hasui, Seiichiro; Haraguchi, Yayoi

    2012-01-01

    After the reactor accident of Fukushima nuclear power plant in Japan on March 11, 2011, many food adopted widely in school food service such as rice, wheat, milk are known to have risk for radioactivity contamination. To protect all children from exposure, the authors quantitatively examined risk assessment coming from food and conclude that radioactivity due to cesium 137 in rice, wheat, and milk for school lunch should be less than 10 Bq/kg and, furthermore from 2013, as lower as possible and less than 5 Bq/kg. (S. Ohno)

  11. Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

    International Nuclear Information System (INIS)

    Moriyama, Yoshinori

    1998-01-01

    Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

  12. Radioactivity in the hydrologic environment

    International Nuclear Information System (INIS)

    Werner, L.B.

    1969-01-01

    Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

  13. Radioactivity in the hydrologic environment

    Energy Technology Data Exchange (ETDEWEB)

    Werner, L B [Isotopes, Inc., Palo Alto, CA (United States)

    1969-07-01

    Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

  14. 21 CFR 361.1 - Radioactive drugs for certain research uses.

    Science.gov (United States)

    2010-04-01

    ... Research Committee. A Radioactive Drug Research Committee, composed and approved by the Food and Drug... CFR 20.61. Investigator Chairman, Radioactive Drug Research Committee At any time a proposal is... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Radioactive drugs for certain research uses. 361.1...

  15. The merchant shipping (dangerous goods) (amendment) rules 1980 No. 789

    International Nuclear Information System (INIS)

    1980-01-01

    These Rules amend the Merchant Shipping Rules 1978 and revoke the Merchant Shipping (Dangerous Goods) (Amendment) Rules 1979. The purpose of this amendment is to update the references to the 1978 Report of the Department of Trade's Standing Advisory Committee on the Carriage of Dangerous Goods in Ships (the Blue Book) and the 1977 Edition of the International Maritime Dangerous Goods Code of IMCO (the IMDG Code), referred to in the 1978 Rules. The amendments concern, inter alia, marking of packages on board ship which contain dangerous goods, including radioactive materials (NEA) [fr

  16. Production of high intensity radioactive beams

    International Nuclear Information System (INIS)

    Nitschke, J.M.

    1990-04-01

    The production of radioactive nuclear beams world-wide is reviewed. The projectile fragmentation and the ISOL approaches are discussed in detail, and the luminosity parameter is used throughout to compare different production methods. In the ISOL approach a thin and a thick target option are distinguished. The role of storage rings in radioactive beam research is evaluated. It is concluded that radioactive beams produced by the projectile fragmentation and the ISOL methods have complementary characteristics and can serve to answer different scientific questions. The decision which kind of facility to build has to depend on the significance and breadth of these questions. Finally a facility for producing a high intensity radioactive beams near the Coulomb barrier is proposed, with an expected luminosity of ∼10 39 cm -2 s -1 , which would yield radioactive beams in excess of 10 11 s -1 . 9 refs., 3 figs., 7 tabs

  17. Provision of RPA advice to users of minor radioactive sources

    International Nuclear Information System (INIS)

    French, A.P.; Anderson, A.G.

    1991-01-01

    The problems of providing cost effective Radiation Protection Supervisor (RPS) training and appropriate storage for minor radioactive sources are discussed. Threshold limits of radioactive holdings are proposed, above which an RPS should be formally trained and specialised source storage facilities provided. Proposals are made for the provision of practical radiation protection advice without need of a detailed hazard assessment. (author)

  18. Low-level radioactive waste management in hospitals

    International Nuclear Information System (INIS)

    Peyrin, J.O.

    1991-01-01

    In medical establishments, radioisotopes are used in diagnostic techniques, in chemotherapy or in radioimmunology. Hospitable radioactive wastes are characterized by polymorphism and low activity levels in a great volume. These wastes are also associated with infectivity and toxicity. This paper makes a balance and describes new radioactive waste management proposals. 4 refs.; 3 tabs.; 1 fig

  19. Radioactive wastes: a proposal to its classification

    International Nuclear Information System (INIS)

    Domenech N, H.; Garcia L, N.; Hernandez S, A.

    1996-01-01

    On the basis of the quantities and the characteristics of the stored radioactive wastes in Cuba and the IAEA system of wastes classification, the concentration activities that would be used as limits for those categories are evaluated. This approach suggests a limit of 10 TBq/m 3 for short lived liquid wastes of Low and Intermediate Level (less than 30 years) and 5 TBq/m 3 for long lived liquid wastes (more than 30 years). For solid wastes the suggested limits are ten times lower. Taking into account the small quantities of arising wastes and to make easy its segregation, collection and disposal, a low level waste sub-classification in three new categories, whether or not they may be direct discharged, is suggested. As lower classification limit, while not specific exemption levels are established in the country, the use of an ALI min fraction is emphasized, meanwhile the total discharged activity will be no greater than 10 MBq or 100 MBq when the discharge occurs over the whole year. (authors). 6 refs., 5 tabs

  20. USA perspectives. Safety and security of radioactive sources

    International Nuclear Information System (INIS)

    Dicus, G.J.

    1999-01-01

    In contrast to the 103 licensed nuclear power plants in the United States, there are about 157,000 licenses that authorize the use of radioactive materials subject to US Atomic Energy Act. as amended. Each year the NRC receives about 200 reports of lost, stolen or abandoned radioactive sources and devices. The NRC has established a programme to review and analyze reports and other information on losses, thefts, abandonments, and discoveries of radioactive sources that helped to identify and characterize the problem with safety and security of radioactive sources in devices used under the general license programme. In summary, a large number of radioactive sources in use in the USA have a very good safety record. When used properly by trained personnel with effective regulatory oversight, the many uses of radioactive sources are safe and provide a net benefit to society. If problems occur such as overexposures or contamination of property, it is essential that hey are promptly reported to the regulatory authority. If necessary appropriate emergency response measures can be taken, and the problems analysed. In that way, effective risk-informed regulatory measures can be activated to assure the continued safety and security of radioactive sources

  1. AEC sets basic policy line on treatment and disposal of radioactive waste

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The AEC's new policy line for the treatment and disposal of radioactive wastes is explained with three tables added. The first table was prepared by MITI's Nuclear Fuel Advisory Committee regarding the projections on the amounts of radioactive wastes to be discharged from nuclear power plants, fuel fabrication plants and reprocessing plants, and the other two tables were made by the AEC committee on technical development of radioactive waste management, the one proposed the developmental steps necessary for establishing waste management technologies, and the other showed the related research and development items with target time schedule. The proper treatment and disposal of radioactive waste S are the problems that have to be resolved prior to the full development and utilization of nuclear energy. The Atomic Energy Commission set up a committee on July 29, 1975, to discuss the technologies on the management of radioactive wastes. The principle essential to the radioactive waste management was set, and it is desirable that this principle is put into practice with the cooperation and understanding of the people and all parties concerned. The countermeasures proposed will be subject to review yet as the technology makes further progress and they are as follows: on the high level radioactive waste management and the low-and intermediate-level radioactive waste management, the basic idea, targets and measures are given, and the methods for promoting experimental ocean dumping of low level radioactive wastes are proposed. (Iwakiri, K.)

  2. Some considerations about the natural atmospheric radioactive aerosol

    International Nuclear Information System (INIS)

    Renoux, A.; Madelaine, G.

    1985-01-01

    From experiments made in Brest by the use of a semi-automatic device for direct measurements of atmospheric radon (the double filter method), we obtained daily average values of Radon 222 concentration, and establish that the values obtained are completely different according to the wind direction. We establish that radioactive balance is never realized in the air between radon and its daughters RaA(Po218), RaB(Pb214) and RaC(Bi214); the state of radioactive balance strongly depends on wind direction. We also study the ionic state of the radioactive aerosol accruing from Radon 222. Using an experimental system consisting of absolute filters, diffusion batteries, cascade impactors and ions tubes, we establish the size distribution of natural radioactive aerosol. We thus show 40% of the natural atmospheric radioactivity is located on particles whose radii are inferior to 2 . 10-2 mm. A good agreement is provided between the theory and our experimental points

  3. Trasmar: automated vehicle for transport of radioactive materials

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  4. Juridical and institutional aspects of radioactive wastes

    International Nuclear Information System (INIS)

    Faria, N.M. de.

    1988-07-01

    The author proposes a discussion of a new branch of the public law - the nuclear law. The main subject is the radioactive waste. Its production is a decisive problem in the utilization of nuclear energy being one of the discussed questions from the technical, economical, political, social and juridical points of view. Countries have been striving to establish their own policies related to radioactive wastes having always in mind the man and the environmental protection. In this scenario the author developed the investigations trying to discuss juridical and institutional aspects of radioactive wastes on the international level as well as in different countries with the aim to establish the juridical basis of a radioactive wastes policy in Brazil [pt

  5. DOE reassesses civilian radioactive waste management program

    International Nuclear Information System (INIS)

    Yates, M.

    1990-01-01

    This article reports on the announcement by the Department of Energy (DOE) that the opening of a high-level radioactive nuclear waste repository site will be delayed for seven years. The article discusses DOE's reassessment plan, the restructuring of the Office of Civilian Radioactive Waste Management, site access and evaluation, the Monitored Retrievable Storage Commission proposal, and the industry's response

  6. Regulations relevant to the transport of radioactive materials in Switzerland

    International Nuclear Information System (INIS)

    Smith, L.

    1996-01-01

    As is the case in many countries, the transport of radioactive materials in Switzerland is primarily regulated by the national regulations for the transport of dangerous goods. Currently these regulations, in the case of radioactive material, incorporate the 1985 IAEA Safety Series 6 Regulations for the Safe Transport of Radioactive Material (As amended 1990). However, as is also the case in some other countries, consignors, shippers and carriers of radioactive materials must also comply with additional laws when shipping radioactive materials. The most important of these other laws and their accompanying regulations are those concerned with radiation protection (import, export and carriers licences) and nuclear power (import, export, inland transport and transit licences). This paper sets out to describe the collective requirements resulting from all three of these sets of regulations. (Author)

  7. Considerations about radioactive events and their psycho social effects

    International Nuclear Information System (INIS)

    Vasconcelos, Laercia Abreu

    1995-01-01

    This study presents some behavioral patterns which are observed in the context of a radioactive accident. Comparing three different situations involving radioactive elements, Three Mile Island (USA), Chernobyl (ISC) and Goiania (Brazil), it is observed that, despite the differences in radiological levels, the populations involved show similar response characteristics. The impact of the radioactive events on health has been the main concern of the exposed population, and the response patterns observed in the different radioactive events seem to be less variable than it was proposed in the first studies. (author)

  8. Relocation of radioactive residuals store: environment effects statement

    International Nuclear Information System (INIS)

    1984-11-01

    This Environment Effects Statement describes and assesses the likely environmental effects of the proposal to relocate the Health Commission's existing radioactive residuals store to a site within the established Dutson Downs waste disposal area, located 20 km south-east of Sale and 225 km east of Melbourne. The information presented demonstrates that the siting and construction of the proposed radioactive residuals store and the procedures to be adopted for the handling and storage of materials will not present an unacceptable risk to public health and safety, nor will it involve any significant adverse environmental effects

  9. Radioactive waste management status and trends - Issue no. 4, February 2005

    International Nuclear Information System (INIS)

    2005-03-01

    The purpose of this publication is to compile and disseminate information about the status of and trends in radioactive waste management in IAEA Member States in a timely manner. The publication is suitable for radioactive waste managers and regulators, and decision making organizations in both governmental and private sectors. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. It addresses national systems for radioactive waste management, classification of radioactive waste, sources of radioactive waste, decommissioning of nuclear facilities, predisposal management of radioactive waste, managing the consequences of best practices, data collection and reporting and highlights of the work of the IAEA and other international organizations in 2003. It ends with achievements and challenges, acronyms, abbreviations, symbols and expressions. The plan is to have the publication evolve to serve a broader audience using easy-to-understand graphical and tabular data

  10. Radioactive waste management status and trends - Issue no. 4, February 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    The purpose of this publication is to compile and disseminate information about the status of and trends in radioactive waste management in IAEA Member States in a timely manner. The publication is suitable for radioactive waste managers and regulators, and decision making organizations in both governmental and private sectors. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. It addresses national systems for radioactive waste management, classification of radioactive waste, sources of radioactive waste, decommissioning of nuclear facilities, predisposal management of radioactive waste, managing the consequences of best practices, data collection and reporting and highlights of the work of the IAEA and other international organizations in 2003. It ends with achievements and challenges, acronyms, abbreviations, symbols and expressions. The plan is to have the publication evolve to serve a broader audience using easy-to-understand graphical and tabular data.

  11. Report of safety of the characterizing system of radioactive waste

    International Nuclear Information System (INIS)

    Angeles C, A.; Jimenez D, J.; Reyes L, J.

    1998-09-01

    Report of safety of the system of radioactive waste of the ININ: Installation, participant personnel, selection of the place, description of the installation, equipment. Proposed activities: operations with radioactive material, calibration in energy, calibration in efficiency, types of waste. Maintenance: handling of radioactive waste, physical safety. Organization: radiological protection, armor-plating, personal dosemeter, risks and emergency plan, environmental impact, medical exams. (Author)

  12. The management of radioactive wastes in Canada

    International Nuclear Information System (INIS)

    1979-01-01

    Ten papers are presented, dealing with the management and environmental impact of radioactive wastes, environmental considerations related to uranium mining and milling, the management of uranium refining wastes, reactor waste management, proposals for the disposal of low- and intermediate-level wastes, disposal of nuclear fuel wastes, federal government policy on radioactive waste management, licensing requirements, environmental assessment, and internatioal cooperation in wast management. (LL)

  13. The national scheme for monitoring radioactive fallout in milk

    International Nuclear Information System (INIS)

    Green, B.M.R.

    1979-01-01

    The National Radiological Protection Board, Harwell, assumed responsibility for the national milk monitoring scheme on Jan. 1, 1979. Milk contamination provides a good guide to radioactivity in the British diet. Brief reference is made to U.K. surveys of radioactive fallout in human food prior to January 1979, and current arrangements for the sampling of milk in the U.K. are explained. The milk is analysed for 90 Sr, 137 Cs and stable calcium. Additional samples are collected to check for 131 I or other short-lived isotopes in the event of atmospheric nuclear tests or accidents involving possible releases of radioactivity. (U.K.)

  14. Radioactive wastes in the air

    International Nuclear Information System (INIS)

    1968-01-01

    Methods of preventing the pollution of air by radioactive waste from atomic centres were discussed in an Agency Symposium held in New York at the end of August. It was agreed that the atomic industry has a good safety record, and suggestions were made that there should now be a concerted effort to prevent air pollution by all industries. (author)

  15. Problems of control of radioactive waste

    International Nuclear Information System (INIS)

    Doi, Kazumi

    2000-01-01

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

  16. Security of radioactive sources. The evolving new international dimensions

    International Nuclear Information System (INIS)

    Gonzalez, Abel J.

    2001-01-01

    Security of radioactive sources has become an issue of serious public concern after the devastating terrorist attacks of 11 September 2001. Yet it is worth asking how serious the the problem actually is, given the fact that hundreds of dangerous chemicals and biological agents pose perhaps greater terrorist threats that need to be urgently reduced. Radioactive sources do not contain the type of nuclear materials that would allow someone to build a nuclear bomb and trigger a major catastrophe. Though radioactive sources can be potentially dangerous for anyone coming into close contact with them, they are safely used in everyday life for medical care and treatment, among other applications in fields of industry, agriculture, and science. However, there is increasing apprehension that radioactive sources could be turned into a terrorist tool what the media call a 'dirty bomb'. To increase the protection of radiation sources, the IAEA proposes a number of measures to strengthen regulatory control and to update its standards and expanding programmes in respect to terrorism threats. The proposals include: introducing a peer review service to appraise State regulatory infrastructures for the security of radioactive sources, including protection during transport; examining the feasibility of helping States to locate large orphan sources to bring them under regulatory control; reviewing and eventually revising the Code of Conduct on the Safety and Security of Radioactive Sources to make it more comprehensive in relation to security and to determine how compliance might be monitored; reviewing the requirements on the security of radioactive sources contained in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radioactive Sources on and updating other relevant documents; exploring the practicability of an international marking system for large significant sources and of establishing a norm for a more secure physical form

  17. Construction and equipment requirements for installations and laboratories handling unsealed radioactive materials in low and medium activity - Proposal of an Israeli standard

    Energy Technology Data Exchange (ETDEWEB)

    Ben-Shlomo, A; Schlesinger, T; Barshad, M [Soreq Nuclear Research Center, Yavne (Israel)

    1993-10-01

    Working with unsealed radioactive materials involves risks of internal or external exposure to ionizing radiation. Exposure of human beings to ionizing radiation involves adverse health effects and must be prevented or at least reduced to reasonable levels. Radiation sources in this work are unsealed radioactive materials, that may be solids, liquid or in gaseous states, and in varying toxic levels. Various works and actions that are performed on the unsealed radioactive materials have varying potentials of dispersion, contamination and exposure, so that the combination of the type of work activity, isotope characteristics and physical state dictate the internal and external exposure risks. In order to limit the exposure of the personnel of installations and laboratories which deals with unsealed radioactive materials, national and international authorities and organizations standards and procedures for the requirements of construction and equipment of such installations and laboratories. This document means to be a proposal for an Israeli standard requirements for equipment and construction of installations working with low and medium activity unsealed radioactive materials. The targets for defining the, construction and equipment, requirements are: a. Safety and proper protection of personnel and public from external and internal exposure while the work is done properly. Proper protection against the risk of contaminating the environment. c. Standardization of requirements. d. Proper design of installations and laboratories. e. Supply means for evaluation and reduction of construction costs.The equipment detailed here refers to fixed (none movable) equipment which is a part of the construction of the laboratory or installation, unless specified otherwise. The document starts with a review of the recommendations of some international organizations (WHO, IAEA, NRPB) for construction and equipment requirements for these laboratories and installations. Then the

  18. Strategy on radioactive waste management in Lithuania

    International Nuclear Information System (INIS)

    Poskas, P.; Adomaitis, J.E.

    2003-01-01

    In Lithuania about 70-80% of all electricity is generated at a single power station, Ignalian NPP which has two non-upgradable RBMK-1500 type reactors. The unit 1 will be closed by 2005. The decision on unit 2 should be made in Lithuanian Parliament very soon taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. The Government approved the Strategy on Radioactive Waste Management in 2002. Objectives of this strategy are to develop the radioactive waste management infrastructure based on modern technologies and provide for the set of practical actions that shall bring management of radioactive waste in Lithuania in compliance with radioactive waste management principles of IAEA and with good practices in force in EU Member States. Ignalina NPP is undertaking a program of decommissioning support projects, financed by grants from the International Ignalina Decommissioning Support Fund, administered by the European Bank for Reconstruction and Development. This program comprises also the implementation of investment projects in a number of pre-decommissioning facilities including the management of radioactive waste and spent nuclear fuel. (orig.)

  19. 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.)

  20. Torness: proposed nuclear power station

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  1. Radioactive waste management glossary

    International Nuclear Information System (INIS)

    1982-04-01

    Terminology used in documents published by the IAEA is frequently defined in glossaries in the separate documents so that understanding is enhanced, particularly for terms having unique meanings in the field of radioactive waste management. This has been found to be a good practice but frequently a burdensome one, too. In addition, terms in various documents occasionally were used differently. Thus, a common glossary of terms for radioactive waste management documents is believed to have merit. This glossary has been developed for use in IAEA documentation on radioactive waste management topics. The individual items have been compiled by selecting terms and definitions from thirty sources, listed on the next page, and numerous people. An effort has been made to use the definitions in internationally-accepted glossaries (e.g. ICRP, ICRU, ISO), with minimum modification; similarly, definitions in recently published IAEA documents have been respected. Nevertheless, when modifications were believed appropriate, they have been made. The glossary, stored on magnetic tape, is intended to be used as a standard for terminology for IAEA use; it is hoped that some benefits of common international terminology may result from its use in IAEA documentation

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

    International Nuclear Information System (INIS)

    Zhang Baozeng; Xia Zitong; Zou Zhaozhuang

    2014-01-01

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

  3. Ordinance on the transport of dangerous goods by road (SDR)

    International Nuclear Information System (INIS)

    1985-04-01

    This Ordinance regulates the transport of dangerous goods by road and replaces a similar Ordinance of 1972. The dangerous goods are listed in Annex A and the special provisions to be complied with for their transport are contained in Annex B. Radioactive materials, categorized as Class IVb, are included in the goods covered by the Ordinance. The Ordinance which entered into force on 1 May 1985 was amended on 9 April 1987 on a minor point and on 27 November 1989 so as to provide for special training for drivers of vehicles carrying such goods. This latter amendment entered into force on 1 January 1990. (NEA) [fr

  4. Management of radioactive waste from nuclear applications

    International Nuclear Information System (INIS)

    1997-01-01

    Radioactive waste arises from the generation of nuclear energy and from the production of radioactive materials and their applications in industry, agriculture, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. Technical expertise is a prerequisite for safe and cost-effective management of radioactive waste. A training course is considered an effective tool for providing technical expertise in various aspects of waste management. The IAEA, in co-operation with national authorities concerned with radioactive waste management, has organized and conducted a number of radioactive waste management training courses. The results of the courses conducted by the IAEA in 1991-1995 have been evaluated at consultants meetings held in December 1995 and May 1996. This guidance document for use by Member States in arranging national training courses on the management of low and intermediate level radioactive waste from nuclear applications has been prepared as the result of that effort. The report outlines the various requirements for the organization, conduct and evaluation of training courses in radioactive waste management and proposes an annotated outline of a reference training course

  5. Evaluation of transport safety analysis processes of radioactive material performed by a regulatory body

    International Nuclear Information System (INIS)

    Mattar, Patricia Morais

    2017-01-01

    Radioactive substances have many beneficial applications, ranging from power generation to uses in medicine, industry and agriculture. As a rule, they are produced in different places from where they are used, needing to be transported. In order for transport to take place safely and efficiently, national and international standards must be complied with. This research aims to assess the safety analysis processes for the transport of radioactive material carried out by the regulatory body in Brazil, from the point of view of their compliance with the International Atomic Energy Agency (IAEA) standards. The self-assessment methodology named SARIS, developed by the AIEA, was used. The following steps were carried out: evaluation of the Diagnosis and Processes Mapping; responses to the SARIS Question Set and complementary questions; SWOT analysis; interviews with stakeholders and evaluation of a TranSAS mission conducted by the IAEA in 2002. Considering only SARIS questions, processes are 100% adherent. The deepening of the research, however, led to the development of twenty-two improvement proposals and the identification of nine good practices. The results showed that the safety analysis processes of the transport of radioactive material are being carried out in a structured, safe and reliable way but also that there is much opportunity for improvement. The formulation of an action plan, based on the presented proposals, can bring to the regulatory body many benefits. This would be an important step towards convening an external evaluation, providing greater reliability and transparency to the regulatory body´s processes. (author)

  6. Lessons to be learned from radioactive waste disposal practices for non-radioactive hazardous waste management

    International Nuclear Information System (INIS)

    Merz, E.R.

    1991-01-01

    The criteria to be set up for any kind of hazardous waste disposal must always be put in perspective: 1. what are the waste characteristics? 2. what time period for safe isolation is of interest? 3. which geological disposal alternatives exist? Different approaches may be used in the short- and long-term perspective. In either case, a general procedure is recommended which involves concentrating, containing and isolating the source of toxicity, both radioactive and chemotoxic substances, as far as practicable. Waste characterization of either chemotoxic or radioactive wastes should be performed applying comparable scientifically based principles. The important question which arises is whether their hazard potential can be quantified on the basis of dose comparison regarding the morbidity effects of radiation and of chemical pollutants. Good control over the consequences of hazardous waste disposal requires threat detailed criteria for tolerable contamination of radioactive as well as chemical pollutants should be established, and that compliance with these criteria can be demonstrated. As yet, there are no well developed principles for assessing the detriment from most types of genotoxic waste other than radioactive material. The time horizon discussed for both categories of waste for their proof of safe isolation differs by a factor of about one hundred. (au)

  7. Natural analogue study for low-and-intermediate level radioactive waste shallow burial disposal

    International Nuclear Information System (INIS)

    Gu Cunli; Fan Zhiwen; Huang Yawen; Cui Anxi; Liu Xiuzheng; Zhang Jinshen

    1995-01-01

    The paper makes a comparison of low-and-intermediate level radioactive waste shallow burial disposal with Chinese ancient tombs in respects of siting, engineering structures, design principle and construction procedures. Results showed that Chinese ancient tombs are very good analogue for low-and-intermediate level radioactive waste shallow burial disposal. Long-term preservation of ancient tombs and buried objects demonstrated that low-and-intermediate level radioactive waste shallow burial disposal would be safe if suitable sites were selected, reasonable engineering structures and good backfill materials were adopted, and scientific construction procedures were followed. The paper reports for the first time the testing results of certain ancient tomb backfill materials. The results indicated that the materials have so low a permeability as 1.5 x 10 -8 cm/s , and strong adsorption to radionuclides Co and Cs with the distribution coefficients of 1.4 x 10 4 mL/g and 2.1 x 10 4 mL/g, and the retardation factors of 4.4 x 10 4 and 7.7 x 10 4 respectively. Good performance of these materials is important assurance of long-term preservation of the ancient tombs. These materials may be considered to be used as backfill materials in low-and-intermediate level radioactive shallow burial disposal. (4 figs., 10 tabs.)

  8. An overview of radioactive waste disposal procedures of a nuclear medicine department.

    Science.gov (United States)

    Ravichandran, R; Binukumar, J P; Sreeram, Rajan; Arunkumar, L S

    2011-04-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented.

  9. An overview of radioactive waste disposal procedures of a nuclear medicine department

    International Nuclear Information System (INIS)

    Ravichandran, R.; Binukumar, J.P.; Sreeram, Rajan; Arunkumar, L.S.

    2011-01-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the 131 I solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of 131 I- much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented. (author)

  10. Requirements for a radioactive waste data base

    International Nuclear Information System (INIS)

    Sato, Y.; Kobayashi, I.; Kikuchi, M.

    1990-01-01

    With the progress of nuclear fuel cycle in Japan, various types of radioactive waste will generate at each nuclear facility in the cycle. Therefor generated volume and stored quantity of waste will be supposed to increase. From the viewpoints of safety and public acceptance, by using mainframe computer it is necessary that the treatment of historical waste data, the estimation of generated waste volume and stored quantity and the investigation of research and development status of waste processing and disposal are carried out. This paper proposes design and development of the radioactive waste data base which is able to properly and correctly manage and grasp numerical and/or documentary information for generated radioactive waste. So the data base will be expected to use for planning the future management of radioactive waste. (author)

  11. Ceramic and glass radioactive waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Readey, D.W.; Cooley, C.R. (comps.)

    1977-01-01

    This report contains 14 individual presentations and 6 group reports on the subject of glass and polycrystalline ceramic radioactive waste forms. It was the general consensus that the information available on glass as a waste form provided a good basis for planning on the use of glass as an initial waste form, that crystalline ceramic forms could also be good waste forms if much more development work were completed, and that prediction of the chemical and physical stability of the waste form far into the future would be much improved if the basic synergistic effects of low temperature, radiation and long times were better understood. Continuing development of the polycrystalline ceramic forms was recommended. It was concluded that the leach rate of radioactive species from the waste form is an important criterion for evaluating its suitability, particularly for the time period before solidified waste is permanently placed in the geologic isolation of a Federal repository. Separate abstracts were prepared for 12 of the individual papers; the remaining two were previously abstracted.

  12. Qualifications of and acceptance criteria for transporting special form radioactive material

    International Nuclear Information System (INIS)

    Hovingh, J.

    1991-01-01

    A special form radioactive material is a radioactive material that is in an inert, insoluble, indispersible form such that even in the event of an accident, it will not be dispersed into the environment in a way that could have an adverse impact on public health and safety. Methods of qualifying a special form radioactive material are discussed. Interpretation of acceptance criteria are proposed for the transportation of Type B quantities of a special form radioactive material. 11 refs

  13. Cosmic disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, Y; Morisawa, S [Kyoto Univ. (Japan). Faculty of Engineering

    1975-03-01

    The technical and economical possibility and safety of the disposal of highly radioactive waste into cosmos are reviewed. The disposal of highly radioactive waste is serious problem to be solved in the near future, because it is produced in large amounts by the reprocessing of spent fuel. The promising methods proposed are (i) underground disposal, (ii) ocean disposal, (iii) cosmic disposal and (iv) extinguishing disposal. The final disposal method is not yet decided internationally. The radioactive waste contains very long life nuclides, for example transuranic elements and actinide elements. The author thinks the most perfect and safe disposal method for these very long life nuclides is the disposal into cosmos. The space vehicle carrying radioactive waste will be launched safely into outer space with recent space technology. The selection of orbit for vehicles (earth satellite or orbit around planets) or escape from solar system, selection of launching rocket type pretreatment of waste, launching weight, and the cost of cosmic disposal were investigated roughly and quantitatively. Safety problem of cosmic disposal should be examined from the reliable safety study data in the future.

  14. High purity radioactive beams at the bevalac

    International Nuclear Information System (INIS)

    Alonso, J.R.; Chatterjee, A.; Tobias, C.A.

    1979-03-01

    Peripheral nuclear fragmentation reactions of primary Bevalac heavy ion beams are used to produce secondary beams of radioactive nuclei. The large cross section and small deflection of the projectile fragments lead to high production and delivery efficiency for these beams. Dispersive beam transport allows good separation and purification of the desired secondary beams. 11 C and 19 Ne beams of high purity and good intensity (almost 0.2% of the primary beam current) are presently being used for biomedical experiments

  15. The protection of radioactive nuclide and nursing management in DSA room

    International Nuclear Information System (INIS)

    Zhang Guimin

    2009-01-01

    Objective: To discuss the protection of radioactive nuclide and nursing management in DSA room. Methods: The clinical state of the protection of radioactive 131 I nuclide and nursing management in DSA room was retrospectively summarized. Results: The standard management for the protection of radioactive nuclide in DSA room was established. The main management schemas included the management of personnel, the management of professional skills and, specialty, the management of radioactive drugs and abandoned odds and ends, preoperative health education, etc. Conclusion: The standard management can ensure that the patients get a good radionuclide therapy in DSA room, and, at the same time, the working environment can be effectively protected and the professional nursing staff can be well trained. (authors)

  16. High-level radioactive waste disposal type and theoretical analyses

    International Nuclear Information System (INIS)

    Lu Yingfa; Wu Yanchun; Luo Xianqi; Cui Yujun

    2006-01-01

    Study of high-level radioactive waste disposal is necessary for the nuclear electrical development; the determination of nuclear waste depository type is one of importance safety. Based on the high-level radioactive disposal type, the relative research subjects are proposed, then the fundamental research characteristics of nuclear waste disposition, for instance: mechanical and hydraulic properties of rock mass, saturated and unsaturated seepage, chemical behaviors, behavior of special soil, and gas behavior, etc. are introduced, the relative coupling equations are suggested, and a one dimensional result is proposed. (authors)

  17. Geologic disposal of radioactive waste: Ethical and technical issues

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1999-01-01

    Ethical goals that future people should be protected and should not have to protect themselves from our radioactive waste are claimed by geologic repository projects. The best test of sufficient protection is to show that the calculated individual doses to future farming families are well below a regulatory limit. That limit should be no greater than what is now adopted to protect the public from operating licensed facilities. Present US calculations show doses, at times well beyond 10,000 years, that exceed current accepted limits by at least three orders of magnitude. Notwithstanding, there is a good chance that the goals can still be achieved by careful technical design of the geologic confinement system. But many in the US now propose ways that would allow greater individual exposures from radionuclides that eventually leak from a geologic repository. Examples include: (a) the 10,000-year cutoff proposed by industry, the US Congress, EPA, and DOE, thus obscuring the later times when higher doses are certain to result; (b) the vicinity-average dose proposed by industry and the US Congress; (c) the probabilistic critical groups proposed by EPRI and by the National Research Council's TYMS committee; (d) proposals to rely on future humans to detect and cleanup excessive amounts of radioactivity that may escape from a repository, and (e) the move to base compliance on calculated doses from well water drawn at considerable distance from Yucca Mountain. Each of these proposals would lead to a far more lenient radiation protection standard than current standards. Each of these proposals is without sufficient scientific basis for its use as a protector of public health. Each of these proposals would violate one or more of the ethical goals. Each is made without adequate discussion and explanation and without explaining how and why it would violate one or more of the ethical goals. What if serious work on alternatives fails to produce conservatively calculated and

  18. Radioactive wastes in Oklo

    International Nuclear Information System (INIS)

    Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A.

    2006-01-01

    The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive waste of the reactors that the nature put

  19. 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)

  20. Issues of natural radioactivity in phosphates

    International Nuclear Information System (INIS)

    Schnug, E.; Haneklaus, S.; Schnier, C.; Scholten, L.C.

    1996-01-01

    The fertilization of phosphorus (P) fertilizers is essential in agricultural production, but phosphates contain in dependence on their origin different amounts of trace elements. The problem of cadmium (Cd) loads and other heavy metals is well known. However, only a limited number of investigations examined the contamination of phosphates with the two heaviest metals, uranium (U) and thorium (Th), which are radioactive. Also potassium (K) is lightly radioactive. Measurements are done n the radioactivity content of phosphates, P fertilizers and soils. The radiation doses to workers and public as well as possible contamination of soils from phosphate rock or fertilizer caused by these elements or their daughter products is of interest with regard to radiation protection. The use of P fertilizers is necessary for a sustainable agriculture, but it involves radioactive contamination of soils. The consequences of the use of P fertilizers is discussed, also with regard to existing and proposed legislation. 11 refs., 2 figs., 7 tabs

  1. The politics of radioactive waste disposal

    International Nuclear Information System (INIS)

    Kemp, R.

    1992-01-01

    Plans for radioactive waste disposal have been among the most controversial of all environmental policies, provoking vociferous public opposition in a number of countries. This book looks at the problem from an international perspective, and shows how proposed solutions have to be politically and environmentally, as well as technologically acceptable. In the book the technical and political agenda behind low and intermediate level radioactive waste disposal in the UK, Western Europe, Scandinavia and North America is examined. The technical issues and the industrial proposals and analyses and factors which have been crucial in affecting relative levels of public acceptability are set out. Why Britain has lagged behind countries such as Sweden and France in establishing Low Level Waste (LLW) and Intermediate Level Waste (ILW) sites, the strength of the 'not in my backyard' syndrome in Britain, and comparisons of Britain's decision-making process with the innovative and open pattern followed in the US and Canada are examined. An important insight into the problems facing Nirex, Britain's radioactive waste disposal company, which is seeking to establish an underground waste site at Sellafield in Cumbria is given. (author)

  2. National inventory of radioactive materials and wastes for 2012: Abstract, Synthesis report, geographical inventory, Descriptive catalogue of families, The essentials

    International Nuclear Information System (INIS)

    2012-01-01

    This extremely voluminous report first proposes an abstracted overview of the inventory of radioactive materials and wastes in France in 2012. This first part addresses the radioactive wastes globally and then their different categories (very low activity, low and medium activity and short lifetime, low activity and long lifetime, medium activity and long lifetime, high activity, wastes related to radon, wastes with historical management modes). It gives an assessment of already produced wastes and of future wastes. It describes how radioactive wastes are managed, presents the various storage centres, proposes an overview of current investigations for long lifetime or high activity wastes, indicates waste localizations, and addresses the valuable materials. Then a synthesis report addresses the radioactive wastes and their management, gives some general results, proposes a waste inventory with respect to the economic sector (electronuclear, defence, research, non-electronuclear industry, medicine), presents the various historical situations (different types of storage, mining sites, contaminated sites) and proposes fives thematic files (immersed wastes, management of used radioactive sources, wastes with a strengthened natural radioactivity, existing and projected solutions for the management of radioactive wastes in France, foreign inventories of radioactive wastes). The third part is a geographical inventory which proposes sheets of information and data for the different concerned sites in France. The fourth part proposes a presentation of radioactive wastes (classification, origin, and management, families defined with respect to lifetime and activity level, origins, parcels and packaging, production data). A last part evokes the challenges and principles of the management of radioactive materials and wastes, recalls some data from the 2010 inventory, proposes predictions of radioactive waste production by 2020 and 2030, gives a prospective assessment with

  3. Calibration with MCNP of NaI detector for the determination of natural radioactivity levels in the field.

    Science.gov (United States)

    Cinelli, Giorgia; Tositti, Laura; Mostacci, Domiziano; Baré, Jonathan

    2016-05-01

    In view of assessing natural radioactivity with on-site quantitative gamma spectrometry, efficiency calibration of NaI(Tl) detectors is investigated. A calibration based on Monte Carlo simulation of detector response is proposed, to render reliable quantitative analysis practicable in field campaigns. The method is developed with reference to contact geometry, in which measurements are taken placing the NaI(Tl) probe directly against the solid source to be analyzed. The Monte Carlo code used for the simulations was MCNP. Experimental verification of the calibration goodness is obtained by comparison with appropriate standards, as reported. On-site measurements yield a quick quantitative assessment of natural radioactivity levels present ((40)K, (238)U and (232)Th). On-site gamma spectrometry can prove particularly useful insofar as it provides information on materials from which samples cannot be taken. Copyright © 2016 The Authors. Published by Elsevier Ltd.. All rights reserved.

  4. Method of producing a solution of radioactive lanthanum-140 from radioactive barium-140 in an isotope generator and installation to carry out the method

    International Nuclear Information System (INIS)

    Akerman, K.; Jacobs, G.; Sauerwein, K.

    1979-01-01

    A method of separating radioactive lanthanum-140 from radioactive Ba-140 is proposed. The lanthanum-140 will be washed out of a sulphate precipitate and separated from Ba-140-sulphate by a granular filter mass of CaSO 4 and BaSO 4 . Details of the process are given. (UWI) [de

  5. Management of radioactive waste from non-power applications in the Netherlands

    International Nuclear Information System (INIS)

    Codee, H.D.K.

    2002-01-01

    Radioactive waste results from the use of radioactive materials in hospitals, research establishments, industry and nuclear power plants. The Netherlands forms a good example of a country with a small and in the near future ending nuclear power programme. The radioactive waste from non-power applications therefore strongly influences the management choices. A dedicated waste management company COVRA, the Central Organisation for Radioactive Waste manages all radioactive waste produced in the Netherlands. For the small volume, but broad spectrum of radioactive waste, a management system was developed based on the principle to isolate, to control and to monitor the waste. Long-term storage is an important element in this management strategy. It is not seen as a 'wait and see' option but as a necessary step in the strategy that will ultimately result in final removal of the waste. Since the waste will remain retrievable for a long time new technologies and new disposal options can be applied when available and feasible. (author)

  6. Non-radioactive stand-in for radioactive contamination. I. Non-radioactive tests

    International Nuclear Information System (INIS)

    Rohe, M.J.; Rankin, W.N.; Postles, R.L.

    1985-01-01

    Candidate non-radioactive materials for use as a stand-in for radioactive contamination during application of a high-pressure, hot water decontamination were identified and evaluated. A stand-in for radioactive contamination is needed to evaluate the decontaminability of replacement canyon cranes at the manufacturers location where actual radioactive contamination cannot be used. This evaluation was conducted using high-pressure, hot-water at 420 psi, 190 0 F, and 20 gal/min through a 1/8-in.-diam nozzle, the decontamination technique preferred by SRP Separations Department for this application. A non-radioactive stand-in for radioactive contamination was desired that would be removed by direct blast stream contact but would remain intact on surfaces where direct contact does not occur. This memorandum describes identification of candidate non-radioactive stand-in materials and evaluation of these materials in screening tests and tests with high-pressure, hot-water blasting. The following non-radioactive materials were tested: carpenter's line chalk; typing correction fluid; dye penetrant developer; latex paint with attapulyite added; unaltered latex paint; gold enamel; layout fluid; and black enamel. Results show that blue layout fluid and gold enamel have similar adherence that is within the range expected for actual radioactive contamination. White latex paint has less adherence than expected for actual radioactive contamination. The film was removed at a rate of 2 . Black enamel has more adherence than expected from actual radioactive contamination. In these tests ASTM No. 2B surfaces were harder to clean than either ASTM No. 1 or electropolished surfaces which had similar cleaning properties. A 90 0 blast angle was more effective than a 45 0 blast angle. In these tests there was no discernible effect of blast distance between 1 and 3 ft

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  8. 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)

  9. Radioactive ores from Agostinho field, Pocos de Caldas (MG), Brazil

    International Nuclear Information System (INIS)

    Fujimori, K.

    1974-01-01

    Aiming to characterize the radioactive minerals of Campo Agostinho, Pocos de Caldas - Brazil, the survey of all natural radiactive elements and their geochemical behaviors, decays and radioactive equilibrium was done. Several models of radioactive instability of the minerals or the radioactive samples were proposed to characterize the geochemistry and the mineralization of radioactive elements. The complete isotopic analysis of the elements was done by high resolution gamma spectrometry, using a Ge(Li) detector, at the temperature of liquid nitrogen, coupled to a multichannel analyser. The sample in radioactive equilibrium of Atomic Energy Comission of United States - A.S. n.6, NBL - New Brunswick Laboratory, was considered as standard sample. Fluorite, zircons, pirite, molibinite, rutile, anatase, niobophyllite, and in small ratio (bellow 0.1%) uranothorianite, coffinite, pyrochlore, monazite and apatite. (M.C.K.) [pt

  10. Radioactive contamination of honey and other bee-keeping products

    International Nuclear Information System (INIS)

    Frantsevich, L.I.; Komissar, A.D.; Levchenko, I.A.

    1990-01-01

    Great amount of dust is collected in propolis under emergency atmospheric fallouts. Specific coefficient of the product migration amounts to several m 2 per 1 kg. Propolis is a good biological indicator of radioactive fallouts. The propolis collection is inadmissible after radioactive fallouts. Cocoon residuals obtained during bees-wax separation contain many radionuclides and should be disposed in special places. Nuclides are absent in bees-wax. Nuclides accumulated absent in a bee organism migrate into honey and queen milk, the honey is contaminated mainly via biogenic path

  11. Proposal for a questionnaire to assess risk perception concerning a radioactive waste repository; Proposta de um questionario destinado a avaliar a percepcao de risco relativa a um repositorio de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    Tanimoto, Katia Suemi

    2011-07-01

    One of the key features for public acceptance of nuclear energy is the belief that radioactive waste can be managed safely, in order to protect human beings from its possible harmful effects in present and future generations. In this sense, it is essential to understand how people perceive the risk associated with radioactive waste and which the main factors driving their attitudes toward its disposal are. One of the ways to achieve this understanding is through opinion polls. In this study, a questionnaire focused on the nuclear energy acceptability issue and its association with radioactive waste management was proposed, covering the following aspects: attitudes towards radioactive waste and nuclear power, credibility on institutions and sectors responsible by the nuclear safety, identification of perceived benefits, risk perception of specific technologies and activities, perception of real risk, emotional reaction comprehension and precautionary principle. Results obtained from a pilot questionnaire application are presented and discussed in this paper. (author)

  12. Ontario hydro radioactive material transportation field guide

    International Nuclear Information System (INIS)

    Howe, W.

    1987-01-01

    The recent introduction of both the AECB Transport Packaging of Radioactive Material Regulations and Transport Canada's Transportation of Dangerous Goods Regulations have significantly altered the requirements for transporting radioactive material in Canada. Extensive additional training as well as certification of several hundred Ontario Hydro employees has been necessary to ensure compliance with the additional and revised regulatory requirements. To assist in the training of personnel, an 'active' corporate Ontario Hydro Field Guide for Radioactive Material Transport document has been developed and published. The contents of this Field Guide identify current Ontario Hydro equipment and procedures as well as the updated relevant regulatory requirements within Canada. In addition, to satisfying Ontario Hydro requirements for this type of information over two thousand of these Field Guides have been provided to key emergency response personnel throughout the province of Ontario to assist in their transportation accident response training

  13. The technologically-reinforced natural radioactivity

    International Nuclear Information System (INIS)

    2005-01-01

    Technologically-reinforced natural radioactivity comes from mining industries, geological resources and ores de-confinement, and from separation, purification, transformation and use of by-products or products. Partly based on a survey and questionnaires sent to industrial organisations, this report proposes a large and detailed overview of this kind of radioactivity for different sectors or specific activities: the French phosphate sector, the international rare Earth and heavy ores sector, the French monazite sector, the ilmenite sector, the French and international zirconium sector, the non-ferrous metal sector, the international and French drinkable, mineral and spring water sector, the international wastewater sector, the French drilling sector, the international and French geothermal sector, the international and French gas and oil sector, the international and French coal sector, the international and French biomass sector, the international and French paper-making industry, and the management of wastes with technologically-reinforced natural radioactivity in France

  14. Proposal for a research programme on geological disposal of radioactive waste in the Netherlands

    International Nuclear Information System (INIS)

    1984-06-01

    The present report sets out a tentative research program related to radiologic safety of geological disposal of radioactive waste, set against the background of present knowledge in this field. The final stage of this program has to lead to a definitive appraisal of the suitability of the site explored in that stage for disposal of high-level radioactive waste. Subsequent stages of the research effort is outlined in a critical path diagram. Radiological safety figures as the central factor in making choices. The report indicates the state of the art in different specialisms involved in the study of both natural barriers (rheology, hydrology, radionuclide transport, radiation damage) and artificial barriers (mining engineering) for geological disposal. (G.J.P.)

  15. Transport and extraction of radioactive ions stopped in superfluid helium

    NARCIS (Netherlands)

    Huang, WX; Dendooven, P; Gloos, K; Takahashi, N; Arutyunov, K; Pekola, JP; Aysto, J

    A new approach to convert a high energy beam to a low energy one, which is essential for the next generation radioactive ion beam facilities, has been proposed and tested at Jyvaskyla, Finland. An open Ra-223 alpha-decay-recoil source has been used to produce radioactive ions in superfluid helium.

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

    International Nuclear Information System (INIS)

    Griesbach, M.

    2009-01-01

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

  17. Transport of Gamma Radiography Apparatus (Dangerous Goods 1978, no. 7)

    International Nuclear Information System (INIS)

    1978-01-01

    The Minister of Transport amended the Regulations on the Transport of Dangerous Goods of 15 April 1945 by Order dated 24 August 1978. The modifications concern the safety conditions to be complied with for the transport of portable industrial gamma radiography apparatus containing sealed radioactive sources. (NEA) [fr

  18. Long-term storage of radioactive solid waste within disposal facilities

    International Nuclear Information System (INIS)

    Wakerley, M.W.; Edmunds, J.

    1986-05-01

    A study of the feasibility and implications of operating potential disposal facilities for low and intermediate level solid radioactive waste in a retrievable storage mode for extended periods of up to 200 years has been carried out. The arisings of conditioned UK radioactive waste up to the year 2030 have been examined. Assignments of these wastes to different types of underground disposal facilities have been made on the basis of their present activity and that which they will have in 200 years time. Five illustrative disposal concepts proposed both in the UK and overseas have been examined with a view to their suitability for adaption for storage/disposal duty. Two concepts have been judged unsuitable because either the waste form or the repository structure were considered unlikely to last the storage phase. Three of the concepts would be feasible from a construction and operational viewpoint. This suggests that with appropriate allowance for geological aspects and good repository and waste form design that storage/disposal within the same facility is achievable. The overall cost of the storage/disposal concepts is in general less than that for separate surface storage followed by land disposal, but more than that for direct disposal. (author)

  19. Treatment of radioactive waste - Routine or challenge? Proceedings

    International Nuclear Information System (INIS)

    2003-01-01

    The seminar had the following topics: Proposal for new legislation covering radioactive waste management in the EU, new requirements preparations for the later repository, efficient and cost effective treatment of radioactive waste water, intermediate level waste cementation, incineration of spent ion exchange resins in a triphasic mixture, application of THOR-technology on resins, new development for transportation and storage of reactor vessel parts, and conditioning of nuclear fuel containing wastes. (uke)

  20. An overview of radioactive waste disposal procedures of a nuclear medicine department

    Science.gov (United States)

    Ravichandran, R.; Binukumar, J. P.; Sreeram, Rajan; Arunkumar, L. S.

    2011-01-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented. PMID:21731225

  1. An overview of radioactive waste disposal procedures of a nuclear medicine department

    Directory of Open Access Journals (Sweden)

    R Ravichandran

    2011-01-01

    Full Text Available Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented.

  2. Radioactive waste management and disposal in Australia

    International Nuclear Information System (INIS)

    Harries, J.R.

    1997-01-01

    A national near-surface repository at a remote and arid location is proposed for the disposal of solid low-level and short-lived intermediate-level radioactive wastes in Australia. The repository will be designed to isolate the radioactive waste from the human environment under controlled conditions and for a period long enough for the radioactivity to decay to low levels. Compared to countries that have nuclear power programs, the amount of waste in Australia is relatively small. Nevertheless, the need for a national disposal facility for solid low-level radioactive and short-lived intermediate-level radioactive wastes is widely recognised and the Federal Government is in the process of selecting a site for a national near-surface disposal facility for low and short-lived intermediate level wastes. Some near surface disposal facilities already exist in Australia, including tailings dams at uranium mines and the Mt Walton East Intractable Waste Disposal Facility in Western Australia which includes a near surface repository for low level wastes originating in Western Australia. 7 refs, 1 fig., 2 tabs

  3. ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

    International Nuclear Information System (INIS)

    R.H. Little, P.R. Maul, J.S.S. Penfoldag

    2003-01-01

    This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible

  4. Protection of environmental contamination by radioactive materials and remediation of environment

    International Nuclear Information System (INIS)

    2003-05-01

    This report consisted of the environmental contamination of radioactive and non-radioactive materials. 38 important accident examples of environmental contamination of radioactive materials in the world from 1944 to 2001 are stated. Heavily polluted areas by accidents are explained, for example, Chernobyl, atomic reactor accidents, development of nuclear weapon in USA and USSR, radioactive waste in the sea. The environmental contamination ability caused by using radioactive materials, medical use, operating reactor, disposal, transferring, crashing of airplane and artificial satellite, release are reported. It contains measurements and monitor technologies, remediation technologies of environmental contamination and separation and transmutation of radioactive materials. On the environmental contamination by non-radioactive materials, transformation of the soil contamination in Japan and its control technologies are explained. Protection and countermeasure of environmental contamination of radioactive and non-radioactive materials in Japan and the international organs are presented. There are summary and proposal in the seventh chapter. (S.Y.)

  5. Swedish national plan for the management of all radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    2010-01-15

    The Swedish Radiation Safety Authority has been assigned by the government to develop a national plan for the management of all radioactive waste. This report was presented to the government 30 June 2009. The report has been developed in coordination with representatives from other authorities, trade and industry organizations, operators and other parties interested, forming a joint action group. The action proposals in this report are focused on bringing waste management outside the nuclear field, where requirements are essentially regulated by the Act on Radiation Protection, to a level comparable with the management of nuclear waste (including the management of spent nuclear fuel). The Swedish Radiation Safety Authority believes that the objective of the national waste plan is that Sweden, by 2020, will have a comprehensive waste management system whereby all types of radioactive waste will be disposed of in a safe manner. The plan will make it easier to ensure that waste sub-systems for nuclear and non-nuclear waste - which could otherwise easily be regarded as being separated from each other - do not need to be distinguished to any great extent. To ensure continuity in the work in the future, with regard to the follow-up of plans for all radioactive waste, the Swedish Radiation Safety Authority propose that the national waste plan is updated every three years. The plan can then function as the strategy document or the action plan it is intended to be, ensuring that the focus remains on the various problems associated with waste management at different times, so that the set objective can be reached by 2020. A survey was carried out to identify the problems and shortcomings that were found in the waste-management system and what measures are required to resolve them within the near future. The joint action group has contributed by describing various problems as well as by offering points of view on the action proposals which the Swedish Radiation Safety

  6. Swedish national plan for the management of all radioactive waste

    International Nuclear Information System (INIS)

    2011-01-01

    The Swedish Radiation Safety Authority has been assigned by the government to develop a national plan for the management of all radioactive waste. This report was presented to the government 30 June 2009. The report has been developed in coordination with representatives from other authorities, trade and industry organizations, operators and other parties interested, forming a joint action group. The action proposals in this report are focused on bringing waste management outside the nuclear field, where requirements are essentially regulated by the Act on Radiation Protection, to a level comparable with the management of nuclear waste (including the management of spent nuclear fuel). The Swedish Radiation Safety Authority believes that the objective of the national waste plan is that Sweden, by 2020, will have a comprehensive waste management system whereby all types of radioactive waste will be disposed of in a safe manner. The plan will make it easier to ensure that waste sub-systems for nuclear and non-nuclear waste - which could otherwise easily be regarded as being separated from each other - do not need to be distinguished to any great extent. To ensure continuity in the work in the future, with regard to the follow-up of plans for all radioactive waste, the Swedish Radiation Safety Authority propose that the national waste plan is updated every three years. The plan can then function as the strategy document or the action plan it is intended to be, ensuring that the focus remains on the various problems associated with waste management at different times, so that the set objective can be reached by 2020. A survey was carried out to identify the problems and shortcomings that were found in the waste-management system and what measures are required to resolve them within the near future. The joint action group has contributed by describing various problems as well as by offering points of view on the action proposals which the Swedish Radiation Safety

  7. Summary document on the proposed decision by the Environment Agency on the application by Devonport Royal Dockyard Limited (DML) to dispose of radioactive wastes from Devonport Royal Dockyard Plymouth. Radioactive Substances Act 1993

    International Nuclear Information System (INIS)

    2001-11-01

    The Environment Agency (the Agency) has reached a proposed decision on the application from Devonport Royal Dockyard Limited (known as DML) to dispose of radioactive waste from its premises in Plymouth. After careful consideration of the application, which included advice from health and radiological protection experts and an extended public consultation, the Agency now proposes to grant DML a new authorisation containing a series of stringent conditions to protect people and the environment. This proposed decision is now being submitted to the Secretary of State for Environment, Food and Rural Affairs and the Secretary of State for Health. This will enable the ministers to decide whether they wish to exercise their powers in relation to DML's application. The Agency is satisfied that: The contents of the proposed authorisation are consistent with European and UK law. International treaty obligations, government policy objectives and protection of public health, the food chain and the environment; The issuing of the new authorisation to DML would not have a significant environmental impact and the health risks from the discharges at the proposed limits are not significant in radiological terms; The proposed authorisation reflects the best advice on the risk to humans from low level radiation; The programme of improvements that the operator is required to carry out, together with new generally lower discharge limits will provide potentially significant environmental improvements; The proposed integrated authorisations will provide a better basis for regulation than the existing authorisations. (author)

  8. Continuing education of teachers in the early years: "Good Practices Seminar" as a proposal for teacher education and integration

    Directory of Open Access Journals (Sweden)

    Mariana Vaitiekunas Pizarro

    2017-12-01

    Full Text Available There are many studies that show challenges, demands and needs in the search for improvement of teacher education. Seeking to break with the teacher's view that "always plays the same practices", the present study aimed to evaluate the placement of teachers on a proposal for training in school through socialization of pedagogical practices considered successful by teachers called "Good Seminar Practices" and to assess the extent of this situation as a proposal for continuing education. The research, qualitative, made use of semi-structured questionnaires to map the perceptions of teachers regarding this formative proposal. The results highlight the importance of qualifying the teacher do to not summarize a make devoid of purpose and criticism, valuing teachers' ideas in order to legitimize the faculty knowledge and refine their practices surpassing the understanding of teacher as mere executor of tasks.

  9. Radioactive material packaging performance testing

    International Nuclear Information System (INIS)

    Romano, T.

    1992-06-01

    In an effort to provide uniform packaging of hazardous material on an international level, recommendations for the transport of dangerous goods have been developed by the United Nations. These recommendations are performance oriented and contrast with a large number of packaging specifications in the US Department of Transportation's hazard materials regulations. This dual system presents problems when international shipments enter the US Department of Transportation's system. Faced with the question of continuing a dual system or aligning with the international system, the Research and Special Programs Administration of the US Department of Transportation responded with Docket HM-181. This began the transition toward the international transportation system. Following close behind is Docket HM-169A, which addressed low specific activity radioactive material packaging. This paper will discuss the differences between performance-oriented and specification packaging, the transition toward performance-oriented packaging by the US Department of Transportation, and performance-oriented testing of radioactive material packaging by Westinghouse Hanford Company. Dockets HM-181 and HM-169A will be discussed along with Type A (low activity) and Type B (high activity) radioactive material packaging evaluations

  10. Multiple myeloma on polycythemia vera following radioactive phosphorus therapy

    International Nuclear Information System (INIS)

    West, W.O.

    1976-01-01

    A 74-year-old white man with established polycythemia vera was treated with radioactive phosphorus after phlebotomies alone failed to control his disease. About 2 3 / 4 years later he died of multiple myeloma. The mutagenic effect of radioactive phosphorus may have caused or possibly accelerated preexisting myeloma. Basic nonmalignant disease deserves careful consideration before radiation or radiomimetic agents are used. One might consider a probably less mutagenic drug such as hydroxyurea in patients with polycythemia vera when phlebotomy alone does not give good control of red cell mass and thrombocytosis

  11. An improved segmented gamma scanning for radioactive waste drums

    International Nuclear Information System (INIS)

    Liu Cheng; Wang Dezhong; Bai Yunfei; Qian Nan

    2010-01-01

    In this paper, the equivalent radius of radioactive sources in each segment is determined by analyzing the different responses of the two identical detectors, and an improved segmented gamma scanning is used to assay waste drums containing mainly organic materials, and proved by an established simulation model. The simulated radioactivity distributions in homogenous waste drum and an experimental heterogeneous waste drum were compared with those of traditional segmented gamma scanning. The results show that our method is good in performance and can be used for analyzing the waste drums. (authors)

  12. Eighteenth annual report of: The Radioactive Waste Management Advisory Committee

    International Nuclear Information System (INIS)

    1998-07-01

    This annual report reviews the RWMAC's work programme and progress made in 1997-1998; discusses operational and administrative matters including financial management and policy review; and presents the 1998 RWMAC work programme. Particular chapters are devoted to the management of intermediate and high level radioactive waste and spent fuel; the Dounreay Nuclear Establishment; the radioactive waste discharge authorisations. The document presents the RWMAC's review of the Ministry of Defence's radioactive waste management practices. A separate chapter is devoted to the study of radioactive waste management practices in Spain. Annexes to the report include terms of reference and membership of the Radioactive Waste Management Advisory Committee; RWMAC financial statement; declaration and register of member's interests; the RWMAC's 1998 work programme; the RWMAC's response to the Government on Proposals for the control and remediation of radioactively contaminated land

  13. Accelerator complex for a radioactive ion beam facility at ATLAS

    International Nuclear Information System (INIS)

    Nolen, J.A.

    1995-01-01

    Since the superconducting heavy ion linac ATLAS is an ideal post-accelerator for radioactive beams, plans are being developed for expansion of the facility with the addition of a driver accelerator, a production target/ion source combination, and a low q/m pre-accelerator for radioactive ions. A working group including staff from the ANL Physics Division and current ATLAS users are preparing a radioactive beam facility proposal. The present paper reviews the specifications of the accelerators required for the facility

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  15. Sealed radioactive sources and method of their production

    International Nuclear Information System (INIS)

    Benadik, A.; Tympl, M.; Stopek, K.

    1985-01-01

    The active layer of the proposed sources consists of an inorganic sorbent activated with a radioactive component in form of gel, xerogel or glass. The active particles of the inorganic sorbent have the shape of spheres 2 to 2000 μm in diameter. The sources have a tubular, cylindrical or needle shape and are compact with low leachability. They feature minimal radionuclide leakage, they are reliable and safe. Their production technology is proposed. The inorganic sorbent is put in contact with the sollution of the radioactive compound, then separated from the liquid phase, filled into containers, dried, calcined or sintered or otherwise heat-processed into glass at temperatures of 250 -1800 degC. (M.D.)

  16. Royal Decree 1749/1984 of 1 August approving the national regulations on the safe transport of dangerous goods by air together with technical instructions for the safe transport of dangerous goods by air

    International Nuclear Information System (INIS)

    1984-01-01

    This Royal Decree approves the national Regulations on the safe transport of dangerous goods by air. The Regulations as well as the attached detailed technical instructions are based on the 1981 revised text of the Annex concerning dangerous goods of the Chicago Convention on International Civil Aviation. It also covers radioactive materials. (NEA) [fr

  17. Principles for disposal of radioactive and chemical hazardous wastes

    International Nuclear Information System (INIS)

    Merz, E. R.

    1991-01-01

    The double hazard of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, flammability, corrosiveness as well as chemical reactivity on the other hand. Chemotoxic waste normally has a much more complex composition than radioactive waste and appears in much larger quantities. However, the two types of waste have some properties in common when it comes to their long-term impact on health and the environment. In order to minimize the risk associated with mixed waste management, the material assigned for ultimate disposal should be thoroughly detoxified, inertized, or mineralized prior to conditioning and packaging. Good control over the environmental consequence of waste disposal requires that detailed criteria for tolerable contamination should be established, and that compliance with these criteria can be demonstrated. For radioactive waste, there has been an extensive international development of criteria to protect human health. For non-radioactive waste, derived criteria exist only for a limited number of substances

  18. The development of radioactive waste treatment technology(IV)

    International Nuclear Information System (INIS)

    Kim, Joon Hyung; Yim, Sung Paal; Lee, Kune Woo; Yoo, Jeong Woo; Kim, Young Min; Park, Seong Chul

    1992-03-01

    Following studies were performed in the project of development of radioactive waste treatment technology. 1) Treatment of radioactive borated liquid wastes by reverse osmosis : Separation characteristics of boric acid were estimated using cellulose acetate membrane and aromatic polyamide membrane. The performance of reverse osmosis process was evaluated in terms of boric acid recovery, radiochemical rejection, and membrane flux by operating variables such as applied pressure and feed concentration. 2) Oily waste treatment : The mathematical model to estimate oil removal efficiency is to be proposed at coalescence column. 3) Treatment of radioactive laundry waste 4) Comparison of evaporation and ion-exchange 5) State of the art of high integrity container. (Author)

  19. Recommendations on the transport of dangerous goods. Model regulations. 11. revised ed.

    International Nuclear Information System (INIS)

    1999-01-01

    The Recommendations on the Transport of Dangerous Goods are addressed to governments and to the international organizations concerned with the regulation of the transport of dangerous goods. They have been prepared by the United Nations Economic and Social Council's Committee of Experts on the Transport of Dangerous Goods, and they were first published in 1956 (ST/ECA/43-E/CN.2/170). Pursuant to Resolution 645 G (XXIII) of 26 April 1957 of the Economic and Social Council and subsequent resolutions, they have been regularly amended and updated at succeeding sessions of the Committee of Experts. At its eighteenth session (28 November-7 December 1994), the Committee of Experts considered that reformatting the Recommendations on the Transport of Dangerous Goods into Model Regulations that could be directly integrated into all modal national and international regulations would enhance harmonization, facilitate regular up-dating of all legal instruments concerned, and result in overall considerable resource savings for the Governments of the Member States, the United Nations, the specialized agencies and other international organizations. At its nineteenth session (2-10 December 1996), the Committee adopted a first version of the Model Regulations on the Transport of Dangerous Goods, which was annexed to the tenth revised edition of the Recommendations on the Transport of Dangerous Goods. At its twentieth session (7-16 December 1998), the Committee adopted various amendments to the Model Regulations and new provisions including, in particular, packing instructions for individual substances and articles and additional provisions for the transport of radioactive material. The additional provisions concerning the transport of radioactive material were developed in close cooperation with the International Atomic Energy Agency (IAEA) and are based on the 1996 Edition of the IAEA Regulations for the Safe Transport of Radioactive Material which have been reformatted so as to be

  20. Radioactive material air transportation; Transporte aereo de material radioativo

    Energy Technology Data Exchange (ETDEWEB)

    Pader y Terry, Claudio Cosme [Varig Logistica (VARIGLOG), Sao Paulo, SP (Brazil)

    2002-07-01

    As function of the high aggregated value, safety regulations and the useful life time, the air transportation has been used more regularly because is fast, reliable, and by giving great security to the cargo. Based on the International Atomic Energy Agency (IAEA), the IATA (International Air Transportation Association) has reproduced in his dangerous goods manual (Dangerous Goods Regulations - DGR IATA), the regulation for the radioactive material air transportation. Those documents support this presentation.

  1. Report on current research into organic materials in radioactive waste

    International Nuclear Information System (INIS)

    Norris, G.H.

    1987-11-01

    A preliminary review of relevant recent papers on organic materials in radioactive waste is presented. In particular, the effects of chelating or complexing agents, the influence of bacteria and the role of colloids are assessed. The requirement for further radioactive waste inventory detail is indicated. Potential problem areas associated with the presence of organic materials in radioactive waste are identified and appropriate experimental work to assess their significance is proposed. Recommendations for specific further work are made. A list and diagrams of some of the more important polymer structures likely to be present in radioactive waste and their possible degradation products are appended. (author)

  2. Long term governance for radioactive waste management. Final report of Cowan2 - work package 4

    International Nuclear Information System (INIS)

    Schneider, Th.; Schieber, C.; Lavele, S.

    2006-12-01

    This report aims at identifying key features for the long term governance of radioactive waste. It is proposed by the COWAN2 Work Package 4 the purpose of which was to identify, discuss and analyse the institutional, ethical, economic and legal considerations raised by long term radioactive waste storage or disposal on the three interrelated issues of: responsibility and ownership of radioactive waste on the long term, continuity of local dialogue between stakeholders and monitoring of radioactive waste management facilities, and compensation and sustainable development. The aim is also to propose guidelines in order to better address long term issues in decision-making processes and start long term governance

  3. Long term governance for radioactive waste management. Final report of Cowan2 - work package 4

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Th.; Schieber, C.; Lavele, S.

    2006-12-15

    This report aims at identifying key features for the long term governance of radioactive waste. It is proposed by the COWAN2 Work Package 4 the purpose of which was to identify, discuss and analyse the institutional, ethical, economic and legal considerations raised by long term radioactive waste storage or disposal on the three interrelated issues of: responsibility and ownership of radioactive waste on the long term, continuity of local dialogue between stakeholders and monitoring of radioactive waste management facilities, and compensation and sustainable development. The aim is also to propose guidelines in order to better address long term issues in decision-making processes and start long term governance

  4. Error calculations statistics in radioactive measurements

    International Nuclear Information System (INIS)

    Verdera, Silvia

    1994-01-01

    Basic approach and procedures frequently used in the practice of radioactive measurements.Statistical principles applied are part of Good radiopharmaceutical Practices and quality assurance.Concept of error, classification as systematic and random errors.Statistic fundamentals,probability theories, populations distributions, Bernoulli, Poisson,Gauss, t-test distribution,Ξ2 test, error propagation based on analysis of variance.Bibliography.z table,t-test table, Poisson index ,Ξ2 test

  5. Northwest disposal site for LLW and ILW in China radioactive impact assessment

    International Nuclear Information System (INIS)

    Wei Kuizi; He Chunying; Lu Baozhen; Li Tingjun

    1993-01-01

    This paper describes the studies and main conclusions in site selection, design, and radioactive impact assessment of the Northwest Disposal Site of China for intermediate- and low-level radioactive wastes. At the end of the paper, further works are proposed

  6. Proposal of implementation of Environmental Management System at the Laboratory of Radioactive Waste In IPEN-SP

    International Nuclear Information System (INIS)

    Moura, Luiz Antonio Abdalla

    2008-01-01

    An increasing use of nuclear technology in the form of its several applications (electricity generation, medical, industrial, agricultural, environment and radiosterilization) is currently being observed in Brazil. Radioactive waste of high, medium or lower activity is produced in all fuel cycle and other research activities, industrial activities of fuel production and electricity generation. Appropriate and safe technologies are available for the treatment and storage of radioactive waste and, when applied, contribute for the acceptance of nuclear energy by the Society. With the increasing importance of demands related to environmental issues, the International Organization for Standardization issued the Standard ISO 14.001 - Environmental Management System, applied to all types and size of organizations, helping them to increase their environment performance. In this research, the standard requirements were commented in detail, being particularized to the Laboratory of Radioactive Waste from IPEN, as a case study. (author)

  7. Transports of radioactive materials. Legal regulations, safety and security concepts, experience; Befoerderung radioaktiver Stoffe. Rechtsvorschriften, Sicherheits- und Sicherungskonzept, Erfahrungen

    Energy Technology Data Exchange (ETDEWEB)

    Schwarz, Guenther

    2012-07-15

    In Germany, approximately 650,000 to 750,000 units containing radioactive materials for scientific, medical and technical applications are shipped annually by surface, air and water transports. Legally speaking, radioactive materials are dangerous goods which can cause hazards to life, health, property and the environment as a result of faulty handling or accidents in transit. For protection against these hazards, their shipment therefore is regulated in extensive national and international rules of protection and safety. The article contains a topical review of the international and national transport regulations and codes pertaining to shipments of radioactive materials, and of the protection concepts underlying these codes so as to ensure an adequate standard of safety and security in shipping radioactive materials in national and international goods traffic. (orig.)

  8. Radioactive waste management: International peer reviews

    International Nuclear Information System (INIS)

    Warnecke, E.; Bonne, A.

    1995-01-01

    The Agency's peer review service for radioactive waste management - known as the Waste Management Assessment and Technical Review Programme (WATRP) - started in 1989, building upon earlier types of advisory programmes. WATRP's international experts today provide advice and guidance on proposed or ongoing radioactive waste management programmes; planning, operation, or decommissioning of waste facilities; or on legislative, organizational, and regulatory matters. Specific topics often cover waste conditioning, storage, and disposal concepts or facilities; or technical and other aspects of ongoing or planned research and development programmes. The missions can thus contributed to improving waste management systems and plans, and in raising levels of public confidence in them, as part of IAEA efforts to assist countries in the safe management of radioactive wastes. This article presents a brief overview of recent WATRP missions in Norway, Slovak Republic, Czech Republic and Finland

  9. Immobilization of hazardous and radioactive waste into glass structures

    International Nuclear Information System (INIS)

    Wicks, G.G.

    1997-01-01

    As a result of more than three decades of international research, glass has emerged as the material of choice for immobilization of a wide range of potentially hazardous radioactive and non-radioactive materials. The ability of glass structures to incorporate and then immobilize many different elements into durable, high integrity, waste glass products is a direct function of the unique random network structure of the glassy state. Every major country involved with long-term management of high-level radioactive waste (HLW) has either selected or is considering glass as the matrix of choice for immobilizing and ultimately, disposing of the potentially hazardous, high-level radioactive material. There are many reasons why glass is preferred. Among the most important considerations are the ability of glass structures to accommodate and immobilize the many different types of radionuclides present in HLW, and to produce a product that not only has excellent technical properties, but also possesses good processing features. Good processability allows the glass to be fabricated with relative ease even under difficult remote-handling conditions necessary for vitrification of highly radioactive material. The single most important property of the waste glass produced is its ability to retain hazardous species within the glass structure and this is reflected by its excellent chemical durability and corrosion resistance to a wide range of environmental conditions. In addition to immobilization of HLW glass matrices are also being considered for isolation of many other types of hazardous materials, both radioactive as well as nonradioactive. This includes vitrification of various actinides resulting from clean-up operations and the legacy of the cold war, as well as possible immobilization of weapons grade plutonium resulting from disarmament activities. Other types of wastes being considered for immobilization into glasses include transuranic wastes, mixed wastes, contaminated

  10. Transport of radioactive material by air, proposal for a revision of the regulation

    International Nuclear Information System (INIS)

    Devillers, C.; Ringot, C.

    1989-01-01

    The regulation should be modified in such a way that the packages used for the air transport of radioactive material presenting a high level of potential danger be designed to fulfill their safety functions for a large fraction of the conditions likely to be encountered in an aircraft accident

  11. Effect of the proposed adoption of the International Atomic Energy Agency regulations, 1985 revision, on the U.S. radioactive waste transportation industry

    International Nuclear Information System (INIS)

    Benda, G.A.; Lewis, M.S.; Allen, J.H.

    1989-01-01

    The Nuclear Regulatory Commission (NRC) is proposing changes to 10CFR 71 transportation regulations to achieve compatibility with the 1985 IAEA regulations. The intent of these changes is to be more compatible with the international standard on shipping containers, package requirements, and performance criteria. The NRC has, however, modified part of its regulations to restrict the packaging of LSA by limiting the total activity rather than adopting the IAEA standard. This paper addresses how the proposed regulations will affect the low-level radioactive waste transportation industry. It describes the impacts on the transportation industry in three major areas-IAEA consistency, economic impact, and risk assessment. Available transport data from the Barnwell disposal site was used in the analysis of the proposed changes. The impacts addressed include possible increased radiation exposures, transportation risks and liability, transportation and processing costs, and waste disposal costs resulting in little health and safety benefit. Although the health and safety benefits of any change to the current regulations are minimal, suggested alternatives to the proposed regulations are discussed that more closely conform with the international standards while still maintaining health and safety

  12. Evaluation on radioactive level and quality of aquatic environment in Suzhou

    International Nuclear Information System (INIS)

    Yu Rongsheng; Tu Yu; Zhang Ruiju

    2007-01-01

    Objective: To assess the quality grade of water source in Suzhou in terms of the radioactive level. Methods: The levels of total α and total β activities in samples of water were detected by relative measurement with medium thickness using model BH 1216 low level α and β detector. 241 Am and pure potassium chloride were used as reference radioactive sources. Results: Among all samples collected, the measured levels varied from (2.62 ± 0.17) x 10 -2 to (8.48±2.80) x 10 -2 Bq/L for total α and (0.77 ± 0.47) x 10 -1 to (3.75 ± 0.26) x 10 -1 Bq/L for total β, the average levels of β/α were from 1.6 to 7.2. Conclusions: The radioactivity level of water source in Suzhou was within the natural background range, free from contamination of artificial radioactive nuclides, which was regarded as good in quality in terms of radioactive level. It is shown that the radioactivity of well water was highest among all investigated water sources. (authors)

  13. Options in radioactive waste management revisited: a proposed framework for robust decision making.

    Science.gov (United States)

    Flüeler, T

    2001-08-01

    Deregulation, with concurrent pressure on electricity utilities, has fundamentally changed the once-"closed" radioactive waste management system controlled by the so-called "nuclear establishment." Advocacy coalitions may change-who knows in which direction-but policy learning may also take place. This article presents a framework to evaluate the management options for a specified concept of "sustainability." When weighing the different objectives in view of the long-lasting potential danger of radiotoxic substances, the overall goal of a sound waste management system is to demonstrate safety. The first-priority objective of a disposal system, therefore, is its stability so that it can comply with the protection goal, that is, the long-term protection of humans and the environment from ionizing radiation. The complementary objective is flexibility, defined here as intervention potential. Because trade-offs within the "sustainability triangle" of ecology, economy, and society are unavoidable, the concept of "integral robustness"-both technical and societal-is introduced into radioactive waste management. A system is robust if it is not sensitive to significant parameter changes. In the present case, it has to have a conservative, passively stable design with built-in control and intervention mechanisms. With regard to technical implementation, a concept called "monitored long-term geological disposal" is presented. Such an "extended" final disposal concept emphasizes technical robustness, recognizes evaluation demands (for a potential break-off of a project), and enhances process-based transparency. This open approach admittedly sets high challenges with regard to technicalities as well as the institutional setting and the management process. It requires "mutual learning" by and from all stakeholders to achieve a truly sustainable radioactive waste management system.

  14. Public service of radioactive waste management for small producers

    International Nuclear Information System (INIS)

    Zeleznik, N.; Mele, I.

    2001-01-01

    By Governmental decree of May 1999, the Agency for radwaste management (ARAO) was authorized as a state public service for managing radioactive waste from small producers. By this decree the ARAO also became the operator of the Central Interim Storage intended for radioactive waste from industry, medicine and research, located in Brinje near Ljubljana. In this paper the current situation will be presented, together with plans for improving public service and the necessary refurbishment and modernization of the storage facility. Execution of the proposed measures, modifications and a modernization will ensure proper and safe storing of all radioactive waste from small producers produced in Slovenia, thus fulfilling the requirements for full operation of the public service of radioactive waste management.(author)

  15. The problems and suggestions on supervision of the radioactive material transport

    International Nuclear Information System (INIS)

    Cao Fangfang; Que Ji; Zhang Min; Pan Yuting

    2012-01-01

    The developing background and importance of the rules on supervision of the radioactive material transport are discussed in the paper. Based on the existing problems found in the process of implementing the rule 'Regulations for the safe transport of Radioactive Material', some countermeasures are proposed. (authors)

  16. How good is the education of the test personnel in radiography?

    International Nuclear Information System (INIS)

    Pittlik, A.; Soelter, B.

    1999-01-01

    The education of the test personnel in Radiography intends to ensure the responsible use of radioactive sources by a high quality consciousness and a good technical knowledge. The German Society for Non-Destructive Testing (DGZfP) arranges relevant courses that are described in detail. (orig.) [de

  17. Radioactivity Portal Monitor: An actual application and its unconventional detector

    International Nuclear Information System (INIS)

    Izraelevitch, F.; Matatagui, E.; Regueiro Veiga, J.L.

    2012-01-01

    A Radioactivity Portal Monitor is an instrument designed to be used at traffic check points to detect the presence of ionizing radiation in goods, vehicles, people, in critical places such as those at border road crossing, airports and seaports, the entrance at nuclear facilities etc. and alert the officer to the presence of radioactive and nuclear material. We have developed and built, and is in operation a Radioactivity Portal Monitor for gamma radiation. The detector and the associated electronics does not follow a conventional design concept and is based on a pressurized ionization chamber with a very large sensitive volume (60 liters) and a very large length (2 meters), and a very low level DC electronics (fAmp). The System is simple, and its operational characteristics are excellent. The reference radiation level is the background radiation, which is continuously measured, and compared with the radiation level measured when a subject (vehicle, person, good) goes trough the Monitor. The system automatically takes a decision, and alert the officer with an alarm signal if the detected radiation level is larger than the reference (dynamical) level. We will describe the designed system and some of its characterization results will be shown (author)

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

    International Nuclear Information System (INIS)

    Wakaida, Yasuo.

    1996-01-01

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

  19. The use of radioactive materials in German schools. Obstacles and chances

    International Nuclear Information System (INIS)

    Vahlbruch, Jan-Willem

    2015-01-01

    The basics for the understanding of radioactivity and radioprotection are set in the secondary school. Therefore the German-Swiss Radiation Protection Association already is trying to support the appropriate teaching of relevant topics in school for a long time. Unfortunately experiments with radioactive material are hampered in Germany by complex and confusing legislation. In this contribution the framework is described which is given by the German legislation for the use of radioactive sources in secondary schools. Additionally proposals for different simple experiments with radioactivity are presented which can be easily implemented in teaching and alternative methods are introduced like e.g. virtual experiments.

  20. Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

    International Nuclear Information System (INIS)

    McAulay, I.R.

    1996-01-01

    Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials

  1. Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

    Energy Technology Data Exchange (ETDEWEB)

    McAulay, I R [Trinity Coll., Dublin (Ireland). Physical Lab.

    1996-10-01

    Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials.

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  3. Research on near-surface disposal of very low level radioactive waste

    International Nuclear Information System (INIS)

    Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

    2012-01-01

    Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

  4. Nuclide-related exemption limits for radioactive materials

    International Nuclear Information System (INIS)

    Przyborowski, S.; Scheler, R.

    1984-01-01

    A procedure has been proposed for setting nuclide-related exemption limits for radioactive materials. It consists in grading the radionuclides into 4 groups of radiotoxicity and assigning only one activity limit to each of them. Examples are given for about 200 radionuclides. The radiation exposures resulting from a continuous steady release of activity fractions or from short-period release of the entire activity were assessed to remain below 0.1 ALI in both of these borderline cases, thus justifying the license-free utilization of radioactive materials below the exemption limits. (author)

  5. Veracity in big data: How good is good enough.

    Science.gov (United States)

    Reimer, Andrew P; Madigan, Elizabeth A

    2018-01-01

    Veracity, one of the five V's used to describe big data, has received attention when it comes to using electronic medical record data for research purposes. In this perspective article, we discuss the idea of data veracity and associated concepts as it relates to the use of electronic medical record data and administrative data in research. We discuss the idea that electronic medical record data are "good enough" for clinical practice and, as such, are "good enough" for certain applications. We then propose three primary issues to attend to when establishing data veracity: data provenance, cross validation, and context.

  6. Order of 15 September 1992 concerning the Regulations for the transport of dangerous goods (provisions on road transport and alphabetical list of goods) (Dangerous Goods 1992 No. 1)

    International Nuclear Information System (INIS)

    1992-01-01

    The specific provisions of the 1945 Order concerning the transport of dangerous goods by road have been repealed by this 1992 Order, with few exceptions. The provisions covering both road and other transport by land no longer apply to road transport, except for Appendix 6 which concerns flexible lead and equipment for pumping hydrocarbons. The repealed provisions have been replaced by provisions annexed to the 1992 Order. The Annexes concern materials and their mode of transport, transport equipment and the alphabetical list of materials which include radioactive materials. (NEA)

  7. Activities of the IAEA in the area of radioactive waste management

    International Nuclear Information System (INIS)

    Efremenkov, V.M.

    1998-01-01

    The IAEA activity in the area of radioactive waste management mainly concentrates on three areas, namely: (i) the establishing of international principles and standards for the safe management of radioactive waste; (ii) to promote the development and improvements of waste processing technologies, including handling, treatment, conditioning, packaging, storage and disposal of waste; and (iii) assisting developing Member States in establishing good waste management practice through dissemination of technical information, providing technical support and training. These activities are carried out by the Waste Technology Section, Department of Nuclear Energy, and the Waste Safety Section, Department of Nuclear Safety. The Waste Technology Section's activities are organized into four subprogrammes covering: the handling, processing and storage of radioactive waste; radioactive waste disposal; technology and management aspects of decontamination, decommissioning and environmental restoration; and waste management information and support services

  8. Radioactivity--Killer or the "Elixir of Life"?

    Science.gov (United States)

    Kennedy, Paula

    2011-01-01

    It is frequently said that a good teacher will spice up their lessons with anecdotes and stories associated with the subject as these help to bring the subject alive. This is true in teaching radioactivity but it is not always easy to find a useful fund of stories--especially for a non-specialist. Paula Kennedy shares the stories and anecdotes…

  9. Modelling radioactivity in the environment

    International Nuclear Information System (INIS)

    Scott, E.M.

    2003-01-01

    Just as an environmental model typically will be composed of a number of linked sub-models, representing physical, chemical or biological processes understood to varying degrees, this volume includes a series of linked chapters exemplifying the fundamental nature of environmental radioactivity models in all compartments of the environment. Modelling is an often misunderstood and maligned activity and this book can provide, to a broad audience, a greater understanding of modelling power but also some of the limitations. Modellers and experimentalists often do not understand and mistrust each other's work yet they are mutually dependent, in the sense that good experimental science can direct good modelling work and vice-versa. There is an increasing reliance on model results in environmental management, yet there is also often misuse and misrepresentation of these results. This book can help to bridge the gap between unrealistic expectations of model power and the realisation of what is possible, practicable and feasible in modelling of environmental radioactivity; and finally, - modelling tools, capacity and power have increased many-fold in a relatively short period of time. Much of this is due to the much-heralded computer revolution, but much is also due to better science. It is useful to consider what gap if any still remains between what is possible and what is necessary

  10. 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.)

  11. Radioactive waste disposal in deep geologic deposits. Associated research problems

    International Nuclear Information System (INIS)

    Rousset, G.

    1992-01-01

    This paper describes the research associated problems for radioactive waste disposal in deep geologic deposits such granites, clays or salt deposits. After a brief description of the underground disposal, the author studies the rheology of sedimentary media and proposes rheological models applied to radioactive wastes repositories. Waste-rock interactions, particularly thermal effects and temperature distribution versus time. 17 refs., 14 figs

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

    International Nuclear Information System (INIS)

    2009-05-01

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

  13. Interim report to the Nuclear Regulatory Commission on radioactive waste classification

    International Nuclear Information System (INIS)

    King, W.C.; Cohen, J.J.

    1977-01-01

    The Lawrence Livermore Laboratory assisted the Nuclear Regulatory Commission in the development of a radioactive waste classification system that will satisfy technical, environmental, and societal concerns. This is an interim report to the NRC on work accomplished to date. It describes a proposed waste-classification system that is based on the final disposition of waste material. The system consists of three classes of radioactive waste. The classification of any radioactive waste will depend primarily on its hazard potential. Other characteristics such as longevity (half-size) will be considered also. The levels of hazard that differentiate the three classes of radioactive waste will be determined by ongoing work. This report describes other work to be completed before a suitable radioactive waste-classificaion system is established

  14. Security in the transport of radioactive material - interim guidance for comment

    International Nuclear Information System (INIS)

    Legoux, P.; Wangler, M.

    2004-01-01

    While the IAEA has provided specific guidance for physical protection in the transport of nuclear material, its previous publications have only provided some general guidelines for security of non-nuclear radioactive material in transport. Some basic practical advice has been provided in the requirements of the International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources (BSS) [1]. These guidelines were primarily directed toward such issues as unintentional exposure to radiation, negligence and inadvertent loss. Recently, the IAEA published a document on the security of sources, which included some general guidance on providing security during transport of the sources. However, it is clear that more guidance is needed for security during the transport of radioactive material in addition to those already existing for nuclear material. Member States have requested guidance on the type and nature of security measures that might be put in place for radioactive material in general during its transport and on the methodology to be used in choosing and implementing such measures. The purpose of the TECDOC on Security in the Transport of Radioactive Material being developed by the IAEA is to provide an initial response to that request. This interim guidance is being developed with a view to harmonizing the security guidance - as much as possible - with existing guidance from the IAEA for the transport of radioactive sources and nuclear material. It is also intended to harmonize with model requirements developed in 2002-2003 by the United Nations Economic and Social Council's Committee of Experts on the Transport of Dangerous Goods and on the Globally Harmonised System of Classification and Labelling of Chemicals which was issued as general security guidelines for all dangerous goods, including radioactive material, and that will shortly be implemented as binding regulations by the international modal authorities

  15. Security in the transport of radioactive material - interim guidance for comment

    Energy Technology Data Exchange (ETDEWEB)

    Legoux, P.; Wangler, M. [International Atomic Energy Agency, Vienna (Austria)

    2004-07-01

    While the IAEA has provided specific guidance for physical protection in the transport of nuclear material, its previous publications have only provided some general guidelines for security of non-nuclear radioactive material in transport. Some basic practical advice has been provided in the requirements of the International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources (BSS) [1]. These guidelines were primarily directed toward such issues as unintentional exposure to radiation, negligence and inadvertent loss. Recently, the IAEA published a document on the security of sources, which included some general guidance on providing security during transport of the sources. However, it is clear that more guidance is needed for security during the transport of radioactive material in addition to those already existing for nuclear material. Member States have requested guidance on the type and nature of security measures that might be put in place for radioactive material in general during its transport and on the methodology to be used in choosing and implementing such measures. The purpose of the TECDOC on Security in the Transport of Radioactive Material being developed by the IAEA is to provide an initial response to that request. This interim guidance is being developed with a view to harmonizing the security guidance - as much as possible - with existing guidance from the IAEA for the transport of radioactive sources and nuclear material. It is also intended to harmonize with model requirements developed in 2002-2003 by the United Nations Economic and Social Council's Committee of Experts on the Transport of Dangerous Goods and on the Globally Harmonised System of Classification and Labelling of Chemicals which was issued as general security guidelines for all dangerous goods, including radioactive material, and that will shortly be implemented as binding regulations by the international modal

  16. Continuous Tracking of RFID Tagged Radioactive Sources

    International Nuclear Information System (INIS)

    Broide, A.; Marcus, E.; Gabay, Y.; Miron, E.; Seif, R.; Wengrowicz, U.; Kadmon, Y.; Tirosh, D.

    2008-01-01

    The prevention of radiation hazards due to radioisotopes is one of the concerns of the Atomic Energy Agency (IAEA). In a series of international conferences held in the last five years) this issue was discussed thoroughly. One of the conclusions was that strict management of radioactive sources is essential. The management of radioactive sources would help to prevent transference of radioactive materials to unauthorized personal. For this purpose, states should make a concerted effort to follow the principles of the Code of Conduct on the Security of Radioactive Sources(2). In this context, the identification of roles and responsibilities of governments, licensees and international organizations is vital(3). The referred activities are primarily related to control over radioactive sources and enhance the tracking ability of radiation sources . In this paper, a proposed Radioactive Sources Tracking System is presented. This system facilitates real time monitoring capability of fixed and mobile radiation sources. The system provides the location of the source and indication whether the source is inside or outside the shielding container. The information about the sources location and condition can be used to coordinate a fast response in case of any attempt to steal or tamper with a source. These goals are achieved by using GPS (Global Positioning System), RFID (Radio Frequency Identification) and control and management software

  17. Radioactive waste management in the Netherlands. A practical solution in full operation

    International Nuclear Information System (INIS)

    Codee, H.D.K.

    2000-01-01

    All radioactive waste produced in the Netherlands is managed by COVRA, the central organization for radioactive waste. The Netherlands forms a good example of a country with a small and in the near future ending nuclear power programme. However, radioisotope production, nuclear research and other industrial activities will continue to produce radioactive waste. For the small volume, but broad spectrum of radioactive waste, the Netherlands has developed a management system based on the principles to isolate, to control and to monitor the waste. Long term storage is an important element in the management strategy that will ultimately result in final removal of the waste. Since the waste will remain retrievable for a long time, new technologies and new disposal options can be applied when available and feasible. (author)

  18. Equity issues in radioactive waste management

    International Nuclear Information System (INIS)

    Kasperson, R.E.

    1984-01-01

    The 15 papers in this book deal with the equity issues of locus, legacy and labor/laity as they occur in the nuclear industry's handling of radioactive wastes. The intent is to identify and clarify inequities in alternative approaches to radioactive waste management in a way that will inform current public policy deliberations and planning. The papers are arranged in five parts which put the problem in perspective, then define the locus, the legacy, and the labor problem, and conclude with a set of proposals for a more equitable management. A separate abstract was prepared for each of the 15 chapters selected for INS, EDB, and EPA

  19. The status of radioactive waste management: needs for reassessments

    International Nuclear Information System (INIS)

    Eisenbud, M.

    1980-01-01

    Plicies that dictate the procedures for management of radioactive wastes are influenced by superstition and require fresh examination. It is shown that low level wastes from biomedical and clinical laboratories could be safely disposed of without any restrictions related to their radioactivity. High level waste management should be reexamined to determine the length of isolation required; thought by some to be 1000 years, and to investigate the use of geological repositories. It is also proposed that many forms of waste could be safely disposed of in the oceans, as data has already been accumulated from the fallout of massive quantities of radioactive debris. (H.K.)

  20. 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.)

  1. The disposal of radioactive waste in Sweden, West Germany and France

    International Nuclear Information System (INIS)

    1987-01-01

    Representatives from Humberside, Lincolnshire and Bedford County Councils have visited radioactive waste disposal sites in Sweden (Forsmak), West Germany (Konrad) and France (Centre de la Manche). The British regions are those in which there are sites which NIREX (Nuclear Industry Radioactive Waste Executive) have been investigating with a view to disposing of low and intermediate level radioactive waste. The sites, methods of disposal, cost and radiation levels are detailed for the three countries visited and compared with the NIREX proposals for shallow trench disposal for wastes at low and intermediate levels. The general findings were that the three countries visited are more advanced in the development of policies and practices for radioactive waste disposal with better technical alternatives to the NIREX proposals. Secondly, that the overall cost may be greater than for a shallow repository but would still be less than 1% of the nuclear electricity generation cost. Thirdly, the need to gain and sustain public acceptance for what was being done was more clearly understood and acted on than in the UK. (U.K.)

  2. Wrong low level radioactive waste management in hospitals and improvement steps

    International Nuclear Information System (INIS)

    Keren, M.

    2000-01-01

    Hospitals are producers of great amounts of all kind of waste, including dangerous waste. The dangerous waste can be toxic, biological, radioactive, or a mixture of several kinds. There are clear procedures how to store and treat every kind of waste separately, according to its characteristics. Radioactive waste should be disposed only to a central radwaste disposal site. If the radioactive waste is mixed with biological waste, and contains long half-life isotopes, it should be neutralized from biological hazards before disposal to radwaste storage site. If the waste contains short half-life isotopes, it should be stored in a proper intermediate storage facility till a complete decay of the radioactive elements, and then treated as not radioactive. The existing procedures are old and a new proposal for radwaste procedures was prepared but not implemented. After several repetitive violations of the old regulations by some hospitals, it was decided to advance the implementation of the new proposal. This proposal consists of a detailed procedures for segregation, storage, decay and disposal of radwaste. It is based on the new recommendations of the IAEA. The responsibility for implementing the regulations is on the producers of the waste. This paper summarizes the violations and describes the main recommendations for improving procedures. The competent authority used moderate enforcement steps because of the delay in the implementation of the new procedures. As a matter of fact, the competent authority concluded that it's own investigation procedures should improve, but we shall not discuss it in this paper. (author)

  3. Characterizing the proposed geologic repository for high-level radioactive waste at Yucca Mountain, Nevada: hydrology and geochemistry

    Science.gov (United States)

    Stuckless, John S.; Levich, Robert A.

    2012-01-01

    This hydrology and geochemistry volume is a companion volume to the 2007 Geological Society of America Memoir 199, The Geology and Climatology of Yucca Mountain and Vicinity, Southern Nevada and California, edited by Stuckless and Levich. The work in both volumes was originally reported in the U.S. Department of Energy regulatory document Yucca Mountain Site Description, for the site characterization study of Yucca Mountain, Nevada, as the proposed U.S. geologic repository for high-level radioactive waste. The selection of Yucca Mountain resulted from a nationwide search and numerous committee studies during a period of more than 40 yr. The waste, largely from commercial nuclear power reactors and the government's nuclear weapons programs, is characterized by intense penetrating radiation and high heat production, and, therefore, it must be isolated from the biosphere for tens of thousands of years. The extensive, unique, and often innovative geoscience investigations conducted at Yucca Mountain for more than 20 yr make it one of the most thoroughly studied geologic features on Earth. The results of these investigations contribute extensive knowledge to the hydrologic and geochemical aspects of radioactive waste disposal in the unsaturated zone. The science, analyses, and interpretations are important not only to Yucca Mountain, but also to the assessment of other sites or alternative processes that may be considered for waste disposal in the future. Groundwater conditions, processes, and geochemistry, especially in combination with the heat from radionuclide decay, are integral to the ability of a repository to isolate waste. Hydrology and geochemistry are discussed here in chapters on unsaturated zone hydrology, saturated zone hydrology, paleohydrology, hydrochemistry, radionuclide transport, and thermally driven coupled processes affecting long-term waste isolation. This introductory chapter reviews some of the reasons for choosing to study Yucca Mountain as a

  4. Characterizing the proposed geologic repository for high-level radioactive waste at Yucca Mountain, Nevada--hydrology and geochemistry

    Science.gov (United States)

    Stuckless, John S.; Levich, Robert A.

    2012-01-01

    This hydrology and geochemistry volume is a companion volume to the 2007 Geological Society of America Memoir 199, The Geology and Climatology of Yucca Mountain and Vicinity, Southern Nevada and California, edited by Stuckless and Levich. The work in both volumes was originally reported in the U.S. Department of Energy regulatory document Yucca Mountain Site Description, for the site characterization study of Yucca Mountain, Nevada, as the proposed U.S. geologic repository for high-level radioactive waste. The selection of Yucca Mountain resulted from a nationwide search and numerous committee studies during a period of more than 40 yr. The waste, largely from commercial nuclear power reactors and the government's nuclear weapons programs, is characterized by intense penetrating radiation and high heat production, and, therefore, it must be isolated from the biosphere for tens of thousands of years. The extensive, unique, and often innovative geoscience investigations conducted at Yucca Mountain for more than 20 yr make it one of the most thoroughly studied geologic features on Earth. The results of these investigations contribute extensive knowledge to the hydrologic and geochemical aspects of radioactive waste disposal in the unsaturated zone. The science, analyses, and interpretations are important not only to Yucca Mountain, but also to the assessment of other sites or alternative processes that may be considered for waste disposal in the future. Groundwater conditions, processes, and geochemistry, especially in combination with the heat from radionuclide decay, are integral to the ability of a repository to isolate waste. Hydrology and geochemistry are discussed here in chapters on unsaturated zone hydrology, saturated zone hydrology, paleohydrology, hydrochemistry, radionuclide transport, and thermally driven coupled processes affecting long-term waste isolation. This introductory chapter reviews some of the reasons for choosing to study Yucca Mountain as a

  5. Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 3

    International Nuclear Information System (INIS)

    2003-08-01

    The purpose of this report is to compile and disseminate information about the status of and trends in radioactive waste management in Agency Member States in a timely manner. The report is suitable for radioactive waste managers and regulators, decision making organizations in both governmental and private sectors, and for Agency Departments, in both the regular and Technical Co-operation programmes. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. The plan is to have the document evolve to serve a broader audience using easy-to-understand graphical and tabular data. For this, the third report in the series, contributions on a variety of topics in radioactive waste management were solicited from persons and organizations external to the Agency. Throughout the report, submissions received from external contributors are denoted. The preparation of this annual report involves (a) a meeting with a team of consultants from a variety of government and industrial organizations to compile a first draft, (b) the optional issuance of special service contracts to polish and supplement the first draft, (c) review by Agency staff and external contributors to the report and (d) final review and approval by the Director of the Nuclear Energy and Waste Technology Division, Nuclear Energy Department, in the Agency

  6. Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-01

    The purpose of this report is to compile and disseminate information about the status of and trends in radioactive waste management in Agency Member States in a timely manner. The report is suitable for radioactive waste managers and regulators, decision making organizations in both governmental and private sectors, and for Agency Departments, in both the regular and Technical Co-operation programmes. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. The plan is to have the document evolve to serve a broader audience using easy-to-understand graphical and tabular data. For this, the third report in the series, contributions on a variety of topics in radioactive waste management were solicited from persons and organizations external to the Agency. Throughout the report, submissions received from external contributors are denoted. The preparation of this annual report involves (a) a meeting with a team of consultants from a variety of government and industrial organizations to compile a first draft, (b) the optional issuance of special service contracts to polish and supplement the first draft, (c) review by Agency staff and external contributors to the report and (d) final review and approval by the Director of the Nuclear Energy and Waste Technology Division, Nuclear Energy Department, in the Agency.

  7. CERN: Producing radioactive beams

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Accelerating radioactive beams has long been of interest at CERN's ISOLDE on-line isotope separator - the possibility was discussed at a CERN Workshop on intermediate energy physics as early as 1977. Meanwhile, as was highlighted in the 1991 report of the Nuclear Physics European Collaboration Committee, widespread scientific interest in these beams has developed and a range of projects are proposed, under construction or operational throughout the world

  8. Safety and security of radioactive sources - international provisions

    International Nuclear Information System (INIS)

    Czarwinski, R.; Weiss, W.

    2005-01-01

    For more than 50 years radioactive sources are used beneficially world-wide in medicine, industry, research and teaching. In the early 50ies mainly Ra-226 sources were used especially for medical applications. In the mean time a great number of radionuclides with more or less risk to individuals, society and environment are used. The number of these sources is increasing. The available experience with the application of sealed sources in industry, medicine, research and teaching shows that despite the widespread use of such sources a high level of safety can be achieved. One precondition is that the regulatory control of a radioactive source has to be carried out consistently during the life cycle of the sources - 'from cradle to grave'. Particular attention has to be given to the so-called orphan sources which are not subject to regulatory control, either because they have never been under control, or because they have been lost, misplaced, abandoned, stolen or transferred without proper authorisation. The concern about orphan sources arising from poor safety and security standards of radioactive material around the world resulted in intensive global actions especially in the light of the security situation after the 11 th September 2001. The improvement of regulatory control is one of the key elements in preventing people, goods and environment from being exposed exceptionally by the misuse of radioactive sources. Important steps toward the improvement of the safety and security of high radioactive sources are the IAEA Code of Conduct on the Safety and Security of Radioactive Sources and the European Directive on the Control of High Activity Sealed Radioactive Sources and Orphan Sources. (orig.)

  9. Governing for the Common Good.

    Science.gov (United States)

    Ruger, Jennifer Prah

    2015-12-01

    The proper object of global health governance (GHG) should be the common good, ensuring that all people have the opportunity to flourish. A well-organized global society that promotes the common good is to everyone's advantage. Enabling people to flourish includes enabling their ability to be healthy. Thus, we must assess health governance by its effectiveness in enhancing health capabilities. Current GHG fails to support human flourishing, diminishes health capabilities and thus does not serve the common good. The provincial globalism theory of health governance proposes a Global Health Constitution and an accompanying Global Institute of Health and Medicine that together propose to transform health governance. Multiple lines of empirical research suggest that these institutions would be effective, offering the most promising path to a healthier, more just world.

  10. 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

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

    International Nuclear Information System (INIS)

    Endo, Mitsuru; Endo, Mai; Kakizaki, Takao

    2015-01-01

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

  12. Radioactive waste from non-licensed activities - identification of waste, compilation of principles and guidance, and proposed system for final management

    International Nuclear Information System (INIS)

    Jones, C.; Pers, K.

    2001-07-01

    Presently national guidelines for the handling of radioactive waste from non-licensed activities are lacking in Sweden. Results and information presented in this report are intended to form a part of the basis for decisions on further work within the Swedish Radiation Protection Institute on regulations or other guidelines on final management and final disposal of this type of waste. An inventory of radioactive waste from non-licensed activities is presented in the report. In addition, existing rules and principles used in Sweden - and internationally - on the handling of radioactive and toxic waste and non-radioactive material are summarized. Based on these rules and principles a system is suggested for the final management of radioactive material from non-licensed activities. A model is shown for the estimation of dose as a consequence of leaching of radio-nuclides from different deposits. The model is applied on different types of waste, e.g. peat ashes, light concrete and low-level waste from a nuclear installation

  13. The 2016-2018 National Plan of Management of Radioactive Materials and Wastes - Project

    International Nuclear Information System (INIS)

    Gazzo, Alexis; Robert, Jean-Gabriel; Abraham, Christophe; Benaze, Manon de

    2015-01-01

    A first document contains the project of the National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority, respectively on the plan preliminary focus, and on the plan itself. An answer to this last one is then proposed, followed by a synthesis of the plan project and the text of the corresponding decree

  14. Survey on non-nuclear radioactive waste; Kartlaeggning av radioaktivt avfall fraan icke kaernteknisk verksamhet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-11-01

    On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden.

  15. Proposed format and content of environmental reports for deep geologic terminal repositories for radioactive material

    International Nuclear Information System (INIS)

    Carrell, D.J.; Jones, G.L.

    1978-01-01

    As the Nuclear Regulatory Commission has not yet issued a format guide for the preparation of an environmental impact statement for radioactive waste repositories, Rockwell Hanford operations has developed an annotated outline which will serve as the basis for the environmental evaluation activities until replaced by an appropriate NRC regulatory guide. According to the outline, the applicant should summarize the major environmental effects that are expected to occur during the construction, operation, and terminal isolation phases of the radioactive material repository. Compare these environmental effects with the possible effect of continued use of interim storage facilities. Unless unforeseen environmental effects become apparent, the summary should be a positive statement indicating that the short-term environmental effects are outweighed by the long-term benefits of the repository

  16. ANSTO's radioactive waste management policy. Preliminary environmental review

    International Nuclear Information System (INIS)

    Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

    1996-05-01

    For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs

  17. The ''Ulisse'' project for the treatment of radioactive wastes of ENEA Department of Fuel

    International Nuclear Information System (INIS)

    Broglia, M.

    1988-01-01

    The high-level liquid wastes producedby the Nuclear Fuel Cycle Department of the Italian Committee for R and D of Nuclear and Alternative Energy since 1970 up today, are characterized by a very high aluminum content which would seriously limit the option of their vitrification. A simple chemical process for the separation of the radioactive fraction from the aluminum nitrate solution before vitrification has been proposed, reducing by a factor 10 the finally obtainable glass-waste volume (the ''ULISSE'' Project). This comparative study of the ''ULISSE'' high-level waste and detailed compositions of preferred products from various international Laboratories should supply a good initial condition in a glass matrix design for waste immobilization, and a feed-back control on the Project parameters

  18. Vitrification of high-level radioactive and hazardous wastes

    International Nuclear Information System (INIS)

    Lutze, W.

    1993-12-01

    The main objective is to summarize work conducted on glasses as waste forms for high-level radioactive fission product solutions up to the late 1980's (section I and II). Section III addresses the question, whether waste forms designed for the immobilization of radioactive residues can be used for the same purpose for hazardous wastes. Of particular interest are those types of hazardous wastes, e.g., fly ashes from municipal combustion plants, easy to convert into glasses or ceramic materials. A large number of base glass compositions has been studied to vitrify waste from reprocessing but only borosilicate glasses with melting temperatures between 1100 C and 1200 C and very good hydrolytic stability is used today. (orig./HP) [de

  19. Control of sealed radioactive sources in Peru

    International Nuclear Information System (INIS)

    Ramirez Quijada, R.

    2001-01-01

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

  20. Chemical treatment of liquid radioactive waste at the Boris Kidric Institute

    International Nuclear Information System (INIS)

    Lazic, S.; Vukovic, Z.; Voko, A.

    1989-01-01

    The results of lab-scale experiments on the chemical treatment of radioactive liquid waste collected at the Boris Kidric Institute are presented. The radioactive waste was treated by cobalt hexacyanoferrate precipitation followed by flocculation with polyelectrolyte flocculating agents. The main parameters investigated were standing time, pH and ratio of reagents. The flocculating agents were tested by filtration test and floccule stability test. Satisfactory decontamination factors by precipitation at pH 10 and good separation of solid and liquid phase by applying Praestol polyelectrolytes were obtained (author)

  1. Radiation doses arising from the air transport of radioactive materials

    International Nuclear Information System (INIS)

    Gelder, R.; Shaw, K.B.; Wilson, C.K.

    1989-01-01

    There is a compelling need for the transport of radioactive material by air because of the requirement by hospitals throughout the world for urgent delivery for medical purposes. Many countries have no radionuclide-producing capabilities and depend on imports: a range of such products is supplied from the United Kingdom. Many of these are short lived, which explains the need for urgent delivery. The only satisfactory method of delivery on a particular day to a particular destination is often by the use of scheduled passenger air service. The International Civil Aviation Organization's Technical Instructions for the Safe Transport of Dangerous Goods by Air (ICAO 1987-1988), prescribe the detailed requirements applicable to the international transport of dangerous goods by air. Radioactive materials are required to be separated from persons and from undeveloped photographic films or plates: minimum distances as a function of the total sum of transport indexes are given in the Instructions. A study, which included the measurement and assessment of the radiation doses resulting from the transport of radioactive materials by air from the UK, has been performed by the National Radiological Protection Board (NRPB) on behalf of the Civil Aviation Authority (CAA) and the Department of Transport (DTp)

  2. 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

  3. Sampling and characterization of radioactive liquid wastes

    International Nuclear Information System (INIS)

    Zepeda R, C.; Monroy G, F.; Reyes A, T.; Lizcano, D.; Cruz C, A. C.

    2017-09-01

    To define the management of radioactive liquid wastes stored in 200 L drums, its isotope and physicochemical characterization is essential. An adequate sampling, that is, representative and homogeneous, is fundamental to obtain reliable analytical results, therefore, in this work, the use of a sampling mechanism that allows collecting homogenous aliquots, in a safe way and minimizing the generation of secondary waste is proposed. With this mechanism, 56 drums of radioactive liquid wastes were sampled, which were characterized by gamma spectrometry, liquid scintillation, and determined the following physicochemical properties: ph, conductivity, viscosity, density and chemical composition by gas chromatography. 67.86% of the radioactive liquid wastes contains H-3 and of these, 47.36% can be released unconditionally, since it presents activities lower than 100 Bq/g. 94% of the wastes are acidic and 48% have viscosities <50 MPa s. (Author)

  4. Regulatory criteria for the disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Wagstaff, K.P.

    1986-09-01

    Radiological protection criteria have been proposed by the Atomic Energy Control Board for judging the potential long-term impacts of radioactive waste disposal options in which the wastes are contained and isolated from the human environment. This paper reviews the proposed criteria and the regulatory guidelines for their application in performance assessments, taking note of the public comments received to-date

  5. Technical report from Radioactive Waste Management Funding and Research Center

    International Nuclear Information System (INIS)

    2007-10-01

    As the only one Japanese organization specialized in radioactive waste, RWMC (Radioactive Waste Management Funding and Research Center) has been conducting the two major roles; R and D and the fund administration for radioactive waste management. The focus of its studies includes land disposal of LLW (Low-level radioactive wastes) and it has gradually extended to research on management and disposal techniques for high-level (HLW) and TRU wastes and studies on securing and managing the funds required for disposal of these wastes. The present document is the yearly progress report of 2006 and the main activities and research results are included on spent fuel disposal techniques including radon diffusion and emanation problem, performance studies on underground facilities for radioactive waste disposal and its management, technical assessment for geological environment, remote control techniques, artificial barrier systems proposed and its monitoring systems, and TRU disposals. (S. Ohno)

  6. The Constitution, waste facility performance standards, and radioactive waste classification: Is equal protection possible?

    Energy Technology Data Exchange (ETDEWEB)

    Eye, R.V. [Kansas Dept. of Health and Environment, Topeka, KS (United States)

    1993-03-01

    The process for disposal of so-called low-level radioactive waste is deadlocked at present. Supporters of the proposed near-surface facilities assert that their designs will meet minimum legal and regulatory standards currently in effect. Among opponents there is an overarching concern that the proposed waste management facilities will not isolate radiation from the biosphere for an adequate length of time. This clash between legal acceptability and a perceived need to protect the environment and public health by requiring more than the law demand sis one of the underlying reasons why the process is deadlocked. Perhaps the most exhaustive public hearing yet conducted on low-level radioactive waste management has recently concluded in Illinois. The Illinois Low-Level Radioactive Waste Disposal Facility Sitting Commission conducted 71 days of fact-finding hearings on the safety and suitability of a site near Martinsville, Illinois, to serve as a location for disposition of low-level radioactive waste. Ultimately, the siting commission rejected the proposed facility site for several reasons. However, almost all the reasons were related, to the prospect that, as currently conceived, the concrete barrier/shallow-land burial method will not isolate radioactive waste from the biosphere. This paper reviews the relevant legal framework of the radioactive waste classification system and will argue that it is inadequate for long-lived radionuclides. Next, the paper will present a case for altering the classification system based on high-level waste regulatory considerations.

  7. Data base for radioactive waste management: review of low-level radioactive waste disposal history

    International Nuclear Information System (INIS)

    Clancy, J.J.; Gray, D.F.; Oztunali, O.I.

    1981-11-01

    This document is prepared in three volumes and provides part of the technical support to the draft environmental impact statement (NUREG-0782) on a proposed regulation, 10CFR Part 61, setting forth licensing requirements for land disposal of low level radioactive waste. Volume 1 is a summary and analysis of the history of low level waste disposal at both commercial and government disposal facilities

  8. IAEA Mission Says France Committed to Safe, Responsible Management of Radioactive Waste

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said France demonstrated a comprehensive commitment to safety with a responsible approach to the management of radioactive waste and spent nuclear fuel. The team also made suggestions aimed at further enhancements and noted several good practices. The Integrated Review Service for Radioactive Waste and Spent Fuel Management, Decommissioning and Remediation (ARTEMIS) team concluded an 11-day mission to France on 24 January. The mission, requested by the Government of France, was hosted by the Directorate General of Energy and Climate (DGEC), with the participation of officials from several relevant organizations including the French National Radioactive Waste Agency (ANDRA) and the Nuclear Safety Authority (ASN), which is responsible for nuclear and radiation safety regulation in the country. ARTEMIS missions provide independent expert advice from an international team of specialists convened by the IAEA. Reviews are based on the IAEA safety standards as well as international good practices. The mission to France aimed to help the country meet European Union obligations that require an independent peer review of national programmes for the safe and responsible management of spent fuel and radioactive waste. Nuclear power currently generates more than 70 percent of France’s electricity. The country has 58 operating nuclear power reactors, which will require the continuing safe management of radioactive waste and spent fuel. France operates facilities for the disposal of very low-level and low-level wastes, and is developing a deep geological repository for the disposal of high-level waste.

  9. Preparation of water-equivalent radioactive solid sources

    International Nuclear Information System (INIS)

    Yamazaki, Ione M.; Koskinas, Marina F.; Dias, Mauro S.

    2011-01-01

    The development of water-equivalent solid sources in two geometries, cylindrical and flat without the need of irradiation in a strong gamma radiation source to obtain polymerization is described. These sources should have density similar to water and good uniformity. Therefore, the density and uniformity of the distribution of radioactive material in the resins were measured. The variation of these parameters in the cylindrical geometry was better than 2.0% for the density and 2.3% for the uniformity and for the flat geometry the values obtained were better than 2.0 % and better than 1.3%, respectively. These values are in good agreement with the literature. (author)

  10. The position of the Bureau of International Recycling on unwanted radioactivity and scrap

    International Nuclear Information System (INIS)

    Neenan, P.; Bartley, R.

    1999-01-01

    The Bureau of International Recycling (BIR) speaks as the unified voice of the international recycling industry on a world level, promoting free-trade in non-hazardous recyclables and the increased usage of recycled goods. In October 1998, BIR presented its 'Guide to Radioactivity' to its members in order to explain the basics of radioactivity, to help determine what actions material recyclers should take and to provide an initial contact guide for summoning expert help. The Guide was promulgated together with a survey questionnaire; initial results of this survey have been collated. BIR members do not trade in radioactive materials and do not wish to receive hazardous radioactive contaminated materials. Furthermore it is very uncommon to find this unwelcome and unwanted material. The burden of handling contaminated materials should not rest on the recycling industry alone, however, as the hazards associated with processing contaminated materials are potentially extreme, recyclers have a role to help safeguard both their workforce and subsequent customers. Some BIR members have invested in in-plant detection equipment of various types from a variety of suppliers to detect contamination from 'lost' sources or from naturally occurring radioactive materials (NORM). Strict State control on sources in use would be very welcome to limit these ' losses'. Not all BIR members are in a position to provide or operate detection equipment; therefore, BIR would welcome States providing detection and control at sea ports and at border checkpoints on railways and roads. Some states have proposed permitting requirements for the handling of radioactive contaminated materials and have tried, inappropriately, to impose on the mainstream recycling industry, permits designed for the specialist decontamination or decommissioning industry. Current discussions on applying the transport of dangerous goods regulations would lead to unnecessary and impracticable additional restraints to

  11. Determination of radioactivity in Cisadane River

    International Nuclear Information System (INIS)

    Tarigan, C.; Lubis, E.

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    Abdel-Halim, H.A.

    2005-01-01

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

  13. Thermodynamic stability of radioactivity standard solutions

    International Nuclear Information System (INIS)

    Iroulard, M.G.

    2007-04-01

    The basic requirement when preparing radioactivity standard solutions is to guarantee the concentration of a radionuclide or a radioelement, expressed in the form of activity concentration (Ac = A/m (Bq/g), with A: activity and m: mass of solution). Knowledge of the law of radioactive decay and the half-life of a radionuclide or radioelement makes it possible to determine the activity concentration at any time, and this must be confirmed subsequently by measurement. Furthermore, when radioactivity standard solutions are prepared, it is necessary to establish optimal conditions of thermodynamic stability of the standard solutions. Radioactivity standard solutions are prepared by metrology laboratories from original solutions obtained from a range of suppliers. These radioactivity standard solutions must enable preparation of liquid and/or solid radioactivity standard sources of which measurement by different methods can determine, at a given instant, the activity concentration of the radionuclide or radioelement present in the solution. There are a number of constraints associated with the preparation of such sources. Here only those that relate to the physical and chemical properties of the standard solution are considered, and therefore need to be taken into account when preparing a radioactivity standard solution. These issues are considered in this document in accordance with the following plan: - A first part devoted to the chemical properties of the solutions: - the solubilization media: ultra-pure water and acid media, - the carriers: concentration, oxidation state of the radioactive element and the carrier element. - A second part describing the methodology of the preparation, packaging and storage of standard solutions: - glass ampoules: the structure of glasses, the mechanisms of their dissolution, the sorption phenomenon at the solid-solution interface, - quartz ampoules, - cleaning and packaging: cleaning solutions, internal surface coatings and

  14. Thermodynamic stability of radioactivity standard solutions

    Energy Technology Data Exchange (ETDEWEB)

    Iroulard, M.G

    2007-04-15

    The basic requirement when preparing radioactivity standard solutions is to guarantee the concentration of a radionuclide or a radioelement, expressed in the form of activity concentration (Ac = A/m (Bq/g), with A: activity and m: mass of solution). Knowledge of the law of radioactive decay and the half-life of a radionuclide or radioelement makes it possible to determine the activity concentration at any time, and this must be confirmed subsequently by measurement. Furthermore, when radioactivity standard solutions are prepared, it is necessary to establish optimal conditions of thermodynamic stability of the standard solutions. Radioactivity standard solutions are prepared by metrology laboratories from original solutions obtained from a range of suppliers. These radioactivity standard solutions must enable preparation of liquid and/or solid radioactivity standard sources of which measurement by different methods can determine, at a given instant, the activity concentration of the radionuclide or radioelement present in the solution. There are a number of constraints associated with the preparation of such sources. Here only those that relate to the physical and chemical properties of the standard solution are considered, and therefore need to be taken into account when preparing a radioactivity standard solution. These issues are considered in this document in accordance with the following plan: - A first part devoted to the chemical properties of the solutions: - the solubilization media: ultra-pure water and acid media, - the carriers: concentration, oxidation state of the radioactive element and the carrier element. - A second part describing the methodology of the preparation, packaging and storage of standard solutions: - glass ampoules: the structure of glasses, the mechanisms of their dissolution, the sorption phenomenon at the solid-solution interface, - quartz ampoules, - cleaning and packaging: cleaning solutions, internal surface coatings and

  15. Developing a Pre-disposal radioactive waste management framework for malawi

    International Nuclear Information System (INIS)

    Guasi, Ephron

    2016-04-01

    In Malawi, uranium mining and other potential radioactive waste generating activities are on the increase. An elaborate national policy document and strategy on radioactive waste management is however not available. A national policy is important because it provides overall direction and the basis for decision making with respect to the management of radioactive waste in a country. Thus the absence of the national policy creates a gap in the country’s regulatory framework for ensuring safety and protection of people and the environment from sources of ionizing radiation. The present study was undertaken to minimize the impact of this regulatory framework gap by proposing a predisposal radioactive waste management framework for Malawi. This was achieved by analyzing the current and anticipated applications of radioactive materials and activities. The international and national regulatory requirements related to predisposal radioactive waste management were also reviewed and analyzed. The study found out that a predisposal radioactive waste management frame work comprised of onsite management of wastes from hospitals and uranium mining and export of high activity disused sources to supplier or management facilities in nearby countries would be the best for Malawi for now and the next ten years. (au)

  16. National Centre for Radioactive Ion Beams (NCRIB)

    International Nuclear Information System (INIS)

    Chintalapudi, S.N.

    1999-01-01

    Radioactive Ion (nuclear) Beams have become prolific recently. Nuclear physics and associated subjects have staged a comeback to almost the beginning with the advent of RIB. A dedicated National Centre for RIB (NCRIB) proposed, discussed at several forums and under serious consideration is described

  17. Spectrum correction algorithm for detectors in airborne radioactivity monitoring equipment NH-UAV based on a ratio processing method

    International Nuclear Information System (INIS)

    Cao, Ye; Tang, Xiao-Bin; Wang, Peng; Meng, Jia; Huang, Xi; Wen, Liang-Sheng; Chen, Da

    2015-01-01

    The unmanned aerial vehicle (UAV) radiation monitoring method plays an important role in nuclear accidents emergency. In this research, a spectrum correction algorithm about the UAV airborne radioactivity monitoring equipment NH-UAV was studied to measure the radioactive nuclides within a small area in real time and in a fixed place. The simulation spectra of the high-purity germanium (HPGe) detector and the lanthanum bromide (LaBr 3 ) detector in the equipment were obtained using the Monte Carlo technique. Spectrum correction coefficients were calculated after performing ratio processing techniques about the net peak areas between the double detectors on the detection spectrum of the LaBr 3 detector according to the accuracy of the detection spectrum of the HPGe detector. The relationship between the spectrum correction coefficient and the size of the source term was also investigated. A good linear relation exists between the spectrum correction coefficient and the corresponding energy (R 2 =0.9765). The maximum relative deviation from the real condition reduced from 1.65 to 0.035. The spectrum correction method was verified as feasible. - Highlights: • An airborne radioactivity monitoring equipment NH-UAV was developed to measure radionuclide after a nuclear accident. • A spectrum correction algorithm was proposed to obtain precise information on the detected radioactivity within a small area. • The spectrum correction method was verified as feasible. • The corresponding spectrum correction coefficients increase first and then stay constant

  18. Spectrum correction algorithm for detectors in airborne radioactivity monitoring equipment NH-UAV based on a ratio processing method

    Energy Technology Data Exchange (ETDEWEB)

    Cao, Ye [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Tang, Xiao-Bin, E-mail: tangxiaobin@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Wang, Peng; Meng, Jia; Huang, Xi; Wen, Liang-Sheng [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Chen, Da [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China)

    2015-10-11

    The unmanned aerial vehicle (UAV) radiation monitoring method plays an important role in nuclear accidents emergency. In this research, a spectrum correction algorithm about the UAV airborne radioactivity monitoring equipment NH-UAV was studied to measure the radioactive nuclides within a small area in real time and in a fixed place. The simulation spectra of the high-purity germanium (HPGe) detector and the lanthanum bromide (LaBr{sub 3}) detector in the equipment were obtained using the Monte Carlo technique. Spectrum correction coefficients were calculated after performing ratio processing techniques about the net peak areas between the double detectors on the detection spectrum of the LaBr{sub 3} detector according to the accuracy of the detection spectrum of the HPGe detector. The relationship between the spectrum correction coefficient and the size of the source term was also investigated. A good linear relation exists between the spectrum correction coefficient and the corresponding energy (R{sup 2}=0.9765). The maximum relative deviation from the real condition reduced from 1.65 to 0.035. The spectrum correction method was verified as feasible. - Highlights: • An airborne radioactivity monitoring equipment NH-UAV was developed to measure radionuclide after a nuclear accident. • A spectrum correction algorithm was proposed to obtain precise information on the detected radioactivity within a small area. • The spectrum correction method was verified as feasible. • The corresponding spectrum correction coefficients increase first and then stay constant.

  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. Current status of radioactive waste management (RWM) in Thailand

    International Nuclear Information System (INIS)

    Chantaraprachoom, N.

    2003-01-01

    Radioactive wastes in Thailand are mainly from the nuclear application in medicine, industry, agriculture, education and research reactor operation. The quantities of radioactive waste each year are relatively small. About 90 m 3 of processed waste and 7 m 3 unprocessed wastes are now stored at the waste storage facilities in the OAP. Recently the regulation on radioactive waste management was drafted and proposed to the cabinet for approval and to be promulgated as a ministerial regulation. A new nuclear research center, r which comprises 10 MW Research Reactor, Radioisotope Production and Centralized Waste Processing and Storage Facilities, is to be established at Ongkarak district in Nakornnayok province in the future. (author)

  1. Regulations related to the transport of radioactive material in Brazil

    International Nuclear Information System (INIS)

    Sahyun, Adelia; Sordi, Gian-Maria A.A.; Sanches, Matias P.

    2001-01-01

    The transport of radioactive material has raised great interest on the part of national regulatory authorities, thus resulting in a safety measures improvement for all kinds of transportation. The transport of radioactive material is regulated by safety criteria much more than those applied to conventional hazardous material. All radioactive material transportation run in Brazilian territory must be in accordance with what is established by the CNEN-NE 5.01 - Transport of Radioactive Material. There are other national and international regulations for radioactive material transportation, which have to be accomplished with and adopted during the operation of radioactive material transportation. The aim of this paper is to verify the criteria set up in the existing regulations and propose a consensus for all the intervening organizations in the regulation process for land, air or sea transportation. This kind of transportation can not depend on the efforts of only one person, a group of workers or even any governmental body, but must be instead a shared responsibility among workers, transport firms and all regulative transportation organizations. (author)

  2. Regulations related to the transport of radioactive material in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Sahyun, Adelia; Sordi, Gian-Maria A.A. [ATOMO Radioprotecao e Seguranca Nuclear, Sao Paulo, SP (Brazil)]. E-mail: atomo@atomo.com.br; Sanches, Matias P. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: msanches@net.ipen.br

    2001-07-01

    The transport of radioactive material has raised great interest on the part of national regulatory authorities, thus resulting in a safety measures improvement for all kinds of transportation. The transport of radioactive material is regulated by safety criteria much more than those applied to conventional hazardous material. All radioactive material transportation run in Brazilian territory must be in accordance with what is established by the CNEN-NE 5.01 - Transport of Radioactive Material. There are other national and international regulations for radioactive material transportation, which have to be accomplished with and adopted during the operation of radioactive material transportation. The aim of this paper is to verify the criteria set up in the existing regulations and propose a consensus for all the intervening organizations in the regulation process for land, air or sea transportation. This kind of transportation can not depend on the efforts of only one person, a group of workers or even any governmental body, but must be instead a shared responsibility among workers, transport firms and all regulative transportation organizations. (author)

  3. Disposal of Radioactive Waste. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2011-01-01

    This publication establishes requirements applicable to all types of radioactive waste disposal facility. It is linked to the fundamental safety principles for each disposal option and establishes a set of strategic requirements that must be in place before facilities are developed. Consideration is also given to the safety of existing facilities developed prior to the establishment of present day standards. The requirements will be complemented by Safety Guides that will provide guidance on good practice for meeting the requirements for different types of waste disposal facility. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Safety requirements for planning for the disposal of radioactive waste; 4. Requirements for the development, operation and closure of a disposal facility; 5. Assurance of safety; 6. Existing disposal facilities; Appendices.

  4. Dosimetry verification of radioactive seed implantation for malignant tumors assisted by 3D printing individual templates and CT guidance

    International Nuclear Information System (INIS)

    Ji, Zhe; Jiang, Yuliang; Guo, Fuxin; Sun, Haitao; Fan, Jinghong; Zhang, Lujing; Wang, Junjie

    2017-01-01

    Objective: We compared the dose distributions of postoperative plans with preoperative plans for 3D printing template-assisted radioactive seed implantations. Methods: A total of 14 patients with malignant tumors enrolled in the study. The dose parameters included D90, minimum peripheral dose, V100, V150, and V200. The statistical method was the paired t-test. Results: There was no significant difference in P values between the two groups for all parameters except for V100. Conclusions: The 3D printing guide template can provide good accuracy for radioactive seed implantation. - Highlights: • It is the first study we as for as we know to compare the preoperative and postoperative dosimetry results of 3D printing templates-assisted radioactive seeds implantation for malignant tumor. • 3D printing guide template can provide good accuracy for radioactive seeds implantation. • The actual dose distributions in postoperative validations were closed to the expectations of preoperative plans. • 3D printing template providing us an effective tool for the standardization and normalization of seed implantation, and having a good application prospect and worthy of further development and popularization.

  5. 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.)

  6. National Plan for the management of radioactive materials and wastes 2013-2015

    International Nuclear Information System (INIS)

    2013-02-01

    This new release of the National Plan for the management of radioactive materials and wastes (PNGMDR) first addresses the principles and objectives of this management: presentation of radioactive materials and wastes, principles to be taken into account to define the different management ways, legal and institutional framework for waste management, societal dimension and memory safeguarding, waste management cost and financing. It proposes an assessment and draws perspectives for the existing management practices: management of historical situations, management of residues of mine processing and mine tailings, management of radioactive wastes, waste management with respect to radioactive decay, valorization of radioactive wastes, incineration of radioactive wastes, storage of very-low-activity wastes, of storage of low- and medium-activity and short-life wastes, management of reinforced natural radioactivity wastes. The third part gives an overview of needs and perspectives for management methods: wastes requiring a specific processing, low-activity long-life wastes, and high-activity and medium-activity long-life wastes

  7. Procedures for accurately diluting and dispensing radioactive solutions

    International Nuclear Information System (INIS)

    1975-01-01

    The technique currently used by various laboratories participating in international comparisons of radioactivity measurements are surveyed and recommendations for good laboratory practice established. Thus one describes, for instance, the preparation of solutions, dilution techniques, the use of 'pycnometers', weighing procedures (including buyoancy correction), etc. It should be possible to keep random and systematic uncertainties below 0.1% of the final result

  8. Commercial radioactive waste disposal: marriage or divorce

    International Nuclear Information System (INIS)

    Corbett, J.S.

    1977-01-01

    It is shown that the state (South Carolina) is doing a good job in regulating the South Carolina disposal facility of Chemo-Nuclear Inc., and that there is no need for the NRC to reassert Federal control. The efforts in developing a low-level site in New Mexico are described. The NRC Task Force report on Federal/state regulation of commercial low-level radioactive waste burial grounds is discussed

  9. A proposed alternative approach for protection of inadvertent human intruders from buried Department of Energy low level radioactive wastes

    International Nuclear Information System (INIS)

    Cochran, J.R.

    1995-01-01

    The burial of radioactive wastes creates a legacy. To limit the impact of this legacy on future generations, we establish and comply with performance objectives. This paper reviews performance objectives for the long-term isolation of buried radioactive wastes; identifies regulatorly-defined performance objectives for protecting the inadvertent human intruder (IHI) from buried low-level radioactive waste (LLW); (3) discusses a shortcoming of the current approach; and (4) offers an alternative approach for protecting the IHI. This alternative approach is written specifically for the burial of US Department of Energy (DOE) wastes at the Nevada Test Site (NTS), although the approach might be applied at other DOE burial sites

  10. Management of radioactive fuel wastes: the Canadian disposal program

    International Nuclear Information System (INIS)

    Boulton, J.

    1978-10-01

    This report describes the research and development program to verify and demonstrate the concepts for the safe, permanent disposal of radioactive fuel wastes from Canadian nuclear reactors. The program is concentrating on deep underground disposal in hard-rock formations. The nature of the radioactive wastes is described, and the options for storing, processing, packaging and disposing of them are outlined. The program to verify the proposed concept, select a suitable site and to build and operate a demonstration facility is described. (author)

  11. An overview of application of bayesian classifier approach in radioactive tracer technology.case study

    International Nuclear Information System (INIS)

    El-Aseer, A.; Dawood, E.; Ben Ayad, S.; Alwerfalli, M.

    2015-01-01

    The usefulness of implementing a radioactive tracer techniques subjected to varied risk factors. Thus, the setup procedure for the application experimental techniques of radioactive tracer must be evaluated prior the decision action steps. One way of doing this, is to use Bay's theorem techniques. As there is a possibility of classifying the implemented parameters into certain catogries depending on their certainty to effect radioactive tracer technology. In this paper, the radioactive tracer experimental parameters classified accoring to Bayesian theory. Using this theory, one can study the proposed technical systems to determine the probabilities of the effectiveness of any selected parameter among the others. The classification of the applied experimental parameters into suitable or unsuitable in proposed theoretically. Ten parameters used in this experimental data were classified accordingly. The posterior is calculate from the prior and the likelihood previously determined by bayes rule.(author)

  12. Good practices in radiological protection at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Singh, V.P.; Kumar, Sanjeev; Agrawal, Mitesh; Tiwari, S.K.; Kulhari, Praveen; Gupta, Ashok

    2016-01-01

    Radiological protection performance of nuclear power plant is assessed by collective exposure, individual average exposure, external/external exposure, personnel/surface contamination and reduction of radioactive wastes. Collective exposure is reduced by integrated comprehensive ALARA program in all aspects of nuclear plant operation and maintenance has reduced collective dose many folds. In the present paper, implementation of new good practices in Radiological Protection is presented

  13. Design and performance assessment of radioactive waste forms: what can we learn from natural analogues

    International Nuclear Information System (INIS)

    Petit, J.C.

    1991-01-01

    In this review, we specify the role of natural analogues for the development of solid radioactive waste-forms. Numerous works have been carried out on the major matrices proposed or actually in use for both high-level (glasses, spent fuel, ceramics) and low- or intermediate-level wastes (cement-based materials, bitumens, resins) as well as for metallic containers. We show that some natural, historical or archaeological materials can be considered as good analogues. We suggest that their use has been quite limited in the past for the design of matrices but that both qualitative and quantitative information of great interest (and in some cases unique) have been already inferred for assessing their long-term performance. 14 figs., 1 tab., 72 refs

  14. Transport of radioactive material in Sudan practice and regulations

    International Nuclear Information System (INIS)

    Abdalla, M. K. E.

    2010-12-01

    In the last couple of decades there has been an impressive increase in applications of radioactive material. Such an extensive and widely spread usage of radioactive materials demands safe transportation of radioactive material from the production site to the application location, as well as quick and effective response in a case of an unexpected transportation event according to Sudan Atomic Energy Commission (SAEC) regulation. The thesis described the local practice for transport of radioactive material as compared to the international standards for radiation protection, and also discussed the emergency procedures that must be follow in case of accident during transport of radioactive material. Furthermore, the objective of this study was also to set proposals for how to cope in the event of a radiological accident. The study methods included survey of current literature on safe transport of radioactive material, survey of national regulations on the subjects in additional to case studies aimed at investigating the practical issues pertinent to transport of radioactive materials in Sudan. A comprehensive review was presented on how to classification of radioactive packages and general requirement for all packaging and packages according to international standard. transport of number of radioactive sources from Khartoum airport to the field was evaluated with regard transport index, category of source, type of package, dose rate around the source, time to destination and means of transport of doses to public, worker are be made. All results were within the limit specified in the national as well as international regulation. The study has addressed for the first time the practice of transport of radioactive material in Sudan. It is anticipated that the results will encourage national organizational and professional bodies to enhance radiation protection and safety of radioactive sources. (Author)

  15. Radioactivity. To better manage polluted soils and sites. Pargny-sur-Saulx, more than 15 years of interventions. Chef de Baie, radioactivity mapping

    International Nuclear Information System (INIS)

    Caplin, Helene; Baumont, Genevieve; Tardieu, Laure; Brisson, Nicolas; Guillevic, Jerome; Serres, Christophe; Barrieu, Olivier

    2016-01-01

    A set of articles proposes an overview of the various actions performed by the IRSN for the management of sites and soils polluted by radioactive substances. A first article outlines the need for a national strategy to manage about forty polluted sites, the lack of a waste elimination sector (the storage is organised, but not the elimination), the action of the IRSN in mapping the radioactivity, in assessing the associated exposure, and in supporting decontamination actions. Costs, benefits, risks and actors are also evoked. A second article describes the various interventions organised over 15 years to manage a site which had been contaminated by the thorium from an ancient plant: site safety, interviews of personnel, elimination of all significant radioactivity. The last article addresses the case of another site, Chef de Baie in La Rochelle, which had been used as a deposit for contaminated materials produced by a neighbouring plant, and where the IRSN intervened to map the radioactivity

  16. Application of the permeation to the production of low radioactive calibrated gas flows. Low radioactive tritium measurement

    International Nuclear Information System (INIS)

    Pilot, Guy.

    1979-12-01

    The permeation of compounds (HT, HTO, 131 ICH 3 , and 129 ICH 3 ) through organic membranes in view of producing low radioactive calibrated gas flows has been studied. This process of which the diffusion is the main stage enables respecting certain conditions (choice of the membrane, temperature, partial pressure differential) our aims to be reached with a good accuracy. In order to measure radioactivity of tritiated standard gases, a detector was built. This detector is an Oeschger type proportional counter with a total volume of 17.4 dm 3 and an useful volume of 3.9 dm 3 . In the conditions of operation, the background is of 1.7.10 -6 I s -1 cm -3 . The counter coupled with a feed-rack enables various samples to be measured and it is possible in the best conditions to detect some 10 -11 μCi cm -3 NTP [fr

  17. 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.

  18. Radioactive waste management

    International Nuclear Information System (INIS)

    Kawakami, Yutaka

    2008-01-01

    Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

  19. 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

  20. 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

  1. Assessing the management system to demonstrate the safe of transport of radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Bruno, Natanael C.; Mattar, Patricia M.; Pontes, Andre T., E-mail: nbruno@cnen.gov.br, E-mail: pmattar@cnen.gov.br, E-mail: atpontes@id.uff.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

    2017-11-01

    Radioactive materials are used for medical purposes, to avoid greenhouse gas effect in energy production plants, food and other products sterilization, research and sophisticated measurement technologies. Transport of radioactive material involves a range of actors each one having specific responsibilities for safety. Through Management System, consignors and carriers fulfil objective evidences that safety requirements are met in practice, while compliance assurance programs allow regulatory bodies and/or competent authorities to demonstrate to society that public, workers and environment are protected. According to the International Atomic Energy Agency (IAEA), safety has to be achieved and maintained through an effective management system. This system should integrate all elements of management so that requirements for safety are established and applied consistently with other requirements, including those related to human performance, quality and security, and that safety is not compromised by other requirements or demands. Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body for the safe transport of radioactive materials, adopt international standards to establish safety requirements deemed relevant for protection of health and minimization of danger to life and property, and to provide for the application of these standards. Seeking for continuous improvement, the adherence of the practices adopted by CNEN's Transport Safety Unit (TSU) against the recommendations from the IAEA was assessed. This assessment led to the elaboration of proposals for improvement as well as the identification of good practices. The methodology used to perform this assessment was the SARIS methodology, developed by the IAEA. This paper will describe the most relevant findings of this study. (author)

  2. Assessing the management system to demonstrate the safe of transport of radioactive material

    International Nuclear Information System (INIS)

    Bruno, Natanael C.; Mattar, Patricia M.; Pontes, Andre T.

    2017-01-01

    Radioactive materials are used for medical purposes, to avoid greenhouse gas effect in energy production plants, food and other products sterilization, research and sophisticated measurement technologies. Transport of radioactive material involves a range of actors each one having specific responsibilities for safety. Through Management System, consignors and carriers fulfil objective evidences that safety requirements are met in practice, while compliance assurance programs allow regulatory bodies and/or competent authorities to demonstrate to society that public, workers and environment are protected. According to the International Atomic Energy Agency (IAEA), safety has to be achieved and maintained through an effective management system. This system should integrate all elements of management so that requirements for safety are established and applied consistently with other requirements, including those related to human performance, quality and security, and that safety is not compromised by other requirements or demands. Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body for the safe transport of radioactive materials, adopt international standards to establish safety requirements deemed relevant for protection of health and minimization of danger to life and property, and to provide for the application of these standards. Seeking for continuous improvement, the adherence of the practices adopted by CNEN's Transport Safety Unit (TSU) against the recommendations from the IAEA was assessed. This assessment led to the elaboration of proposals for improvement as well as the identification of good practices. The methodology used to perform this assessment was the SARIS methodology, developed by the IAEA. This paper will describe the most relevant findings of this study. (author)

  3. Environmental radioactive monitoring, evaluation and protection in luminous workshops of a factory

    International Nuclear Information System (INIS)

    Dai Hanbin; Xiang Ming; Tan Jianzu

    2009-01-01

    Fluorescent technique is often used to display instrumental indicator in the dark environment. Luminous workshops of a factory smear and depict the glassware by means of fluorescent power with adulterated radioactive matter. Because of adulterated radioactive matters such as 226 Ra, 40 K emit alpha-ray,beta-ray and gamma-ray, while they decay spontaneously, and high dose or cumulative radiation can damage human body in different degrees. Therefore, any radioactive damage to human body caused by over-safety dose should be prevented strictly during the working. To ensure health and safety of working staff in luminous workshop and the public, it is necessary to regularly have radioactive monitoring and evaluation to luminous workshop and its surrounding environment. Through the environment radioactive monitoring, the authors analyze its environmental radioactive level,and try to find out the possible problems so as to propose some protective measures for personal health. (authors)

  4. Radioactivity in drinking water: regulations, monitoring results and radiation protection issues

    Directory of Open Access Journals (Sweden)

    Cristina Nuccetelli

    2012-12-01

    Full Text Available INTRODUCTION: Drinking waters usually contain several natural radionuclides: tritium, radon, radium, uranium isotopes, etc. Their concentrations vary widely since they depend on the nature of the aquifer, namely, the prevailing lithology and whether there is air in it or not. AIMS: In this work a broad overview of the radioactivity in drinking water is presented: national and international regulations, for limiting the presence of radioactivity in waters intended for human consumption; results of extensive campaigns for monitoring radioactivity in drinking waters, including mineral bottled waters, carried out throughout the world in recent years; a draft of guidelines for the planning of campaigns to measure radioactivity in drinking water proposed by the Environmental Protection Agency (ARPA of Lombardia.

  5. 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.)

  6. Uncertainty and sensitivity analysis in the 2008 performance assessment for the proposed repository for high-level radioactive waste at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Helton, Jon Craig; Sallaberry, Cedric M.; Hansen, Clifford W.

    2010-01-01

    Extensive work has been carried out by the U.S. Department of Energy (DOE) in the development of a proposed geologic repository at Yucca Mountain (YM), Nevada, for the disposal of high-level radioactive waste. As part of this development, an extensive performance assessment (PA) for the YM repository was completed in 2008 (1) and supported a license application by the DOE to the U.S. Nuclear Regulatory Commission (NRC) for the construction of the YM repository (2). This presentation provides an overview of the conceptual and computational structure of the indicated PA (hereafter referred to as the 2008 YM PA) and the roles that uncertainty analysis and sensitivity analysis play in this structure.

  7. Conditions of sedimentation of deposits of the lower section of the productive strata and their natural radioactivity

    International Nuclear Information System (INIS)

    Alieva, E.G.; Aliev, Ch.S.; Huseynov, D.A.

    2008-01-01

    In this article for the time for sedimentary deposits of the southern Caspian basin is an attempt use of the data of natural radioactivity of sediments in order to reconstruct their conditions sedimentation. The results obtained show a good comparability of the nature of the distribution of radioactive elements with the conditions of sedimentation. Clear contents of dependency is detected radioactive elements from the source of sedimentary material that can be successfully used in conducting the paleo facial and paleogeographic building.

  8. Visiatome: The French Discovery and Information Center on Radioactive Waste Management

    International Nuclear Information System (INIS)

    Brunel, G.; Rabbe, C.; Moncouyoux, J.P.

    2006-01-01

    The French radioactive waste management act of December 30, 1991, included two key provisions. It initiated a major research program with three areas of investigation concerning high-level long-lived radioactive waste management routes, and called for the Government to submit a legislative proposal to Parliament within 15 years (by 2006) specifying the policy guidelines adopted. Considering the sensitive nature of the subject, the questions surrounding the issue of radioactive waste, and the social, economic and environmental concerns for present and future generations, the Government has inaugurated, in 2005, a nationwide public debate on these issues between the submittal of the research reports and the parliamentary discussion of the proposed law. In this context, the CEA has decided to concentrate at Marcoule the expertise and experience acquired in the area of radioactive waste management and to make it available to stakeholders and to the public. A scientific cultural center, Visiatome, has been built to inform the public and facilitate the acceptance of nuclear energy and radioactive waste management by presenting the subject in a manner adapted to the level of knowledge of the visitors. A modern, fun and interactive exhibition of 600 m 2 allows visitors to find out more about energy, waste products, sources of radioactive waste, their treatment and where they are stored, natural and artificial radioactivity, effects of radiation on mankind. It also offers a media library, an auditorium for group discussions and teaching rooms for school groups with the aim of encouraging students to discover science through enjoyment. Visiatome has received several thousand visitors since it was opened to the public on April 10, 2005, and the initial results of this experience can now be reviewed: the design principles of the center and its permanent exhibits, the characteristics of the visitors and their perception of the subjects presented. (authors)

  9. ANSTO`s radioactive waste management policy. Preliminary environmental review

    Energy Technology Data Exchange (ETDEWEB)

    Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

    1996-05-01

    For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs.

  10. Calculations on safe storage and transportation of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Hathout, A M; El-Messiry, A M; Amin, E [National Center for Nuclear Safety and Radiation Control and AEA, Cairo (Egypt)

    1997-12-31

    In this work the safe storage and transportation of fresh fuel as a radioactive material studied. Egypt planned ET RR 2 reactor which is of relatively high power and would require adequate handling and transportation. Therefore, the present work is initiated to develop a procedure for safe handling and transportation of radioactive materials. The possibility of reducing the magnitude of radiation transmitted on the exterior of the packages is investigated. Neutron absorbers are used to decrease the neutron flux. Criticality calculations are carried out to ensure the achievement of subcriticality so that the inherent safety can be verified. The discrete ordinate transport code ANISN was used. The results show good agreement with other techniques. 2 figs., 2 tabs.

  11. Radioactive waste disposal programme and siting regions for geological deep repositories. Executive summary. November 2008

    International Nuclear Information System (INIS)

    2008-11-01

    There are radioactive wastes in Switzerland. Since many decades they are produced by the operation of the five nuclear power plants, by medicine, industry and research. Important steps towards the disposal of these wastes are already realized; the corresponding activities are practised. This particularly concerns handling and packaging of the radioactive wastes, their characterization and inventory, as well as the interim storage and the inferred transportations. Preparatory works in the field of scientific research on deep geological repositories have allowed to acquire high level of technical and scientific expertise in that domain. The feasibility of building long-term safe geological repositories in Switzerland was demonstrated for all types of radioactive wastes; the demonstration was accepted by the Federal Council. There is enough knowledge to propose geological siting regions for further works. The financial funds already accumulated guaranty the financing of the dismantling of the power plants as well as building deep geological repositories for the radioactive wastes. The regulations already exist and the organisational arrangements necessary for the fruitful continuation of the works already done have been taken. The programme of the disposal of radioactive wastes also describes the next stages towards the timely realization of the deep repositories as well as the level of the financial needs. The programme is updated every five years, checked by the regulatory bodies and accepted by the Federal Council who reports to the parliament. The process of choosing a site, which will be completed in the next years, is detailed in the conceptual part of the programme for deep geological repositories. The NAGRA proposals are based exclusively on technical and scientific considerations; the global evaluation taking into account also political considerations has to be performed by the authorities and the Federal Council. The programme states that at the beginning of

  12. Radioactive materials system of the ININ (SMATRAD)

    International Nuclear Information System (INIS)

    Rivero G, E.; Ledezma F, L.E.; Valdivia R, D.

    2007-01-01

    The radioactive iodine (I-131) it is an isotope created starting from the iodine with the purpose of emitting radiation for medicinal use. When a small dose of I-131 is ingested, this is absorbed in the sanguine torrent in the gastrointestinal tract (Gl) and it is concentrated by the blood on the thyroid gland, where it begins to destroy the cells. This treatment makes that the activity of the thyroid decreases in great measure and in some cases it can transform an hyperactive thyroid in a hypoactive thyroid which requires additional treatments. The sodium iodide I-131 is one of the products elaborated and marketed by the ININ in the Radiopharmaceuticals and Radioisotopes production plant, dependent of the Radioactive Material Department of the Nuclear Applications in the Health Management. The Plant is the only one in its type that exists in the country, it has Sanitary License and Good Practice of Production Certificate, emitted by the Secretary of Health, and licenses for the handling and the transportation of radioactive material, sent by the National Commission of Nuclear Safety and Safeguards. Also, the quality system of the plant is certified under the ISO 9001:2000 standard. (Author)

  13. Radioactivity in Chemical Fertilizers

    International Nuclear Information System (INIS)

    Jankovic, M.; Nikolic, J.; Pantelic, G.; Rajacic, M.; Sarap, N.; Todorovic, D.

    2013-01-01

    The fertilizers are essential in agriculture as they supply nutrients to the farming fields. One of the sources of radioactivity other than those of natural origin is mainly due to extensive use of fertilizers. The concentrations of natural radionuclides, 40K, 226Ra, 238U and 235U in different chemical fertilizers, which are part of the regular control of imported goods from the border crossing were analyzed using gamma spectrometry with a high purity germanium (HPGe) detector, relative efficiency 20 %, in order to assess the implications of the extended use of chemical fertilizers. Measurements were performed at Vinca Institute, Radiation and Environmental Protection Department. The obtained results show remarkable wide variations in the radioactivity contents of different samples. The mean (ranges) of specific activities for gamma activity of those fertilizer samples for 40K, 226Ra, 238U and 235U are 4857 (23 - 12 324) Bq/kg, 87 (4-393) Bq/kg, 220 (26-1145) Bq/kg and 15 (1.6-53) Bq/kg, respectively. The radium equivalent activity (Ra eq ) as well as the external absorbed gamma dose rate (D) for all samples was also calculated.(author)

  14. Regulatory issues related to long-term storage and disposal of radioactive wastes in Kazakhstan

    International Nuclear Information System (INIS)

    Kim, A.; Romanenko, O.; Tazhibayeva, I.; Zhunussova, T.

    2012-01-01

    Full text: Reported material is a result of activity accomplished in the framework of cooperation program between Kazakhstan and Norway within 2009-2012. This work was divided into three distinctive parts, as follows: 1. Analysis of existing threats associated with radioactive wastes in the Republic of Kazakhstan. The objective of this part of the work was to reveal the most important threats in the sphere of radioactive waste management in the Republic of Kazakhstan, which require an increased regulatory attention. Threat assessment needed to identify: main radiological threats both for people who work with radioactive wastes and for population living near the radioactive waste storage places now and in the long term which require an increased regulatory attention; problems that need urgent and detailed analysis; and main problems in the realization of regulatory process in Kazakhstan including weakness in the regulatory and legal framework. Threat assessment analysis showed that in order to reduce the level of threats it was necessary to begin developing a national policy and strategy for radioactive waste management which need to be approved by the Government, to develop proposals for Radioactive Wastes new classification, including identification of relevant categories of Radioactive Wastes, as well as criteria for their disposal in accordance with IAEA recommendations and experience from other countries. 2. Development of new classification system for radioactive wastes in Kazakhstan. Following the results of threat assessment performed within the first stage, the objective of the second part of work was to develop a proposal to adopt a new Radioactive Wastes classification in Kazakhstan in accordance with the IAEA recommendations, including implementation of new categories, taking into account international experience and current situation in Kazakhstan. The result of this stage of work was a proposal for a new Radioactive Wastes classification and

  15. Future radioactive liquid waste streams study

    Energy Technology Data Exchange (ETDEWEB)

    Rey, A.S.

    1993-11-01

    This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

  16. Future radioactive liquid waste streams study

    International Nuclear Information System (INIS)

    Rey, A.S.

    1993-11-01

    This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL

  17. Planning and consultation procedures for low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    Kemp, R.

    1989-03-01

    This Report is the result of a year-long study funded by UK Nirex Ltd. between 1986 and 1987. The central purpose was to learn from overseas experience of planning and public consultation procedures associated with the establishment of low-level radioactive waste (LLW) disposal sites. The most recent information on LLW developments in the United States, Canada, France, Holland, Switzerland, Sweden, and West Germany was sought, particularly in regard to: (1) the efficacy of public consultation and negotiation procedures, focusing in particular on the perceived problems, successes and areas for improvement; (2) the key aspects bearing on the public acceptability of LLW proposals; and (3) the form and effect of any compensation mechanisms in operation. The greatest success overseas appears to be linked to some combination of the following elements: authority and clarity in the exposition of the direction of radioactive waste management policy, backed up by authoritative and independent analysis; the early involvement of local authority (county council/regional authority) organisations in the site selection process; careful attention to the potential contribution of authoritative independent advisory groups on both technical and procedural/site selection matters; the development and nurturing of local liaison committees to establish good communications at the local level; careful consideration of means of devolving some power to local authority level for safety reassurance, for example, in relation to site inspections and safety monitoring; the development of an incremental, openly negotiated approach to compensation. (author)

  18. Fifteen years of radioactive waste management at Ontario Hydro

    International Nuclear Information System (INIS)

    Carter, T.J.; Rao, P.K.M.

    1985-01-01

    Ontario Hydro is a large Canadian utility producing 84% (7394 MWe) of the Nuclear Electricity generated in Canada. The low- and intermediate-level radioactive wastes generated by the Ontario Hydro program are currently being managed at the Bruce Nuclear Power Development with various volume reduction, packaging and interim storage systems. Ontario Hydro also owns and operates a radioactive waste transportation system. Studies are in progress for final disposal of these wastes in a suitable geology in Ontario. Since its inception in 1971, Ontario Hydro's radioactive waste management program has evolved into providing a full fledged radioactive waste management capability to the utility's two nuclear generation centres at Pickering and Bruce, and later in the decade, to Darlington. This paper summarizes the various developments in this program; highlights the major facilities both in-service and planned to be built; reviews the experiences gained over fifteen years of in-house waste management; and discusses the proposed reorientation towards ultimate disposal of these wastes. 2 refs., 8 figs., 1 tab

  19. The law of radioactive decay

    International Nuclear Information System (INIS)

    Bouyrie, G

    2004-01-01

    This article deals with the law of radioactive decay (Rutherford-Sody's law) and the way to explain it to high-school or grammar-school students. The mathematical content of the law is recalled and its experimental validation is proposed through the study of the decay of a population of radon-220 atoms. The analysis of the experimental data is made easier by using software such as Generis, Regressi or even Excel

  20. Process of liquid radioactive waste treatment in nuclear power plant and development trend

    International Nuclear Information System (INIS)

    Liu Jiean; Wang Xin; Liu Dan; Zhu Laiye; Chen Bin

    2014-01-01

    The popular liquid radioactive waste treatment methods in nuclear power plants (NPP) are Chemical precipitation, evaporation, ion exchange, membrane treatment, chemical coagulation and activated carbon absorption and so on. 'Filter + activated carbon absorption (Chemical coagulation) + ion exchange' has a good prospect for development, as its simple process, high decontamination factor, low energy consumption and smaller secondary wastes. Also the process is used in Sanmen and Haiyang Projects. The severe incident in NPP set an even higher demand on liquid radioactive waste treatment. The new type treatment materials, optimization of the existed treatment, combination of treatment and the mobile treatment facility is the development trend in liquid radioactive waste treatment in NPP. (authors)

  1. Disposal of radioactive and other hazardous wastes

    International Nuclear Information System (INIS)

    Boge, R.; Bergman, C.; Bergvall, S.; Gyllander, C.

    1989-01-01

    The purpose of the workshop was discuss legal, scientific and practical aspects of disposal of low- and intermediate-level radioactive waste and other types of hazardous waste. During the workshop the non-radioactive wastes discussed were mainly wastes from energy production, but also industrial, chemical and household wastes. The workshop gave the participants the opportunity to exchange information on policies, national strategies and other important matters. A number of invited papers were presented and the participants brought background papers, describing the national situation, that were used in the working groups. One of the main aims of the workshop was to discuss if the same basic philosophy as that used in radiation protection could be used in the assessment of disposal of non-radioactive waste, as well as to come up with identifications of areas for future work and to propose fields for research and international cooperation. The main text of the report consists of a summary of the discussions and the conclusions reached by the workshop

  2. Gallium-67 activated charcoal: a new method for preparation of radioactive capsules for colonic transit study

    International Nuclear Information System (INIS)

    Cheng, Kai-Yuan; Tsai, Shih-Chuan; Lin, Wan-Yu.

    2003-01-01

    Indium-111 is currently the radionuclide of choice for colonic transit study. However, it is expensive and not available in many hospitals. Technetium-99m has been proposed for colonic transit study but the short half-life has limited its use. Gallium-67 citrate is inexpensive and available in most countries. Most importantly, it has a suitable half-life for colonic transit study. Attempts have been made in some studies to use 67 Ga citrate to label activated charcoal, but the results have not been good because of poor stability. In this study, we successfully labelled activated charcoal with 67 Ga citrate by adding alcohol and 5% glucose solution. To evaluate the in vitro stability, the 67 Ga-activated charcoal was incubated in a milieu mimicking the intestinal content, containing lipase, trypsin and glycochenodeoxycholate at different pH values (6.0, 7.0, 7.4 and 8.0) and for different durations (0 h, 24 h, 48 h, 72 h and 96 h). For the in vivo study, the 67 Ga-activated charcoal was loaded into a commercial empty enteric capsule. Colonic transit scintigraphy was performed in five volunteers, including three healthy people and two constipated patients, after intake of the radioactive capsule. Images were obtained at 2 h, 4 h, 6 h, 8 h, 24h, 48 h, 72 h etc. until no radioactivity was detected in the bowel. Our data show that the in vitro stability of 67 Ga-activated charcoal was good. The labelling efficiency still exceeded 91% at 96 h at pH values of 6.0, 7.0 and 7.4. In the group with a pH value of 8.0, the labelling efficiency gradually fell during the 4-day incubation but was still higher than 88% at the end of the fourth day. In the in vivo study, most capsules disintegrated in the caecum/colon region, and the 67 Ga-activated charcoal mixed very well with bowel content. In addition, the radioactive charcoal could be detected clearly on the 72-h image, which is very important for the evaluation of colonic transit time in patients with constipation. In

  3. The disposal of solid radioactive wastes to land sites in the UK

    International Nuclear Information System (INIS)

    Ginniff, M.E.; Phillipson, D.L.

    1984-01-01

    Solid radioactive waste management by land disposal, using a strategy laid down by the government, is discussed. Waste disposal at Drigg, and the proposals for the two preferred sites at Elstow (shallow burial) and Billingham (deep burial) are outlined. Nuclear Industry Radioactive Waste Executive (NIREX); safety; public acceptance; and the role of the private sector; are also described. (U.K.)

  4. A decade of successful domestic sea transports of radioactive waste in Sweden 1982-1992

    International Nuclear Information System (INIS)

    Dybeck, P.; Gustafsson, B.

    1993-01-01

    Today the transports of radioactive waste in Sweden are done on routine basis without any negative publicity. An important contribution to this fact is probably the very good performance of the transport system and the receiving facilities. Since the start of operation of the transport system no accidents have occurred. Almost 1600 tonnes of spent fuel and 10,000 m 3 of radioactive waste have been transported. The capacity and availability of the ship and of the transport system as a whole is large enough to cover all needs for transports of radioactive material in Sweden, at least up to the turn of this century. (J.P.N.)

  5. Analysis of the awareness of medical radioactive waste management plans (with focus on Busan and Gyeongsangnam-do)

    International Nuclear Information System (INIS)

    Kang, Se Sik; Choi, Seok Yoon; Kim, Jung Hoon

    2014-01-01

    This study was conducted to propose medical radioactive waste management methods by background factors of radioactive workers, their awareness of safety management and reduce the difficulty of self-disposal. A population of 102 radiotechnologist who work at hospital in Busan was the subject of this study and a survey was conducted to them. the analysis for the collected data used SPSS/PC+Win13 version and one-way, ANOVA was carried out of verify differences between the groups. The result showed that most of workers had correct awareness of radioactive waste management. Also, about the difficulty of self-disposal, legal procedures were mentioned most often, and as efficient improvement of management methods is concerned, changing the awareness of safety management and disposal was proposed. According to this study, the right way of managing medical radioactive waste is to change the awareness of radioactive workers by reinforcing regular training

  6. Analysis of the awareness of medical radioactive waste management plans (with focus on Busan and Gyeongsangnam-do)

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Se Sik; Choi, Seok Yoon; Kim, Jung Hoon [Dept. of Radiological Science, College of Health Science, Catholic University of Pusan, Busan (Korea, Republic of)

    2014-03-15

    This study was conducted to propose medical radioactive waste management methods by background factors of radioactive workers, their awareness of safety management and reduce the difficulty of self-disposal. A population of 102 radiotechnologist who work at hospital in Busan was the subject of this study and a survey was conducted to them. the analysis for the collected data used SPSS/PC+Win13 version and one-way, ANOVA was carried out of verify differences between the groups. The result showed that most of workers had correct awareness of radioactive waste management. Also, about the difficulty of self-disposal, legal procedures were mentioned most often, and as efficient improvement of management methods is concerned, changing the awareness of safety management and disposal was proposed. According to this study, the right way of managing medical radioactive waste is to change the awareness of radioactive workers by reinforcing regular training.

  7. 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

  8. Radioactive Probes on Ferromagnetic Surfaces

    CERN Multimedia

    2002-01-01

    On the (broad) basis of our studies of nonmagnetic radioactive probe atoms on magnetic surfaces and at interfaces, we propose to investigate the magnetic interaction of magnetic probe atoms with their immediate environment, in particular of rare earth (RE) elements positioned on and in ferromagnetic surfaces. The preparation and analysis of the structural properties of such samples will be performed in the UHV chamber HYDRA at the HMI/Berlin. For the investigations of the magnetic properties of RE atoms on surfaces Perturbed Angular Correlation (PAC) measurements and Mössbauer Spectroscopy (MS) in the UHV chamber ASPIC (Apparatus for Surface Physics and Interfaces at CERN) are proposed.

  9. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

    Skanata, D.; Kroselj, V.; Jankovic, M.

    2007-01-01

    In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

  10. Expansion design for a radioactive sources handling laboratory type II class B

    International Nuclear Information System (INIS)

    Sanchez S, P. S.; Monroy G, F.; Alanis, J.

    2013-10-01

    The Radioactive Wastes Research Laboratory (RWRL) of the Instituto Nacional de Investigaciones Nucleares (Mexico), at the moment has three sections: instrumental analysis, radioactive material processes, counting and a license type II class C, to manipulate radioactive material. This license limits the open sources handling to 300 kBq for radionuclides of very high radio-toxicity as the Ra-226, for what is being projected the license extension to type II class B, to be able to manage until 370 MBq of this radionuclides type, and the Laboratory, since the location where is the RWRL have unused area. This work presents a proposal of the RWRL expansion, taking into account the current laboratory sections, as well as the established specifications by the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The current planes of the RWRL and the expansion proposal of the laboratory are presented. (Author)

  11. [Problems of safety regulation under radioactive waste management in Russia].

    Science.gov (United States)

    Monastyrskaia, S G; Kochetkov, O A; Barchukov, V G; Kuznetsova, L I

    2012-01-01

    Analysis of the requirements of Federal Law N 190 "About radioactive waste management and incorporation of changes into some legislative acts of the Russian Federation", as well as normative-legislative documents actual and planned to be published related to provision of radiation protection of the workers and the public have been done. Problems of safety regulation raised due to different approaches of Rospotrebnadzor, FMBA of Russia, Rostekhnadzor and Minprirody with respect to classification and categorization of the radioactive wastes, disposal, exemption from regulatory control, etc. have been discussed in the paper. Proposals regarding improvement of the system of safety regulation under radioactive waste management and of cooperation of various regulatory bodies have been formulated.

  12. Is Good Fit Related to Good Behaviour? Goodness of Fit between Daycare Teacher-Child Relationships, Temperament, and Prosocial Behaviour

    Science.gov (United States)

    Hipson, Will E.; Séguin, Daniel G.

    2016-01-01

    The Goodness-of-Fit model [Thomas, A., & Chess, S. (1977). Temperament and development. New York: Brunner/Mazel] proposes that a child's temperament interacts with the environment to influence child outcomes. In the past, researchers have shown how the association between the quality of the teacher-child relationship in daycare and child…

  13. 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.)

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

    International Nuclear Information System (INIS)

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

    1964-10-01

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

  15. Radioactive Waste Management in the European Union: Initiatives for New Legislation

    International Nuclear Information System (INIS)

    Taylor, D.

    2003-01-01

    Improving the management of radioactive waste in the European Union is a major theme of the ''nuclear package'' recently adopted by the European Commission. Included in the package are proposals for new legislation that would bring about the development of common safety standards in Europe covering the full nuclear sector, segregated funds to cover all nuclear liabilities that remain after the operating lifetime of an installation and clearly defined waste programs for radioactive waste management in each of the Member States of the Union. Included in these programs must be firm dates for a number decision points leading to disposal of all forms of radioactive waste. The package also puts significant emphasis on more, and better coordinated, research on radioactive waste management as the present levels are thought to be inadequate

  16. Radioactive waste management in the European Union: initiatives for new legislation

    International Nuclear Information System (INIS)

    Taylor, Derek M.

    2003-01-01

    Improving the management of radioactive waste in the European Union is a major theme of the 'nuclear package' recently adopted by the European Commission. Included in the package are proposals for new legislation that would bring about the development of common safety standards in Europe covering the full nuclear sector, segregated funds to cover all nuclear liabilities that remain after the operating lifetime of an installation and clearly defined waste programmes for radioactive waste management in each of the Member States of the Union. Included in these programmes must be firm dates for a number decision points leading to disposal of all forms of radioactive waste. The package also puts significant emphasis on more, and better coordinated, research on radioactive waste management as the present levels are thought to be inadequate. (author)

  17. Radioactive wastes. The management of nuclear wastes. Waste workshop, first half-year - Year 2013-2014

    International Nuclear Information System (INIS)

    Esteoulle, Lucie; Rozwadowski, Elodie; Duverger, Clara

    2014-01-01

    The first part of this report first presents radioactive wastes with their definition, and their classification (radioactivity level, radioactive half-life). It addresses the issue of waste storage by presenting the different types of storage used since the 1950's (offshore storage, surface warehousing, storage in deep geological layer), and by discussing the multi-barrier approach used for storage safety. The authors then present the French strategy which is defined in the PNGMDR to develop new management modes on the long term, to improve existing management modes, and to take important events which occurred between 2010 and 2012 into account. They also briefly present the Cigeo project (industrial centre of geological storage), and evoke controversies related to the decision to locate this project in Bure (existence of geological cracks and defects, stability and tightness of the clay layer, geothermal potential of the region, economic cost). The second part proposes an overview of the issue of nuclear waste management. The author recalls the definition of a radioactive waste, indicates the origins of these wastes and their classification. She proposes a history of the radioactive waste: discovery of radioactivity, military industrialisation and awareness of the dangerousness of radioactive wastes, nuclear wastes and recent incidents (West Valley, La Hague, Windscale). An overview of policies of nuclear waste management is given: immersion of radioactive wastes, major accidental releases, solutions on the short term and on the medium term

  18. The use of nuclear prospecting measurements for characterizing the radioactive status of Al-Bayyarat and Sabkhet Mouh areas, southern Palmyrides, Syria

    International Nuclear Information System (INIS)

    Asfahani, J.; Al-Hent, R.; Aissa, M.

    2014-01-01

    Al-Bayyarat and Sabkhet Mouh areas in southern Palmyride have been radioactively characterized by using different nuclear prospecting measurements. Those measurements include the application of airborne, carborne spectrometric gamma, radon emanation and borehole techniques. The merging of airborne, carborne spectrometric gamma data enables to establish the normalized eU, eTh, and K% maps in the study area. Radon emanation and spectrometric gamma measurements have been applied only in Al- Bayyarat area, where radioactive anomalous zone has been observed. The radioactive characteristics of the study area has been explained through studying and analyzing a profile of 30 Km long, where a plausible geo-radioactive model has been proposed for the uranium leaching and its transport. - Highlights: • Determine the radioactive characteristics of the study area. • Explain the radioactive anomaly observed in Al-Bayarat area. • Analysis of a profile of 30 Km and propose a plausible geo-radioactive model. • Discus the radioactive disequilibrium occurred in the study area

  19. Radioactive Waste and Clean-up: Introduction

    International Nuclear Information System (INIS)

    Collard, G.

    2007-01-01

    The primary mission of the Radioactive Waste and Clean-up division is to propose, to develop and to evaluate solutions for a safe, acceptable and sustainable management of radioactive waste. The Radioactive Waste and Clean-up division programme consists in research, studies, development and demonstration aiming to realise the objective of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation on radioactively contaminated sites. Indeed, it participates in the realisation of an objective which is to ensure that radioactive wastes are safely managed, transported, stored and disposed of, with a view to protecting human health and the environment, within a wider framework of an interactive and integrated approach to radioactive waste management and safety. We believe that nuclear energy will be necessary for the sustainable development of mankind in the 21st century, but we well understand that it would not be maintained if it is not proven that within benefits of nuclear energy a better protection of the environment is included. Although the current waste management practices are both technically and from the environmental point of view adequate, efforts in relation of future power production and waste management technologies should be put on waste minimisation. Therefore, the new and innovative reactors, fuel cycle and waste management processes and installations should be designed so that the waste generation can be kept in minimum. In addition to the design, the installations should be operated so as to create less waste; consideration should be given e.g. to keeping water chemistry clean and other quality factors. SCK-CEN in general and the Radioactive Waste and Clean-up division in particular are present in international groups preparing the development of innovative nuclear reactors, as Generation 4 and INPRO. Because performance assessments are often black boxes for the public, demonstration is needed for the acceptation of

  20. Transport of radioactive materials: the need for radiation protection programmes

    International Nuclear Information System (INIS)

    Masinza, S.A.

    2004-01-01

    The increase in the use of radioactive materials worldwide requires that these materials be moved from production sites to the end user or in the case of radioactive waste, from the waste generator to the repository. Tens of millions of packages containing radioactive material are consigned for transport each year throughout the world. The amount of radioactive material in these packages varies from negligible quantities in shipments of consumer products to very large quantities of shipments of irradiated nuclear fuel. Transport is the main way in which the radioactive materials being moved get into the public domain. The public is generally unaware of the lurking danger when transporting these hazardous goods. Thus radiation protection programmes are important to assure the public of the certainty of their safety during conveyance of these materials. Radioactive material is transported by land (road and rail), inland waterways, sea/ocean and air. These modes of transport are regulated by international 'modal' regulations. The international community has formulated controls to reduce the number of accidents and mitigate their consequences should they happen. When accidents involving the transport of radioactive material occur, it could result in injury, loss of life and pollution of the environment. In order to ensure the safety of people, property and the environment, national and international transport regulations have been developed. The appropriate authorities in each state utilise them to control the transport of radioactive material. Stringent measures are required in these regulations to ensure adequate containment, shielding and the prevention of criticality in all spheres of transport, i.e. routine, minor incidents and accident conditions. Despite the extensive application of these stringent safety controls, transport accidents involving packages containing radioactive material have occurred and will continue to occur. When a transport accident occurs, it

  1. Radioactive wastes in nuclear fuel cycle

    International Nuclear Information System (INIS)

    Sakata, Sadahiro; Nagaike, Tadakatsu; Emura, Satoru; Matsumoto, Akira; Morisawa, Shinsuke.

    1978-01-01

    Recent topics concerning radioactive water management and disposal are widely reviewed. As the introduction, various sources of radioactivity including uranium mining, fuel fabrication, reactor operation and fuel reprocessing and their amount of wastes accumulated per 1000 MWe year operation of a LWR are presented together with the typical methods of disposal. The second section discusses the problems associated with uranium fuel fabrication and with nuclear power plants. Typical radioactive nuclides and their sources in PWRs and BWRs are discussed. The third section deals with the problems associated with reprocessing facilities and with mixed oxide fuel fabrication. Solidification of high-level wastes and the methods of the disposal of transuranic nuclides are the main topics in this section. The fourth section discusses the methods and the problems of final disposal. Various methods being proposed or studied for the final disposal of low- and high-level wastes and transuranic wastes are reviewed. The fifth section concerns with the risk analysis of waste disposal. Both deterministic and probabilistic methods are treated. As the example, the assessment of the risk due to floods is explained. The associated event tree and fault three are presented together with the estimated probability of the occurrence of each constituent failure. In the final section, the environmental problems of radioactive wastes are widely reviewed. (Aoki, K.)

  2. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

  3. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    International Nuclear Information System (INIS)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L.

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R ampersand D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R ampersand D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action

  4. Measurement methodology of natural radioactivity in the thermal establishments

    International Nuclear Information System (INIS)

    Ameon, R.; Robe, M.C.

    2004-11-01

    The thermal baths have been identified as an activity susceptible to expose to ionizing radiations the workers through the natural sources of radon and radon 220. The new regulation obliges these facilities to realize radioactivity measurements. The principal ways of exposure are radon and its daughters inhalation,, exposure to gamma radiation, ingestion of radioelements in thermal waters. I.R.S.N. proposes two methods of measurements of the natural radioactivity in application to the regulation relative to the protection of persons and workers. Some principles to reduce exposure to radon are reminded. (N.C.)

  5. Import/Export Service of Radioactive Material and Radioactive Sources Service

    CERN Multimedia

    2004-01-01

    Please note that the Import/Export Service of radioactive material (http://cern.ch/service-rp-shipping/ - e-mail : service-rp-shipping@cern.ch) and the Radioactive Sources Service (http://cern.ch/service-radioactive-sources - e-mail : service-radioactive-sources@cern.ch) at bldg. 24/E-024 will be closed on FRIDAY 10 SEPTEMBER 2004. Tel. 73171

  6. Assessment of the indicator of sustainable development for radioactive waste management

    International Nuclear Information System (INIS)

    Jung, J. H.; Park, W. J.

    2003-01-01

    As a follow up to the agenda 21's policy statement for safe management of radioactive waste adopted at Rio Conference held in 1992, the UN invited the IAEA to develop and implement indicators of sustainable development for the management of radioactive waste. The IAEA finalized the indicators in 2002, and is planning to calculate the member states' values of indicator in connection with operation of its Net-Enabled Waste Management Database system. In this paper, the basis for introducing the indicators into the radioactive waste management was analyzed, and calculation methodology and standard assessment procedure were simply depicted. According to the proposed standard procedure, the indicators for some countries including Korea were calculated and compared, by use of each country's radioactive waste management framework and its practices. In addition, a series of measures increasing the values of the indicators was derived so as to enhance the sustainability of domestic radioactive waste management program

  7. The development of regulations for road vehicles used in the conveyance of dangerous goods

    International Nuclear Information System (INIS)

    Kdolsky, L.

    1980-01-01

    Aspects of dangerous goods transport are classified according to risks associated with control of the vehicles themselves, trailers, traffic, the goods carried, safety of packing materials, crates and containers and the handling problems. Eight different classifications of goods (e.g. explosive, inflammable, radioactive) listed as potentially dangerous by European authorities are quoted. Theoretical studies are outlined, requiring 6 hours for general studies of the official (ADR) classifications, and 3 hours for specialist work. Documentation involved includes accident reports, licence applications, personnel and traffic records. Practical work (3 hours study) includes examination of vehicles and goods and visual displays (e.g. by film) of typical accidents, causes, consequences and negotiations with civil authorities. (G.C.)

  8. 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.)

  9. Heavy fragment radioactivity

    International Nuclear Information System (INIS)

    Silisteanu, I.

    1991-06-01

    The effect of collective mode excitation in heavy fragment radioactivity (HFR) is explored and discussed in the light of current experimental data. It is found that the coupling and resonance effects in fragment interaction and also the proper angular momentum effects may lead to an important enhancing of the emission process. New useful procedures are proposed for the study of nuclear decay properties. The relations between different decay processes are investigated in detail. We are also trying to understand and explain in a unified way the reaction mechanisms in decay phenomena. (author). 17 refs, 4 figs, 3 tabs

  10. Radioactive materials transport: a story of steady technical improvement

    International Nuclear Information System (INIS)

    Price, M.

    1991-01-01

    The transport of radioactive material is a fundamental part of the nuclear industry and equally vital to the use of radioisotopes in medical diagnosis and therapy. The safety record is impressively good and this aids open discussion of the subject. An independent consultant formerly with Atomic Energy Authority Technology reports on the Second International Conference on Transportation for the Nuclear Industry. (Author)

  11. KS 2031 Radioactive waste - Disposal by the user - Code of practice

    International Nuclear Information System (INIS)

    Mayaka, Edward E.

    2017-01-01

    Sources of ionizing radiation are widely used in Medicine, Agriculture, Industry, Research and Education, and Security checks. The purpose of this code of practice is to recommend practices which are helpful in achieving the ALARA principle for small quantities of radioactive waste and which will ensure a degree of uniformity in radioactive waste disposal procedures. It has been prepared to supplement the radiation control legislation implemented by the Radiation Protection Board. It is possible to carry out a formal radiological hazard assessment of any proposed radioactive waste disposal activity that provides estimates of the risk to a population that is potentially exposed to ionising radiation as a result of the activity

  12. Quality assurance in processing radioactive waste for land disposal

    International Nuclear Information System (INIS)

    1984-01-01

    To provide the appropriate assurances as to the quality of processed radioactive waste it is necessary to consider the complete range of activities involved in the formation and operation of a radioactive waste processing facility. To this end, an outline has been given to the individual elements which should be addressed in quality assurance proposals to the authorising Departments. In general terms, the quality checks on product material should be aimed at demonstrating that the radioactive waste product is what was agreed at the time of process approval. In addition, at the discretion of the authorising Departments, the waste processor will be required to confirm that the product meets any specific acceptance criteria such as the capability to retain the immobilised radionuclides when in contact with water. (author)

  13. National plan of radioactive wastes and matters 2007-2009

    International Nuclear Information System (INIS)

    2006-01-01

    This Plan aims to propose a global framework allowing the management of radioactive wastes, whatever the producers in order to control the safety and the choice of adapted disposal sites. The first part is devoted to the description of solutions of radioactive wastes management for existing or engaged wastes. The second part concerns radioactive materials of the nuclear industry which are not considered as wastes, but as recycling materials for future nuclear reactors. For instance, this part discusses the particular case of the depleted uranium. The third part examines the different channels of the long dated management. The last part brings together the all data and in particular problematic points which must be discussed and analyzed in a logic framework. Propositions and recommendations are provided. (A.L.B.)

  14. Immobilization of radioactive waste in glass matrices

    International Nuclear Information System (INIS)

    Wicks, G.G.

    1978-01-01

    A promising process for long-term management of high-level radioactive waste is to immobilize the waste in a borosilicate glass matrix. Among the most important criteria characterizing the integrity of the large-scale glass-waste forms are that they possess good chemical stability (including low leachability), thermal stability, mechanical integrity, and high radiation stability. Fulfillment of these criteria ensures the maximum margin of safety of glass-waste products, following solidification, handling, transportation, and long-term storage

  15. 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

  16. The Michigan high-level radioactive waste program: Final technical progress report

    International Nuclear Information System (INIS)

    1987-01-01

    This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

  17. Implementing Decree of 29 February 1956 relating to Annex I of the International Convention concerning the Carriage of Goods by Rail (CIM)

    International Nuclear Information System (INIS)

    1956-01-01

    This implementing Decree on Annex I of the International Convention concerning the Carriage of Goods by Rail (CIM) brings into force in Austria the provisions of that Annex on the materials and goods excluded from transport or included under certain conditions defined by the International Regulations concerning the Carriage of Dangerous Goods by Rail (RID). It lays down 7 classes of material; class IVb concerns radioactive materials which are divided into groups A and B respectively covering those emitting gamma-rays and neutrons and those emitting alpha or beta rays. For this latter class, the transport provisions fix packaging criteria; despatch method, markings; it is forbidden to load radioactive materials together with explosives or Groups A and B together. (NEA) [fr

  18. The regulatory framework concerning the safe transport of radioactive material in the European Union

    International Nuclear Information System (INIS)

    Schwarz, G.; Ridder, K.

    2002-01-01

    Radioactive materials of natural and manmade origins are employed worldwide in many areas, such as medicine, research, energy generation, and industry. As a consequence of the special nature and the properties of radioactive substances, irregular handling and use of such materials entails hazards. This is why special safety and protection provisions have been made in the interest of protecting health, life, property, and the environment from such hazards. The development and use of harmonized goals of protection and standards of safety is essential to free trade and the exchange of goods and services within the European Union and worldwide. The national and international institutions and organizations responsible for the protection and safety of transports of radioactive materials, including the European Union and its member countries, early on recognized the need for harmonized safety standards and criteria for transports of dangerous goods and developed an appropriate system of standards of safety and protection and a comprehensive set of tools for monitoring and checking observance of these standards. These tools have been laid down in a system of legally binding agreements, regulations, directives etc., or in recommendations, for the fifteen EU member states. The article presents this system of legally binding agreements, regulations, and recommendations, respectively, which covers the protection and safety of national and international transports of radioactive materials. (orig.) [de

  19. Studies on treatment of radioactive animal carcass, (1)

    International Nuclear Information System (INIS)

    Matsuoka, Osamu; Koizumi, Akira; Fukuda, Satoshi

    1979-01-01

    A new method of waste treatment of animal carcass contaminated with plutonium was proposed. A multi-step process was designed and tested at a laboratory scale which was composed of the following processes; microwave dehydration, heat decomposition and ashing. Microwave dehydration was found the most adequate as the first step of the treatment because of the negligible release of nonvolatile radioactivity. About 70% of body weight was reduced by microwave dehydration. Dehydrated animal carcass was decomposed by graded electric heating under anaerobic condition. Burnable gas and vapour produced by the heat decomposition were oxidized by passing through a reheating tube with excess air. The exhaust gas had no significant radioactivity. The residue of charred carcass was oxidized by heating with excess air. The weight of final product was up to 8% of original wet weight. The proposed multi-step process provided to be adequate for the waste disporsal of Pu contaminated animal carcass. (author)

  20. Natural atmospheric radioactivity

    International Nuclear Information System (INIS)

    Renoux, A.

    1986-01-01

    After having summed up the different old or new units, used in radioactivity and radioprotection, the origins of atmospheric radioactivity are reported. Next the authors deal with the air content in radon, thoron and their radioactive descendants, insisting on the variations of the radon air content and on the radioactive balance between radon and its descendants. Then a few notions concerning the natural radioactive aerosol are developed: electric charge state, granulometric distribution. The possible effects of natural atmospheric radioactivity on man are studied with a distinction between inner irradiation and outer irradiation, an average assessment is shown. Finally the important problem of radon in inhabitations is approached [fr

  1. Characterization, propagation and analysis of aleatory and epistemic uncertainty in the 2008 performance assessment for the proposed repository for radioactive waste at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Helton, Jon Craig; Sallaberry, Cedric M.; Hansen, Clifford W.

    2010-01-01

    The 2008 performance assessment (PA) for the proposed repository for high-level radioactive waste at Yucca Mountain (YM), Nevada, illustrates the conceptual structure of risk assessments for complex systems. The 2008 YM PA is based on the following three conceptual entities: a probability space that characterizes aleatory uncertainty; a function that predicts consequences for individual elements of the sample space for aleatory uncertainty; and a probability space that characterizes epistemic uncertainty. These entities and their use in the characterization, propagation and analysis of aleatory and epistemic uncertainty are described and illustrated with results from the 2008 YM PA.

  2. Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas

    International Nuclear Information System (INIS)

    Rogers, B.C.; Walter, P.L.; Baird, R.D.

    1999-01-01

    This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation

  3. Reversibility and switching options values in the geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Ionescu, Oana; Spaeter, Sandrine

    2011-07-01

    This article offers some economic insights for the debate on the reversible geological disposal of radioactive waste. Irreversibility due to large sunk costs, an important degree of flexibility and several sources of uncertainty are taken into account in the decision process relative to the radioactive waste disposal. We draw up a stochastic model in a continuous time framework to study the decision problem of a reversible repository project for the radioactive waste, with multiple disposal stages. We consider that the value of reversibility, related to the radioactive waste packages, is jointly affected by economic and technological uncertainty. These uncertainties are modeled, first, by a 2-Dimensional Geometric Brownian Motion, and, second, by a Geometric Brownian Motion with a Poisson jump process. A numerical analysis and a sensitivity study of various parameters are also proposed. Switching options values in the geological disposal of radioactive waste. (authors)

  4. 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

  5. Teaching about radioactivity and ionising radiation: an alternative approach

    International Nuclear Information System (INIS)

    Millar, R.; Klaassen, K.; Eijkelhof, H.

    1990-01-01

    This article reviews children's ideas about radiation and radioactivity and identifies several common areas of misunderstanding. A new approach to teaching the topic at school level, which seeks specifically to address these known difficulties, is then proposed and outlined. (author)

  6. Packaging and transport of low and intermediate level radioactive waste

    International Nuclear Information System (INIS)

    Smith, M.J.S.; Streatfield, R.E.

    1987-02-01

    The paper presents an overview of Nirex proposals for the packaging and transport of low and intermediate-level radioactive waste, as well as the regulatory requirements which must be met in such operations. (author)

  7. Yearly plan of safety research on environmental radioactivity for 1996 - 2000

    International Nuclear Information System (INIS)

    1996-01-01

    'Yearly Plan of Safety Research on Environmental Radioactivity' proposed from the special meeting for safety research of environmental radioactivity on December 14, 1995 was investigated by Nuclear Safety Commission. And the safety research of environmental radioactivity in Japan was decided to be pursued according to the plan. The contents of this plan consisted of the purpose and the contents of research as well as the research period and the facilities to be done for each theme. The following themes were included; 1) study on environment·radiation dose and study on radiation exposure reduction. 2) study on biological effects of radiation. 3) study on internal exposure by specified nuclides. 4) study on medical measures for acute radiation exposure. 5) study on assessment of nuclear safety. 6) investigation on radioactivities released from various nuclear facilities in Japan to demonstrate their safety. (M.N.)

  8. Siting regions for deep geological repositories. Nagra’s proposals for stage 3

    International Nuclear Information System (INIS)

    2014-01-01

    This brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) discusses the selection of sites for deep geological repositories for nuclear wastes in Switzerland. The procedure proposed for the selection process is explained. The four sites for possible repositories of high-level radioactive waste as well as for low and intermediate-level wastes are described and rated with respect to the various safety factors involved. The reasons for the long-term safety measures proposed and the geological barriers involved are discussed. The four proposals for depository sites are looked at in more detail. The paper is well illustrated with several diagrams and tables

  9. An automated LS(β)- NaI(Tl)(γ) coincidence system as absolute standard for radioactivity measurements.

    Science.gov (United States)

    Joseph, Leena; Das, A P; Ravindra, Anuradha; Kulkarni, D B; Kulkarni, M S

    2018-07-01

    4πβ-γ coincidence method is a powerful and widely used method to determine the absolute activity concentration of radioactive solutions. A new automated liquid scintillator based coincidence system has been designed, developed, tested and established as absolute standard for radioactivity measurements. The automation is achieved using PLC (programmable logic controller) and SCADA (supervisory control and data acquisition). Radioactive solution of 60 Co was standardized to compare the performance of the automated system with proportional counter based absolute standard maintained in the laboratory. The activity concentrations determined using these two systems were in very good agreement; the new automated system can be used for absolute measurement of activity concentration of radioactive solutions. Copyright © 2018. Published by Elsevier Ltd.

  10. Evaluation of site-generated radioactive waste treatment and disposal methods for the Yucca Mountain repository

    International Nuclear Information System (INIS)

    Subramanian, C.V.; Jardine, L.J.

    1989-01-01

    This study identifies the sources of radioactive wastes that may be generated at the proposed high-level waste (HLW) repository at Yucca Mountain, NV, estimates the waste quantities and characteristics, compares technologies available for waste treatment and disposal, and develops recommended concepts for site-generated waste treatment and disposal. The scope of this study is limited to operations during the emplacement phase, in which 70,000 MTU of high-level waste will be received and emplaced at the proposed repository. The evaluations consider all radioactive wastes generated during normal operations in surface and underground facilities. Wastes generated as a result of accidents are not addressed; accidents that could result in large quantities of radioactive waste are expected to occur very infrequently and temporary, portable systems could be used for any necessary cleanup. The results of this study can be used to develop more definitive plans for managing the site-generated wastes and as a basis for the design of associated facilities at the proposed repository

  11. Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, S.M.

    1997-10-01

    In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country''s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today''s standards. This report summarizes each site''s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US

  12. Cross flow filtration of aqueous radioactive tank wastes

    International Nuclear Information System (INIS)

    McCabe, D.J.; Reynolds, B.A.; Todd, T.A.; Wilson, J.H.

    1997-01-01

    The Tank Focus Area (TFA) of the Department of Energy (DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground tanks. Baseline technologies for treatment of tank waste can be categorized into three types of solid liquid separation: (a) removal of radioactive species that have been absorbed or precipitated, (b) pretreatment, and (c) volume reduction of sludge and wash water. Solids formed from precipitation or absorption of radioactive ions require separation from the liquid phase to permit treatment of the liquid as Low Level Waste. This basic process is used for decontamination of tank waste at the Savannah River Site (SRS). Ion exchange of radioactive ions has been proposed for other tank wastes, requiring removal of insoluble solids to prevent bed fouling and downstream contamination. Additionally, volume reduction of washed sludge solids would reduce the tank space required for interim storage of High Level Wastes. The scope of this multi-site task is to evaluate the solid/liquid separations needed to permit treatment of tank wastes to accomplish these goals. Testing has emphasized cross now filtration with metal filters to pretreat tank wastes, due to tolerance of radiation and caustic

  13. [EDRP public local inquiry] radioactive waste management statement

    International Nuclear Information System (INIS)

    1986-03-01

    The statutory arrangements which will apply to the proposed EDRP at Dounreay in relation to radioactive waste management matters, and the principles against which it will be assessed, are described. Also included are some preliminary, provisional comments on the waste management implications of the outline application. (U.K.)

  14. Proposed systematic methodology for analysis of Pb-210 radioactivity in residues produced in Brazilian natural gas pipes

    International Nuclear Information System (INIS)

    Ferreira, Aloisio Cordilha

    2003-11-01

    Since the 80's, the potential radiological hazards due to the handling of solid wastes contaminated with Rn-222 long-lived progeny - Pb-210 in special - produced in gas pipes and removed by pig operations have been subject of growing concern abroad our country. Nevertheless, little or no attention has been paid to this matter in the Brazilian plants up to now, being these hazards frequently underestimated or even ignored. The main purpose of this work was to propose a systematic methodology for analysis of Pb-210 radioactivity in black powder samples from some Brazilian plants, through the evaluation of direct Pb-210 gamma spectrometry and Bi-210 beta counting technical viabilities. In both cases, one in five samples of black powder analysed showed relevant activity (above 1Bq/kg) of Pb-210, being these results probably related to particular features of each specific plant (production levels, reservoir geochemical profile, etc.), in such a way that a single pattern is not observed. For the proposed methodology, gamma spectrometry proved to be the most reliable technique, showing a 3.5% standard deviation, and, for a 95% confidence level, overall fitness in the range of Pb-210 concentration of activity presented in the standard sample reference sheet, provided by IAEA for intercomparison purposes. In the Brazilian scene, however, the availability of statistically supported evidences is insufficient to allow the potential radiological hazard due to the management of black powder to be discarded. Thus, further research efforts are recommended in order to detect the eventually critical regions or plants where gas exploration, production and processing practices will require a regular program of radiological surveillance, in the near future. (author)

  15. A simple test for PPP among traded goods

    NARCIS (Netherlands)

    Ph.H.B.F. Franses (Philip Hans); D.J.C. van Dijk (Dick)

    2002-01-01

    textabstractThe so-called Balassa-Samuelson model implies that relative prices of non-traded goods may be nonstationary and, hence, that PPP should preferably be tested on real exchange rates based on prices of traded goods only. We propose a simple test for PPP among traded goods which can be

  16. Modified microspheres for cleaning liquid wastes from radioactive nuclides

    International Nuclear Information System (INIS)

    Danilin, Lev; Drozhzhin, Valery

    2007-01-01

    An effective solution of nuclear industry problems related to deactivation of technological and natural waters polluted with toxic and radioactive elements is the development of inorganic sorbents capable of not only withdrawing radioactive nuclides, but also of providing their subsequent conservation under conditions of long-term storage. A successful technical approach to creation of sorbents can be the use of hollow aluminosilicate microspheres. Such microspheres are formed from mineral additives during coal burning in furnaces of boiler units of electric power stations. Despite some reduction in exchange capacity per a mass unit of sorbents the latter have high kinetic characteristics that makes it possible to carry out the sorption process both in static and dynamic modes. Taking into account large industrial resources of microspheres as by-products of electric power stations, a comparative simplicity of the modification process, as well as good kinetic and capacitor characteristics, this class of sorbents can be considered promising enough for solving the problems of cleaning liquid radioactive wastes of various pollution levels. (authors)

  17. The radioactive organic wastewater treatment of INER

    International Nuclear Information System (INIS)

    Shen Chinchang; Chen Chaorui; Chung Jenchren

    2014-01-01

    The treatment strategy of radioactive organic wastewater was to separate it at first, then to treat it step by step by the characteristics of liquid layer. The waste liquid has separated into three layers, the organic layer, aqueous layer and the bottom gel mastic by natural sedimentation. The organic layer has occupied 23% of the total volume, the intermediate aqueous layer occupied 75% of the total volume, the bottom mastic was about 2% of the total. The aqueous layer of organic waste was with Total Organic Carbon (TOC) 20,000ppm. The combustion test shows good treatment performance and all samples can be decomposed completely by incineration. The experiment of incineration has passed the test more than 200 batches and 3000L low-level radioactive organic aqueous solution. The process goes smoothly and gas emission values far below the regulatory limit. Each kilogram of polymer absorber can absorb 45 kg aqueous solution to form a solid combustible material and can be decomposed by incineration. Organic waste solvents were diesel miscible and similar calorific value and small viscosity. It can be used as an incinerator auxiliary fuel of radioactive incinerator. The method testing has begun in this year. It has expected to save diesel fuel consumption of incineration, and well solved such kind waste liquid. (author)

  18. The effect of alternative constraints in radioactive waste disposal on minimum cost scenarios

    International Nuclear Information System (INIS)

    Laundy, R.S.; James, A.R.; Groom, M.S.

    1985-01-01

    The purpose of this report is to describe the results of a set of assessments of the optimum waste assignment and disposal schedule for intermediate and low level radioactive wastes using the DISPOSALS Linear Programming Model developed by CAP Scientific. The main purpose of the present study is to demonstrate the applicability of the DISPOSALS model to the field of radioactive waste management. The results presented provide a good indication of the practicability and usefulness of the model and also provide a number of detailed conclusions regarding specific cases. (author)

  19. Modelling of multiphase flow in concrete cells of the radioactive waste storage facility at El Cabril (Spain)

    International Nuclear Information System (INIS)

    Chaparro, M.C.; Saaltink, M.W.

    2015-01-01

    El Cabril is the low and intermediate level radioactive waste disposal facility for Spain. After sealing the cells that stored the radioactive waste, water was collected from a drainpipe, indicating the flow of water within the cell. A hypothesis had been proposed to explain this phenomenon which consists of capillary rise from groundwater and evaporation and condensation within the cell produced by temperature gradients caused by seasonal temperature fluctuations outside. To corroborate this hypothesis a 2D numerical model was made taking into account all relevant processes such as multiphase flow and heat transport. Data were used measured by sensors in the cells and data from laboratory test. There is a good agreement between the temperature measured by the sensors and the ones calculated by the model. The model shows a drying of the concrete at the hot side (that is the wall during summer and the container during winter). The concrete is saturated with water at the cold side (that is the container during summer and the wall in winter), leading to runoff of water to the drainpipe. The flux at this drainpipe occurred in the two yearly periods, being higher in winter than in summer. (authors)

  20. Dissolution of Kansas evaporites: the radioactive waste disposal problem

    International Nuclear Information System (INIS)

    Smith, B.J.

    1977-01-01

    The radioactive waste repository at Lyons, Kansas, focused attention on the problem of evaporite dissolution. More study is needed in the determination of the mechanisms responsible for deterioration. Also, recent water-use policies have been questioned with the need pointed out for increased effectiveness in planning. Good water planning has to take into account the role of evaporite dissolution in water quality. 23 references

  1. Analysis of radioactive strontium

    International Nuclear Information System (INIS)

    1977-01-01

    In environmental radiation survey, radioactive strontium has been analyzed in compliance with the manual ''Analyzing methods for radioactive strontium'' published in 1960 by the Science and Technology Agency, Japan, and revised in 1963. However, in a past decade, progress and development in analyzing methods and measuring equipments have been significant, therefore the manual was revised in 1974. Major revisions are as follows. (1) Analysis of 90 Sr with long half life was changed to the main theme and that of 89 Sr with short half life became a subordinate one. (2) Measuring criteria and sampling volume were revised. (3) Sample collection method was unified. (4) Analyzing method for soil was improved to NaOH-HCl method which has good recovery rate. (5) 90 Y separation method of simple operation was added for sea water analysis besides EDTA and fuming nitric acid methods. (6) Flame spectrometry for quantitative analysis of stable strontium was revised to atomic absorption spectrometry. The contents of the manual comprises 11 chapters describing introduction, measuring criteria for 90 Sr ( 89 Sr), rain and dust, land water, sea water, soil, sea bottom and river bottom sediments (changed from human urine and human bones), crops, milk (the previous one chapter was divided into two), marine organisms, and everyday foods, respectively. (Wakatsuki, Y.)

  2. A MWPC with a cathode coupled delay line read-out as radioactivity detector for DNA repair studies

    International Nuclear Information System (INIS)

    Bellazzini, R.; Del Guerra, A.; Massai, M.M.; Ragadini, M.; Spandre, G.; Tonelli, G.

    1981-01-01

    A non selective method for the isolation of DNA repair-deficient mutants in mammalian cells is discussed. The method requires radioactive labelling of the short DNA sequences synthesized during repair of damaged regions. Mutants should be recognized by the absence of radioactive incorporation into their DNA. A multiwire proportional chamber (MWPC) is proposed as a suitable radioactivity detector. The performance of a MWPC prototype with a cathode coupled delay line read-out is described and is shown to be adequate for this application. The main advantages of a MWPC are reviewed with respect to other methods used for β - radioactivity counting of biological samples, such as liquid scintillators or autoradiography: the proposed detection method is non destructive for the cells, which are being kept alive for further biological studies, furthermore many cell clones can be screened within a reasonable time. (orig.)

  3. Demister apparatus for gaseous wastes carrying radioactive aerosols

    International Nuclear Information System (INIS)

    Meline, F.G.; Richter, R.J.

    1983-01-01

    In the nuclear industry, more precisely in the field of spent fuel reprocessing, the cleaning of the gaseous wastes, before evacuation, should be realized with a device designed in order to take full account of the constraints that are inherent in the radioactive media. The French Atomic Authority (CEA), in collaboration with the Societe Generale pour les Techniques Nouvelles, have studied and developed types of demister for the nuclear field having good cleaning properties

  4. Current and proposed revisions, changes, and modifications to American codes and standards to address packaging, handling, and transportation of radioactive materials and how they relate to comparable international regulations

    International Nuclear Information System (INIS)

    Borter, W.H.; Froehlich, C.H.

    2004-01-01

    This paper addresses current and proposed revisions, additions, and modifications to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) (i.e., ''ASMEthe Code'') Section III, Division 3 and American National Standards Institute (ANSI)/ASME N14.6. It provides insight into the ongoing processes of the associated committees and highlights important revisions, changes, and modifications to this Code and Standard. The ASME Code has developed and issued Division 3 to address items associated with the transportation and storage of radioactive materials. It currently only addresses ''General Requirements'' in Subsections WA and ''Class TP (Type B) Containments'' (Transportation Packages) in Subsection WB, but is in the process of adding a new Subsection WC to address ''Class SC'' (Storage Containments). ANSI/ASME Standard N14.6 which interacts with components constructed to Division 3 by addressinges special lifting devices for radioactive material shipping containers. This Standard is in the process of a complete re-write. This Code and Standard can be classified as ''dynamic'' in that their committees meet at least four times a year to evaluate proposed modifications and additions that reflect current safety practices in the nuclear industry. These evaluations include the possible addition of new materials, fabrication processes, examination methods, and testing requirements. An overview of this ongoing process is presented in this paper along with highlights of the more important proposed revisions, changes, and modifications and how they relate to United States (US) and international regulations and guidance like International Atomic Energy Agency (IAEA) Requirement No. TS-R-1

  5. 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.

  6. 30 years of the Goiania Accident: a comparative study with other radioactivity dispersion events

    International Nuclear Information System (INIS)

    Smith, Ricardo Bastos; Vicente, Roberto

    2017-01-01

    The year 2017 marks 30 years since the radioactive accident that occurred in the city of Goiania, capital of the state of Goias. It was the largest radiological accident in Brazil, and one of the largest in the world occurring outside nuclear facilities. Regarding the accidents at nuclear power plants, two of the biggest were Chernobyl in Ukraine, a year and a half before Goiania, and the Fukushima accident in Japan, in 2011. Different amounts of radioactive material were dispersed in the environment in each of these events. However, each one’s main pathway of dispersion was different: the accident of Goiania was terrestrial, Chernobyl was at the atmosphere, and Fukushima was mainly in the ocean. This work aims to study these different amounts, comparing such activities. In addition, it proposes to compare the sea dispersion of Fukushima with the amount of radioactive waste dumped in the oceans, when the release of radioactive waste at sea was permitted. It also proposes to compare the Chernobyl aerial dispersion with the radioactive material dissipated in the atmosphere, resulting from the more than 500 atmospheric nuclear tests conducted between 1945 and 1962 by the United States, the former Soviet Union, England, France and China. (author)

  7. 30 years of the Goiania Accident: a comparative study with other radioactivity dispersion events

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Ricardo Bastos; Vicente, Roberto, E-mail: rbsmith@ipen.br, E-mail: rvicente@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The year 2017 marks 30 years since the radioactive accident that occurred in the city of Goiania, capital of the state of Goias. It was the largest radiological accident in Brazil, and one of the largest in the world occurring outside nuclear facilities. Regarding the accidents at nuclear power plants, two of the biggest were Chernobyl in Ukraine, a year and a half before Goiania, and the Fukushima accident in Japan, in 2011. Different amounts of radioactive material were dispersed in the environment in each of these events. However, each one’s main pathway of dispersion was different: the accident of Goiania was terrestrial, Chernobyl was at the atmosphere, and Fukushima was mainly in the ocean. This work aims to study these different amounts, comparing such activities. In addition, it proposes to compare the sea dispersion of Fukushima with the amount of radioactive waste dumped in the oceans, when the release of radioactive waste at sea was permitted. It also proposes to compare the Chernobyl aerial dispersion with the radioactive material dissipated in the atmosphere, resulting from the more than 500 atmospheric nuclear tests conducted between 1945 and 1962 by the United States, the former Soviet Union, England, France and China. (author)

  8. Radioactive Waste Management Research Program Plan for high-level waste: 1987

    International Nuclear Information System (INIS)

    1987-05-01

    This plan will identify and resolve technical and scientific issues involved in the NRC's licensing and regulation of disposal systems intended to isolate high level hazardous radioactive wastes (HLW) from the human environment. The plan describes the program goals, discusses the research approach to be used, lays out peer review procedures, discusses the history and development of the high level radioactive waste problem and the research effort to date and describes study objectives and research programs in the areas of materials and engineering, hydrology and geochemistry, and compliance assessment and modeling. The plan also details the cooperative interactions with international waste management research programs. Proposed Earth Science Seismotectonic Research Program plan for radioactive waste facilities is appended

  9. Removal of some ions from the radioactive liquid wastes by means of membrane techniques

    International Nuclear Information System (INIS)

    Roman, Gabriela; Garganciuc, Dana; Batrinescu, Gheorghe; Popescu, Georgeta

    2000-01-01

    The radioactive wastes imply important problems in the pollution control. Contrary to the case of other liquid wastes, which are specifically treated depending on the nature of pollutants, the liquid radioactive wastes are treated as a function of their activity (high, medium or low) and not depending on the nature of radioisotopes. The paper presents the advantages of the membrane processes as comparing with the classical processes in the removal of some ions from liquid radioactive waste up to values admissible of the current standards. Two types of radioactive liquid solutions were processed namely: one solution from the decontamination of the parts of an installation and other from the decontamination of primary circuit of the nuclear power plant. The first solution was treated with ultrafiltration and reverse osmosis, the retention for radioactive and toxic elements ranging between 14 - 69% for ultrafiltration and 63 - 99% for reverse osmosis. The second solution was processed only with reverse osmosis, a retention between 64 - 98% being obtained. The tests proved that by reverse osmosis membrane process a good removal efficiency of radioactive elements from liquid waste is obtained, corresponding to the requirements imposed by the current regulations. (author)

  10. Reconstruction and modernization of Novi Han radioactive waste repository

    International Nuclear Information System (INIS)

    Kolev, I.

    2001-01-01

    The paper is an overview of the Feasibility Study for Reconstruction and Modernisation of Novi Han Radioactive Waste Repository (NHRWR), performed by EQE Bulgaria AD in 2000 for the Institute for Nuclear Research and Nuclear Energy of the Bulgarian Academy of Sciences. The Study develops a concept for overall reconstruction and modernisation of NHRWR, including rehabilitation and partial reconstruction of existing facilities and planning of new facilities for conditioning and storage of various radioactive wastes and spent sealed sources. The paper presents the general modernisation concept and outlines the proposed principle technical solutions for the existing and new facilities. (author)

  11. Feasibility of storing radioactive wastes in Columbia River basalts

    International Nuclear Information System (INIS)

    Deju, R.A.

    1976-01-01

    In 1968 Atlantic Richfield Hanford Company initiated a study to assess the feasibility of final geologic storage of Hanford defense, radioactive waste in deep caverns constructed in the Columbia River flood basalts. The project, which included geologic studies, hydrologic tests, heat flow analysis, compatibility analysis, and tectonic studies, was suspended in 1972 before completion of interpretive work. In 1976 the interpretation and documentation were completed. These data may be valuable in qualifying the Columbia River flood basalts as a viable medium for final geologic storage of commercial radioactive waste. The findings to date are summarized, and the proposed future work is presented

  12. Suggestions on technical guide of implantation of radioactive seeds

    International Nuclear Information System (INIS)

    Wang Zhongmin; Huang Gang; Lv Zhongwei; Liu Jianjun; Chen Kemin; Chen Yongde

    2009-01-01

    Implantation of radioactive seeds is an effective therapeutic option for the treatment of malignant tumors. With the development of imaging technique and the use of treatment planning system (TPS) it has been more and more employed in clinical settings. The technique has been widely practiced in various malignant tumors, such as prostate cancer, lung caner, pancreatic cancer, hepatocarcinoma, etc. In order to standardize the clinical application of this technology, the authors propose some suggestions concerning the management of radioactive seeds, the indications and contraindications as well as the method of operation as a technical guidance. (authors)

  13. Suggestions on technical guide of implantation of radioactive seeds

    Energy Technology Data Exchange (ETDEWEB)

    Zhongmin, Wang; Gang, Huang; Zhongwei, Lv; Jianjun, Liu [Department of Radiology, Luwan Branch of Ruijin Hospital, School of Medicine, Shanghai Jiaotong Univ., Shanghai (China); Kemin, Chen; Yongde, Chen

    2009-09-15

    Implantation of radioactive seeds is an effective therapeutic option for the treatment of malignant tumors. With the development of imaging technique and the use of treatment planning system (TPS) it has been more and more employed in clinical settings. The technique has been widely practiced in various malignant tumors, such as prostate cancer, lung caner, pancreatic cancer, hepatocarcinoma, etc. In order to standardize the clinical application of this technology, the authors propose some suggestions concerning the management of radioactive seeds, the indications and contraindications as well as the method of operation as a technical guidance. (authors)

  14. Radioactivity levels in surface water of lakes around Izmir / Turkey

    International Nuclear Information System (INIS)

    Doyurum, S.; Turkozu, D. A.; Aslani, M. A. A.; Aytas, S.; Eral, M.; Kaygun, A. K.

    2006-01-01

    Radioactivity presents in surface continental waters is mainly due to the presence of radioactive elements in the earth's crust, other artificial radionuclides have appeared due to such human activities as nuclear power plants, nuclear weapons testing and manufacture and use of radioactive sources It is well known that natural radionuclides can be effective as tracers for the different processes controlling the distribution of elements among dissolved and particulate phases in aquatic systems. The detection of high radionuclide concentrations was proposed as a public health problem in several areas and consequently studies into the risks of radionuclides were started in the 2000s. Especially, these radioactive substances in groundwater are an unwanted and involuntary risk factor from natural sources, not artificial sources. These radioactive substances include uranium, radon found in uranium series, and other radioactive substances such as radium and gross alpha. Uranium present in rock, soil, and natural materials, and is found in small quantities in air, water, and food that people always contact. In this project, lake water samples were collected from three lakes around Izmir-Turkey. In surface lake water samples, pH, mV and conductivity values were measured and alkaline content was determined titrimetrically. The uranium concentrations in the lake water samples were measured using uranium analyzer. The radioactivity concentrations related to gross radium isotopes, gross-? and gross-? activities in the surface lake water were determined. The correlation among some parameters for water samples and concentrations of uranium, activity concentration of gross radium isotopes, gross alpha and gross beta radioactivity are also discussed

  15. Disposal of low-level radioactive waste using high-calcium fly ash. Final report

    International Nuclear Information System (INIS)

    Cogburn, C.O.; Hodgson, L.M.; Ragland, R.C.

    1986-04-01

    The feasibility of using calcium-rich fly ash from coal-fired power plants in the disposal of low-level radioactive waste was examined. The proposed areas of use were: (1) fly-ash cement as a trench lining material; (2) fly ash as a backfill material; and (3) fly ash as a liquid waste solidifier. The physical properties of fly-ash cement were determined to be adequate for trench liner construction, with compressive strengths attaining greater than 3000 psi. Hydraulic conductivities were determined to be less than that for clay mineral deposits, and were on the order of 10 -7 cm/sec, with some observed values as low as 10 -9 cm/sec. Removal of radioisotopes from acidified solutions by fly ash was good for all elements tested except cesium. The removal of cesium by fly ash was similar to that of montmorillonite clay. The corrosive effects on metals in fly ash environments was determined to be slight, if not non-existent. Coatings at the fly-ash/metal interfaces were observed which appeared to inhibit or diminish corrosion. The study has indicated that high-calcium fly ash appears to offer considerable potential for improved retention of low-level radioactive wastes in shallow land disposal sites. Further tests are needed to determine optimum methods of use. 8 refs., 4 figs., 7 tabs

  16. Moessbauer Effect applications using intense radioactive ion beams

    International Nuclear Information System (INIS)

    Taylor, R.D.

    1990-01-01

    The Moessbauer Effect is reviewed as a promising tool for a number of new solid state studies when used in combination with radioactive beam/implantation facilities. The usual Moessbauer Effect involves long-lived radioactive parents (days to years) that populate low-lying nuclear excited states that subsequently decay to the ground state. Resonant emission/absorption of recoil-free gamma rays from these states provide information on a number of properties of the host materials. Radioactive ion beams (RIB) produced on-line allow new Moessbauer nuclei to be studied where there is no suitable parent. The technique allows useful sources to be made having extremely low local concentrations. The ability to separate the beams in both Z and A should provide high specific activity ''conventional'' sources, a feature important in some applications such as Moessbauer studies in diamond anvil high pressure cells. Exotic chemistry is proposed using RIB and certain Krypton and Xenon Moessbauer isotopes

  17. Two-layer type filter for removal of radioactive iodine

    Energy Technology Data Exchange (ETDEWEB)

    Taoki, M

    1976-04-16

    The object is to provide a filter for removing radioactive iodine, which is used for disposal of gaseous waste in an atomic power plant, to particularly hold a pressure loss lower. The filter according to the present invention comprises two layers, which are filled at a front stage with active carbon, which is small in pressure loss and has a good collective efficiency relative to iodine, and at a rear stage with silver zeolite, which has a good collective efficiency relative to both iodine and methyl iodine, whereby respective adsorbent are effectively utilized to minimize pressure loss even if a large quantity of air.

  18. Two-layer type filter for removal of radioactive iodine

    International Nuclear Information System (INIS)

    Taoki, Masafumi.

    1976-01-01

    Object: To provide a filter for removing radioactive iodine, which is used for disposal of gaseous waste in an atomic power plant, to particularly hold a pressure loss lower. Structure: The filter according to the present invention comprises two layers, which are filled at a front stage with active carbon, which is small in pressure loss and has a good collective efficiency relative to iodine, and at a rear stage with silver zeolite, which has a good collective efficiency relative to both iodine and methyl iodine, whereby respective adsorbent are effectively utilized to minimize pressure loss even if a large quantity of air. (Kamimura, M.)

  19. Radioactive materials

    International Nuclear Information System (INIS)

    Sugiura, Yoshio; Shimizu, Makoto.

    1975-01-01

    The problems of radioactivity in the ocean with marine life are various. Activities in this field, especially the measurements of the radioactivity in sea water and marine life are described. The works first started in Japan concerning nuclear weapon tests. Then the port call to Japan by U.S. nuclear-powered naval ships began. On the other hand, nuclear power generation is advancing with its discharge of warm water. The radioactive pollution of sea water, and hence the contamination of marine life are now major problems. Surveys of the sea areas concerned and study of the radioactivity intake by fishes and others are carried out extensively in Japan. (Mori, K.)

  20. HSE policy on decommissioning and radioactive waste management at licensed nuclear sites

    International Nuclear Information System (INIS)

    Bacon, M.

    1997-01-01

    In the UK, radioactive waste management and decommissioning on a licensed nuclear is regulated by the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to radioactive waste management and decommissioning activities. This provides a continuous but flexible safety regime until there is no danger from ionizing radiations. The regulatory policy is discussed, taking into account the implications of the 1995 White Paper reviewing radioactive waste management policy. For both radioactive waste management and decommissioning the key element of HSE policy is the need for strategic planning. This should ensure that problems are not allowed to build up and to demonstrate that, taking into account all factors, the proposed actions are the optimum in terms of safety. There is a presumption in HSE's policy towards disposal of radioactive waste as soon as possible where disposal routes exist. Where long-term storage is necessary passively safe forms are preferred over those requiring continuous monitoring or frequent intervention. (author)

  1. 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.

  2. First radioactive beams at ACCULINNA-2 facility and first proposed experiment

    Science.gov (United States)

    Bezbakh, A. A.; Beekman, W.; Chudoba, V.; Fomichev, A. S.; Golovkov, M. S.; Gorshkov, A. V.; Grigorenko, L. V.; Kaminski, G.; Krupko, S. A.; Mentel, M.; Nikolskii, E. Yu.; Parfenova, Yu. L.; Plucinski, P.; Sidorchuk, S. I.; Slepnev, R. S.; Sharov, P. G.; Ter-Akopian, G. M.; Zalewski, B.

    2018-04-01

    New fragment separator ACCULINNA-2 was installed at the primary beam line of the U-400M cyclotron in 2016. Recently, first radioactive ion beams were obtained. The design parameters of new facility were experimentally confirmed. Intensity, purity and transverse profile of several secondary beams at the final focal plane were studied. The intensities obtained for the secondary beams of 14B, 12Be, 9;11Li, 6;8He in the fragmentation reaction 15N (49.7 AMeV) + Be (2 mm) are in average 15 times higher in comparison to the ones produced at its forerunner ACCULINNA separator. The ACCULINNA-2 separator will become a backbone facility at the FLNR for the research in the field of light exotic nuclei in the vicinity of the nuclear drip lines. The planned first experiment, aimed for the observation of the 7H nucleus at ACCULINNA-2, is outlined.

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

    Directory of Open Access Journals (Sweden)

    Medhat Moustafa E.

    2015-01-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  5. Determination of viscosity in recirculating fluidized bed using radioactive tracer

    International Nuclear Information System (INIS)

    Silva, G.G. da.

    1986-01-01

    The use of radioactive tracer for measuring viscosity is proposed. The methodology relates the terminal velocity of a radioactive sphere in interior of fluid with the viscosity, which can be a fluidized bed or total flow of solids. The arrangement is composed by two γ detectors placed externally and along the bed. Both detectors are coupled by amplifier to electronic clock. The drop time of sphere between two detectors is measured. The bed viscosity two detectors is measured. The bed viscosity is calculated from mathematical correlations of terminal velocity of the sphere. (M.C.K.)

  6. Treating radioactive effluent

    International Nuclear Information System (INIS)

    Kirkham, I.A.

    1981-01-01

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

  7. Animal experiment on 188Re-radioactive nanometre particle esophageal stent

    International Nuclear Information System (INIS)

    Chu Jianjun; Yang Bo; Zhao Difei; Wang Mingzhi; Sun Liang; Jiang Wei

    2004-01-01

    Objective: To investigate the mechanism and clinical reliability of applying 188 Re-radioactive nanometre particle esophageal stent. Methods: An elastic meshed esophageal stent made of double membranous nickel-titanium alloy and loaded with 188 Re-radioactive nanometre particles was used . The stent was introduced into the esophagus of eight experimental pigs and fixed in place. Two pigs served as controls. With the pig aneasthetized, the stent with good expandability was placed in the proper position. Radioactive MBq was applied to the 8 experiment pigs while the two control pigs received only the stent without the radioactive material. Three hours after the insertion of the stent, the pigs were allowed to feed, without any choking observed. Results: Seven days after the treatment of pathologic experiment pigs showed infla mmatory celluar infilfration, congestion and edema in the mucosa and submucous layer. After 21 days, some parts of the esophageal mucosa showed thickening of the vascular layer of the blood vessels and scanty fibrous hyperplasia. Seven days after application of larger dose of 259 MBq stent, pathology examination carried out in the experiment pigs showed extensive infla mmatory cellular infilfration, edema and congestion in the muscles and submucosa, and patch-like necrosis. Twenty-one days after application, repairing fibrous hyperplasia appeared. In the control pigs, not even any traumatic damage was observed. Periodic checking of the stool did not show any leakage of radioactivity and there was no displacement of the stents as confirmed by X-ray exam. Conclusions: The stent is effective to maintain an unobstructed passage of food . The loaded radioactive particles can be concentrated in the target area and adjusted by a body surface magnetic modulation and inhibit the intraluminal epithelial growth of esophageal mucosa without any severe radiation reaction or damage. It is quite promising to resolve the obstruction of advanced esophageal

  8. Technique of stowing packages containing radioactive materials during maritime transportation

    International Nuclear Information System (INIS)

    Ringot, G.; Chevalier, G.; Tomachevsky, E.; Draulans, J.; Lafontaine, I.

    1989-01-01

    The Mont Louis accident (August 25, 1984 - North Sea), in which uraniumhexafluoride packages were involved, alarmed a large number of European competent authorities, including the Commission of European Communities. The latter sponsored in 1986-1987 a bibliographic data collection to obtain a first view on the problem. (C.E.C contracts n degree 86-B-7015-11-004-17 and 86-B-7015-11-005-17). The collected data supply the necessary basis for further work, aiming to increase the safety of transporting radioactive material by ship. The study collected the different deceleration values, used by the transport companies and defined the accident conditions to be considered. This work can serve as a basis for later research to end with the proposal of a code of good practice for stowing. The research-work has been carried out jointly by C.E.A.-France, I.P.S.N. at Fontenay-aux-Roses and by Transnubel S.A. Brussels Belgium. The preliminary research included two main tasks: a statistical analysis, a bibliographic study of ship accidents

  9. Focus on radioactivity

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, M

    1989-01-01

    Written for children, this book looks at the nature of radioactive materials, how they were discovered, what they are used for and how they affect the environment around us. The emphasis is on the benefits of radioactive materials, particularly in nuclear power stations, in medical diagnostics and radiotherapy, in industry and in agriculture. Nuclear fission and fusion are explained, how radioactive materials are handled and naturally occurring radioactivity are included. (UK).

  10. Virtual goods recommendations in virtual worlds.

    Science.gov (United States)

    Chen, Kuan-Yu; Liao, Hsiu-Yu; Chen, Jyun-Hung; Liu, Duen-Ren

    2015-01-01

    Virtual worlds (VWs) are computer-simulated environments which allow users to create their own virtual character as an avatar. With the rapidly growing user volume in VWs, platform providers launch virtual goods in haste and stampede users to increase sales revenue. However, the rapidity of development incurs virtual unrelated items which will be difficult to remarket. It not only wastes virtual global companies' intelligence resources, but also makes it difficult for users to find suitable virtual goods fit for their virtual home in daily virtual life. In the VWs, users decorate their houses, visit others' homes, create families, host parties, and so forth. Users establish their social life circles through these activities. This research proposes a novel virtual goods recommendation method based on these social interactions. The contact strength and contact influence result from interactions with social neighbors and influence users' buying intention. Our research highlights the importance of social interactions in virtual goods recommendation. The experiment's data were retrieved from an online VW platform, and the results show that the proposed method, considering social interactions and social life circle, has better performance than existing recommendation methods.

  11. The future of very low level radioactive wastes in question

    International Nuclear Information System (INIS)

    Vignes, Emmanuelle

    2016-01-01

    After having recalled that nuclear plants produce various radioactive wastes, that the Cigeo project is the proposed solution to store these radioactive wastes, this article more particularly addresses the issue of very low level radioactive wastes which are now the main matter of concern for the IRSN as their quantity is expected to increase during the years to come (notably in relationship with nuclear reactor lifetime extension), and as present storage capacities will soon be saturated. The author first outlines that these wastes are not very dangerous but very cumbersome. Among these so-defined 'very low level' wastes, 30 to 50 per cent could be considered as harmless, but are now processed as dangerous wastes through costly processes. Various possibilities are then envisaged such as a diversification of storage options

  12. A study on the safety of radioactive waste incineration facilities

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Y C [Yonsei Univ., Seoul (Korea, Republic of); Park, W J; Lee, B S; Lee, S H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    1994-12-15

    The main scope of the project is the selection of some considerable items in design criteria of radioactive waste incineration facilities not only for the protection of workers and residents during operation but also for the safe disposal of ashes after incineration. The technological and regulational status on incineration technologies in domestic and foreign is surveyed and analyzed for providing such basic items which must be contained in the guideline for safe and appropriate design, construction and operation of the facilities. The contents of the project are summarized as follows; surveying the status on incineration technologies for both radioactive and non-radioactive wastes in domestic and foreign, surveying and analysing same related technical standards and regulations in domestic and foreign, picking out main considerable items and proposing a direction of further research.

  13. Synthesis and characterization of scandium oxide microspheres for their application in radioactive particle tracking experiments

    International Nuclear Information System (INIS)

    Goswami, Sunil; Biswal, Jayashree; Pant, H.J.; Pillai, K.T.; Bamankar, Y.R.

    2012-01-01

    Radioactive particle tracking (RPT) technique, proposed by Lin et al., is a noble technique for understanding mixing mechanisms of fluids and; evaluation and improvement of design of multiphase flow systems. In RPT technique the motion of a single radioactive particle is tracked in a flow system using an array of strategically mounted NaI(Tl) scintillation detectors around the system. The gamma emitting radioactive tracer particle being tracked is designed to be hydrodynamically similar to that of the phase being traced

  14. Inter-generational Decision Making for Radioactive Waste Disposal, Policy and Science: Regulatory Protection Forever?

    International Nuclear Information System (INIS)

    Regnier, E.P.; Wallo, A.

    2006-01-01

    Assumptions about this generation's duty to future generations underlie decisions on regulatory requirements for disposal of radioactive waste. Regulatory provisions related to time of compliance, dose criteria, and institutional controls, for example, continue to be topics of discussion as regulations are revised or compared. Subjective and difficult ethical issues are either explicit or implicit in these discussions. The information and criteria used must be relevant and help make good decisions that, ideally, increase the overall welfare of future generations. To what extent can or should science usefully inform such decision-making? Both the National Academies of Science and the National Academy of Public Administration (NAPA) have reported on this topic, albeit from different viewpoints. This paper explains and expands upon the rationale used for setting compliance time periods such as the Department of Energy's requirement for a 1,000 year time of compliance with dose limits for low-level radioactive waste disposal facilities. It evaluates radioactive waste disposal against principles of equity recommended by NAPA. Radioactive waste disposal standards require evaluation of impacts much farther into the future than has been common for other endeavors with very long term effects. While performance assessment analyses provide much useful information, their inherent uncertainties over long time periods preclude the projection of reality. Thus, the usefulness of extremely long projections in supporting good decisions that promote the welfare of future generations is limited. Such decisions are fundamentally a question of resource allocation, equity, and fairness. (authors)

  15. Accelerated physical modelling of radioactive waste migration in soil

    International Nuclear Information System (INIS)

    Zimmie, T.F.; De, A.; Mahmud, M.B.

    1994-01-01

    A 100 g-tonne geotechnical centrifuge was used to study the long-term migration of a contaminant and radioactive tracer through a saturated soil medium. The use of the centrifuge simulates the acceleration of travel time in the prototype, which is N times larger than the model, by N 2 , where N is the desired g level. For a 5 h run at 60 g, the test modelled a migration time of about 2 years for a prototype 60 times larger than the small-scale model tested. Iodine 131, used as the tracer, was injected onto the surface of the soil, and was allowed to migrate with a constant head of water through the saturated soil. End window Geiger-Mueller (G-M) tubes were used to measure the count rate of the radioactive tracer flowing through the soil. The time from the peak response of one G-M tube to the other denotes the travel time between the two points in the flow domain. The results obtained using the radioactive tracer are in good agreement with the test performed on the same model setup using potassium permanganate as tracer and with numerical flow net modelling. Radioactive tracers can be useful in the study of nonradioactive contaminants as well, offering a nonintrusive (nondestructive) method of measuring contaminant migration. (author). 18 refs., 1 tab., 7 figs

  16. A review and synthesis of international proposals for the disposal of high-level radioactive wastes into crystalline rock formations

    International Nuclear Information System (INIS)

    1981-05-01

    Examination of the broad range of international concepts for the disposal of high-level radioactive wastes into crystalline rock formations has indicated that systems based upon solid waste units provide the greatest degree of engineering control and security. Three particular disposal concepts are considered worthy of detailed evaluation. In order of priority these are:-tunnel networks with 'in-floor' waste emplacement; matrix of vertical emplacement holes drilled from the surface; tunnel networks with 'in-room' waste emplacement. A review of the international literature has shown that at least ten countries have embarked upon study programmes, but only five have developed detailed conceptual design proposals. These are:- Canada, France, Sweden, the United Kingdom, and the United States. Differing economic, environmental, historical and political circumstances have influenced the pattern of international studies and, to the uninitiated, these factors may obscure some of the relevant technical considerations. Nevertheless, a broad technical concensus is apparent in that all countries currently favour tunnel networks with 'in-floor' waste emplacement. The subject is discussed in detail. (author)

  17. Expansion design for a Laboratory of Radioactive Sources Handling type II, class B

    International Nuclear Information System (INIS)

    Sanchez S, P. S.

    2014-01-01

    This work presents the expansion design of the Radioactive Wastes Research Laboratory (RWRL) installation authorized by the Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico) as type II class C, to manage 40 different radionuclides, approximately. The RWRL has 4 areas at the present time: a laboratory of instrumental analysis, one of radioactive material processes, other of counting and a chemical reagents stock, which is not integrated to the operation license of the RWRL. With the purpose of expanding the operation license of the RWRL to an installation type II class B, to manage until 370 MBq of high radio toxicity radionuclides, is presented in this work an expansion proposal of the RWRL. The expansion proposal is based in: (1) the Mexican Nuclear Standard NOM-027-Nucl-1996 for installations type II class B, (2) the current distribution of water, light, electricity, extraction, gas, air and vacuum services of RWRL, and (3) the available areas inside the building that the RWRL occupies. The proposal contemplates the creation of additional new areas for RWRL: 3 laboratories, 2 dressing rooms, 2 bathrooms and 2 warehouses, one for radioactive materials and another for reagents chemical radiologically inactive. Architectural, electric, hydraulic, extraction and gas planes corresponding to the expansion of RWRL were realized. Inside the proposal the budget required to carry out the mentioned expansion is also presented. (Author)

  18. Environmental impact assessment of decommissioning treatment about radioactive model plant waste ore storage site

    International Nuclear Information System (INIS)

    Bei Xinyu

    2012-01-01

    Aiming at decommissioning treatment project of radioactive model plant waste ore storage site, based on the detailed investigations of source terms and project description, systematic environmental impacts have been identified. The environmental impacts both during decommissioning treatment, radioactive waste transportation and after treatment are assessed. Some specific environmental protection measures are proposed so as to minimize the adverse environmental impacts. (author)

  19. Status and prospects of radioactive waste management in France

    International Nuclear Information System (INIS)

    Gonnot, F.M.

    2012-01-01

    The chairman of ANDRA (French agency for the management of radioactive waste) presents the activities of the agency in the framework of the 2006 Planning Act that took in principle the decision to dispose of the high-level and the long-lived radioactive waste in a geological repository (Cigeo project). One of the important aspects of the Cigeo project is the requirement by law, to study the reversibility and therefore to demonstrate the capability to retrieve already disposed waste packages. In March 2010 the Government accepted the 30 km 2 area proposed by ANDRA for the location of the future repository. At present, ANDRA teams are fully busy on 2 fronts: first in preparing the license application for Cigeo to be submitted in 2015, and secondly in preparing the industrial phase of the Cigeo project. Low-level and intermediate-level radioactive waste are disposed of in surface facilities. (A.C.)

  20. Volume reduction and solidification of radioactive waste incineration ash with waste glass

    International Nuclear Information System (INIS)

    Koyama, Hidemi; Kobayashi, Masayuki

    2007-01-01

    The low-level radioactive waste generated from research institutions and hospitals etc. is packed into a container and is kept. The volume reduced state or the unprocessed state by incineration or compression processing are used because neither landfill sites nor disposal methods have been fixed. Especially, because the bulk density is low, and it is easy to disperse, the low-level radioactive waste incineration ash incinerated for the volume reduction is a big issue in security, safety, stability in the inventory location. A safe and appropriate disposal processing method is desired. When the low temperature sintering method in the use of the glass bottle cullet was examined, volume reduction and stabilization of low-level radioactive waste incineration ash were verified. The proposed method is useful for the easy treatment of the low-level radioactive waste incineration ash. (author)

  1. Enhanced removal of radioactive particles by fluorocarbon surfactant solutions

    International Nuclear Information System (INIS)

    Kaiser, R.; Harling, O.K.

    1993-08-01

    The proposed research addressed the application of ESI's particle removal process to the non-destructive decontamination of nuclear equipment. The cleaning medium used in this process is a solution of a high molecular weight fluorocarbon surfactant in an inert perfluorinated liquid which results in enhanced particle removal. The perfluorinated liquids of interest, which are recycled in the process, are nontoxic, nonflammable, and environmentally compatible, and do not present a hazard to the ozone layer. The information obtained in the Phase 1 program indicated that the proposed ESI process is technically effective and economically attractive. The fluorocarbon surfactant solutions used as working media in the ESI process survived exposure of up to 10 Mrad doses of gamma rays, and are considered sufficiently radiation resistant for the proposed process. Ultrasonic cleaning in perfluorinated surfactant solutions was found to be an effective method of removing radioactive iron (Fe 59) oxide particles from contaminated test pieces. Radioactive particles suspended in the process liquids could be quantitatively removed by filtration through a 0.1 um membrane filter. Projected economics indicate a pre-tax pay back time of 1 month for a commercial scale system

  2. The induced radioactivity danger parameter for gamma radiation

    International Nuclear Information System (INIS)

    Perry, D.R.

    1985-07-01

    Dosimetric and practical aspects of the induced radioactivity danger parameter, as used for calculating the gamma radiation dose rate near to objects that have been exposed to high energy radiation, are examined. A simplified and more generally applicable method of calculation is proposed, based on energy balance in homogeneous media. The problems of applying this in practice are discussed, and it is shown that corrections are generally small enough to be neglected in many practical applications. Examples of calculations by previous and proposed methods are given. (author)

  3. Radioactive waste management solutions

    International Nuclear Information System (INIS)

    Siemann, Michael

    2015-01-01

    One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

  4. Considerations about radioactive events and their psycho social effects; Consideracoes sobre eventos radioativos e seus efeitos psicossociais

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Laercia Abreu [Brasilia Univ., DF (Brazil). Inst. de Psicologia. Dept. de Processos Psicologicos Basicos

    1995-09-01

    This study presents some behavioral patterns which are observed in the context of a radioactive accident. Comparing three different situations involving radioactive elements, Three Mile Island (USA), Chernobyl (ISC) and Goiania (Brazil), it is observed that, despite the differences in radiological levels, the populations involved show similar response characteristics. The impact of the radioactive events on health has been the main concern of the exposed population, and the response patterns observed in the different radioactive events seem to be less variable than it was proposed in the first studies. (author) 29 refs.

  5. Development of closure criteria for inactive radioactive waste disposal sites at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1989-01-01

    The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, specifies that cleanup of inactive waste disposal sites at Department of Energy (DOE) facilities shall at least attain legally applicable or relevant and appropriate requirements (ARARs) for cleanup or control of environmental contamination. This paper discusses potential ARARs for cleanup of inactive radioactive waste disposal sites and proposes a set of closure criteria for such sites at Oak Ridge National Laboratory (ORNL). The most important potential ARARs include Federal standards for radiation protection of the public, radioactivity in drinking water, and near-surface land disposal of radioactive wastes. On the basis of these standards, we propose that cleanup and closure of inactive radioactive waste disposal sites at ORNL shall achieve (1) limits on annual effective dose equivalent for off-site individuals and inadvertent intruders that conform to the DOE's performance objectives for new low-level waste disposal facilities and (2) to the extent reasonably achievable, limits on radionuclide concentrations in ground water and surface waters in accordance with Federal drinking water standards and ground-water protection requirements

  6. 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.

  7. [Nationwide survey on radioactive waste management related to positron emission tomography in Japan].

    Science.gov (United States)

    Nagaoka, Hiroaki; Watanabe, Hiroshi; Yamaguchi, Ichiro; Fujibuchi, Toshioh; Kida, Tetsuo; Tanaka, Shinji

    2009-12-20

    A clearance system for medical radioactive solid waste has not yet been implemented in Japan. Since 2004 new regulations have allowed institutions using positron emission tomography(PET)to handle totally decayed radioactive waste as non-radioactive waste after decay-in-storage. It was expected that this new regulation would mediate the installation of clearance systems in Japan. In order to assess the current situation of radiation safety management in PET institutions, we conducted a nationwide survey. The study design was a cross-sectional descriptive study conducted by questionnaire. The subjects of this survey were all the PET institutions in Japan. Among 224 institutes, 128 institutes are equipped with cyclotrons and 96 institutes are not. The number of returned questionnaires was 138. Among institutes that are using delivered radiopharmaceuticals, 80% treat their waste as non-radioactive according to the new regulation. The impact of new regulations for reducing radioactive waste in PET institutes without a cyclotron was estimated at about $400 thousand per year. The main concern of medical institutes was assessment of the contamination caused by by-products of radioactive nuclides generated in target water during the operation of a cyclotron. It was thought that a rational rule based on scientific risk management should be established because these by-products of radioactive nuclides are negligible for radiation safety. New regulation has had a good influence on medical PET institutes, and it is expected that a clearance system for medical radioactive waste will be introduced in the near future, following these recent experiences in PET institutes.

  8. Results from an official inspection on the transportation of radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Wilhelm, Thomas [TUEV SUED Energietechnik GmbH, Filderstadt (Germany); Kosbadt, Oliver [Ministerium fuer Umwelt, Naturschutz und Verkehr Baden-Wuerttemberg, Stuttgart (Germany)

    2011-07-01

    The German legislation for dangerous goods includes general regulations as well as specific requirements for the real transport processes. Thus an enterprise which is involved in the transportation of dangerous goods has to appoint at least one safety adviser (SA) for the transport of dangerous goods. This is included in Segment 1.8.3 of the European arrangement concerning the international carriage of dangerous goods by road (ADR) as well as in paragraph 1 of the 'Verordnung ueber die Bestellung von Gefahrgutbeauftragten und die Schulung der beauftragten Personen in Unternehmen und Betrieben (Gefahrgutbeauftragtenverordnung, GbV)' (ordinance concerning the safety adviser for the transport of dangerous goods). After 1.7.2 ADR the transportation of radioactive materials is to be subjected to a radiation protection program (RPP). After 1.7.3 ADR quality assurance programs (QAP) are to be established and implemented for all aspects of transportation. (orig.)

  9. Results from an official inspection on the transportation of radioactive material

    International Nuclear Information System (INIS)

    Wilhelm, Thomas; Kosbadt, Oliver

    2011-01-01

    The German legislation for dangerous goods includes general regulations as well as specific requirements for the real transport processes. Thus an enterprise which is involved in the transportation of dangerous goods has to appoint at least one safety adviser (SA) for the transport of dangerous goods. This is included in Segment 1.8.3 of the European arrangement concerning the international carriage of dangerous goods by road (ADR) as well as in paragraph 1 of the 'Verordnung ueber die Bestellung von Gefahrgutbeauftragten und die Schulung der beauftragten Personen in Unternehmen und Betrieben (Gefahrgutbeauftragtenverordnung, GbV)' (ordinance concerning the safety adviser for the transport of dangerous goods). After 1.7.2 ADR the transportation of radioactive materials is to be subjected to a radiation protection program (RPP). After 1.7.3 ADR quality assurance programs (QAP) are to be established and implemented for all aspects of transportation. (orig.)

  10. Radioactive waste management

    International Nuclear Information System (INIS)

    Balek, V.

    1994-01-01

    This booklet is a publication by International Atomic Energy Agency for general awareness of citizens and policy-makers to clarify their concept of nuclear wastes. In a very simple way it tells what is radioactivity, radiations and radioactive wastes. It further hints on various medial and industrial uses of radiations. It discusses about different types of radioactive wastes and radioactive waste management. Status of nuclear power plants in Central and Eastern European countries are also discussed

  11. Radioactive contamination level of vehicles resulted from transporting fine rare-earth minerals by rail

    International Nuclear Information System (INIS)

    Han Kaichun; Yu Boyong; Gao Shengwei

    1997-01-01

    This paper presents monitoring results of radioactive contamination level of steel open wagon surface resulted from transporting fine rare-earth minerals. Under promising transport conditions (the packaging consists of two layers of plastic bags and two layers of plastic net sacks, each package contains 50 kg of minerals, each vehicle carries 60 t), the surface radioactivity (total α and total β) of 16 vehicles on two lines from Baotou to Wujiachuan (924 km) and from Baotou to Sankeshu (2236 km) was measured before loading, after unloading and washing, using α and β surface contamination detector. The results showed that the radioactive contamination level of the vehicle surface after unloading appeared significantly different. The contamination level of vehicle bases was higher than that of both sides, long distance vehicles was higher than that of short distance vehicles. The radioactive contamination level of vehicles surface after washing was below the standard limits, these vehicles can be used for ordinary goods transport

  12. Gallium-67 activated charcoal: a new method for preparation of radioactive capsules for colonic transit study

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, Kai-Yuan [Department of Radiological Technology, ChungTai Institute of Health Sciences and Technology, Taichung (Taiwan); Tsai, Shih-Chuan [Department of Nuclear Medicine, Show Chwan Memorial Hospital, Changhua (Taiwan); Lin, Wan-Yu. [Department of Nuclear Medicine, Taichung Veterans General Hospital, 160 Taichung Harbor Road, Section 3, 40705, Taichung (Taiwan)

    2003-06-01

    Indium-111 is currently the radionuclide of choice for colonic transit study. However, it is expensive and not available in many hospitals. Technetium-99m has been proposed for colonic transit study but the short half-life has limited its use. Gallium-67 citrate is inexpensive and available in most countries. Most importantly, it has a suitable half-life for colonic transit study. Attempts have been made in some studies to use {sup 67}Ga citrate to label activated charcoal, but the results have not been good because of poor stability. In this study, we successfully labelled activated charcoal with {sup 67}Ga citrate by adding alcohol and 5% glucose solution. To evaluate the in vitro stability, the {sup 67}Ga-activated charcoal was incubated in a milieu mimicking the intestinal content, containing lipase, trypsin and glycochenodeoxycholate at different pH values (6.0, 7.0, 7.4 and 8.0) and for different durations (0 h, 24 h, 48 h, 72 h and 96 h). For the in vivo study, the {sup 67}Ga-activated charcoal was loaded into a commercial empty enteric capsule. Colonic transit scintigraphy was performed in five volunteers, including three healthy people and two constipated patients, after intake of the radioactive capsule. Images were obtained at 2 h, 4 h, 6 h, 8 h, 24h, 48 h, 72 h etc. until no radioactivity was detected in the bowel. Our data show that the in vitro stability of {sup 67}Ga-activated charcoal was good. The labelling efficiency still exceeded 91% at 96 h at pH values of 6.0, 7.0 and 7.4. In the group with a pH value of 8.0, the labelling efficiency gradually fell during the 4-day incubation but was still higher than 88% at the end of the fourth day. In the in vivo study, most capsules disintegrated in the caecum/colon region, and the {sup 67}Ga-activated charcoal mixed very well with bowel content. In addition, the radioactive charcoal could be detected clearly on the 72-h image, which is very important for the evaluation of colonic transit time in patients

  13. Safety and security in transportation of radioactive material- the perception of risk

    Energy Technology Data Exchange (ETDEWEB)

    Ericsson, A.M.; Jaernry, C. [AMC Konsult AB, Bromma (Sweden)

    2004-07-01

    Since the event of September 11, 2001, the way most people look at transportation risk has changed. There is now a lot more focusing on the security concerns related to the transportation of radioactive material. Most people are now more concerned about the risk of terrorist actions or sabotage than of accidents. This is probably due to the fact that the safety record for transportation of radioactive material has so far been very good and that most people experience terrorism and sabotage more scaring and less controllable than general accidents. This paper will compare the safety and the security regulations and discuss synergies and contradictions between the sets of regulations.

  14. Safety and security in transportation of radioactive material- the perception of risk

    International Nuclear Information System (INIS)

    Ericsson, A.M.; Jaernry, C.

    2004-01-01

    Since the event of September 11, 2001, the way most people look at transportation risk has changed. There is now a lot more focusing on the security concerns related to the transportation of radioactive material. Most people are now more concerned about the risk of terrorist actions or sabotage than of accidents. This is probably due to the fact that the safety record for transportation of radioactive material has so far been very good and that most people experience terrorism and sabotage more scaring and less controllable than general accidents. This paper will compare the safety and the security regulations and discuss synergies and contradictions between the sets of regulations

  15. ANDRA - National Radioactive Waste Management Agency. Activity report 2015. Financial report 2015

    International Nuclear Information System (INIS)

    2016-01-01

    Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2015

  16. ANDRA - National Radioactive Waste Management Agency. Activity report 2016. Financial report 2016

    International Nuclear Information System (INIS)

    2017-01-01

    Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2016

  17. Environmental Assessment Radioactive Source Recovery Program

    International Nuclear Information System (INIS)

    1995-01-01

    In a response to potential risks to public health and safety, the U.S. Department of Energy (DOE) is evaluating the recovery of sealed neutron sources under the Radioactive Source Recovery Program (RSRP). This proposed program would enhance the DOE's and the U.S. Nuclear Regulatory Commission's (NRC's) joint capabilities in the safe management of commercially held radioactive source materials. Currently there are no federal or commercial options for the recovery, storage, or disposal of sealed neutron sources. This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the DOE were to implement a program for the receipt and recovery at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico, of unwanted and excess plutonium-beryllium ( 238 Pu-Be) and americium-beryllium ( 241 Am-Be) sealed neutron sources. About 1 kg (2.2 lb) plutonium and 3 kg (6.6 lb) americium would be recovered over a 15-year project. Personnel at LANL would receive neutron sources from companies, universities, source brokers, and government agencies across the country. These neutron sources would be temporarily stored in floor holes at the CMR Hot Cell Facility. Recovery reduces the neutron emissions from the source material and refers to a process by which: (1) the stainless steel cladding is removed from the neutron source material, (2) the mixture of the radioactive material (Pu-238 or Am-241) and beryllium that constitutes the neutron source material is chemically separated (recovered), and (3) the recovered Pu-238 or Am-241 is converted to an oxide form ( 238 PuO 2 or 241 AmO 2 ). The proposed action would include placing the 238 PuO 2 or 241 AmO 2 in interim storage in a special nuclear material vault at the LANL Plutonium Facility

  18. Organizing and managing radioactive waste disposal as an experiment

    International Nuclear Information System (INIS)

    Cook, B.J.; Emel, J.L.; Kasperson, R.E.

    1990-01-01

    This paper examines organization and management issues engendered by the national program for permanent disposal of commercial radioactive wastes. The description of current organizational and managerial responses to the waste disposal problem serves as a springboard for consideration of the technical, political, and organizational constraints that impinge upon the waste-management effort. Taking these constraints into account, the authors apply ideas that have emerged from previous radioactive waste-management studies and research on organizations, concluding that a change of course is needed. As an alternative, they propose an experimental approach predicated on the waste-management organization's acknowledging uncertainty and constructing responses that seek to reduce uncertainty systematically and without distortion

  19. The French Experience Regarding Peer Reviews to Improve the Safety and Security of Radioactive Sources

    International Nuclear Information System (INIS)

    Lachaume, J.-L.; Bélot, G.

    2015-01-01

    France has a 50 year history of control over radioactive sources. Convinced that peer reviews may be helpful to improve any regulatory system, France decided to experience a ‘full scope’ Integrated Regulatory Review Service mission in 2006 and its follow-up mission in 2009, including a review of the implementation of the Code of Conduct. The reviews, interviews and observations performed during these missions enabled the experts to have a thorough knowledge of the French system and to highlight its strengths and ways for improvements. Following these reviews, France decided to rely on its good practices, extend them as much as possible and to define, implement and address an action plan to improve its regulatory control over radioactive sources, while maintaining the prime responsibility on the operators. While good practices in the tracking of sources were maintained and slight evolutions were conducted in the safety regulations, licensing process, and inspection and enforcement actions, the major outcome of these reviews will obviously consist of the entrustment of the French Nuclear Safety Authority with the role of the regulatory authority for the security of radioactive sources and the implementation of dedicated provisions. (author)

  20. International guidance on the establishment of quality assurance programmes for radioactivity measurement in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, B.E. [Dosimetry and Medical Radiation Physics Section, Division of Human Health, International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 200, A-1400 Vienna (Austria)]. E-mail: b.zimmerman@iaea.org; Herbst, C. [Department of Medical Physics, University of the Free State, Geneeskundige Fisika G 68, Bloemfontein 9300 (South Africa); Norenberg, J.P. [College of Pharmacy, 2502 Marble, NE MSC09 5360, University of New Mexico, Albuquerque 87131 (United States); Woods, M.J. [Ionizing Radiation Consultants, Ltd., 152 Broom Road, Teddington, Middlesex TW11 9PQ (United Kingdom)

    2006-10-15

    A new guidance document for the implementation of quality assurance (QA) programmes for nuclear medicine radioactivity measurement, produced by the International Atomic Energy Agency, is described. The proposed programme is based on the principles of ISO 17025 and will enable laboratories, particularly in developing countries, to provide consistent, safe and effective radioactivity measurement services to the nuclear medicine community.

  1. International guidance on the establishment of quality assurance programmes for radioactivity measurement in nuclear medicine

    International Nuclear Information System (INIS)

    Zimmerman, B.E.; Herbst, C.; Norenberg, J.P.; Woods, M.J.

    2006-01-01

    A new guidance document for the implementation of quality assurance (QA) programmes for nuclear medicine radioactivity measurement, produced by the International Atomic Energy Agency, is described. The proposed programme is based on the principles of ISO 17025 and will enable laboratories, particularly in developing countries, to provide consistent, safe and effective radioactivity measurement services to the nuclear medicine community

  2. Activities and Issues in Monitoring Scrap Metal Against Radioactive Sources

    Energy Technology Data Exchange (ETDEWEB)

    Chen, S.Y., E-mail: sychen@anl.gov [Argonne National Laboratory, Argonne, IL (United States)

    2011-07-15

    Over the past few decades, the global scrap metal industry has grown increasingly vigilant regarding radioactive contamination. Accidental melts of radioactive sources in some smelting facilities, in particular, have caused considerable damage and required recovery efforts costing tens of millions of dollars. In response, the industry has developed and deployed countermeasures. Increasingly expensive and sophisticated radiation monitoring devices have been implemented at key scrap entry points - ports and scrapyards. Recognition of the importance of such endeavors has led to a series of activities aimed at establishing organized and coordinated efforts among the interested parties. Recent concerns over the potential use of radioactive sources for radiological devices in terrorist acts have substantially heightened the need for national and international authorities to further control, intercept, and secure the sources that have escaped the regulatory domain. Enhanced collaboration by the government and industry could substantially improve the effectiveness of efforts at control; the 'Spanish Protocol' as developed by the Spanish metal industry and government regulators is a good example of such collaboration. (author)

  3. A utility perspective on the proposed Northeast interstate compact

    International Nuclear Information System (INIS)

    Keating, W.R.

    1984-01-01

    The proposed Northeast Compact on Low-Level Radioactive Waste appears to be stalled in its present form. The Low-Level Waste Policy Act of 1980 encourages states to enter into regional waste compacts where practicable. The Northeast Region, which includes eleven states made up of the six New England states plus New York, New Jersey, Pennsylvania, Delaware, and Maryland, is the largest proposed compact region from the standpoint of low-level radioactive waste volumes. There is also wide variation in volumes among the states. Four states in the region have ratified the Northeast Compact, but the remaining seven states, including the three largest generating states, have not ratified to date. The large states are pivotal in determining whether the compact will move forward. The prime concerns of these large volume generating states appear to be host state selection and responsibility issues, as well as some of the proposed powers and authority of the Regional Commission

  4. Too hot to handle. Social and policy issues in the management of radioactive wastes

    International Nuclear Information System (INIS)

    Walker, C.A.; Gould, L.C.; Woodhouse, E.J.

    1983-01-01

    Information about the management of radioactive wastes is provided in this book. Specifically, the book attempts to supply information to further the understanding of the history of radioactive waste management in this country and the role of nuclear energy in the future of the US; the science and technology of the processes that produce radioactive wastes and of the methods proposed for managing them; the biological effects of radiation; the public attitudes about nuclear power; the nature of risks resulting from technological developments and ways of managing them; and the political institutions and processes that govern radioactive waste management. The authors have attempted to present an objective view of nuclear waste management taking a stand neither for nor against nuclear power but placing special emphasis on radioactive waste management rather than nuclear power, because they feel that the latter aspect of the subject has received much more extensive coverage elsewhere. The contents of the book are divided into 7 chapters entitled: The Radioactive Waste Management Problem, Science and Technology of the Sources and Management of Radioactive Wastes, Nuclear Waste Management and Risks to Human Health, Public Attitudes toward Radioactive Wastes, How Safe Is Safe Enough; Determinants of Perceived and Acceptable Risk, The Politics of Nuclear Waste Management, and Value Issues in Radioactive Waste Management

  5. Radioactive consumer products

    International Nuclear Information System (INIS)

    Sato, Otomaru

    1981-01-01

    Present situation of utilizing the radioactive consumer products and exposure dose were reviewed with published data. Practically, consumer products are divided into three categories, (1) radioactive nuclides intentionally incorporated into radioluminous dye, ionization chambers for smoke detector, eliminator of static electricity, and glow lamp (2) natural radioactive nuclides contained in false teeth, porcelain, glass, and gas mantle (3) natural radioactive nuclides accumulated as industrial waste at the consumption of coal, petroleum, and natural gas or in fertilizer and materials for construction. (Nakanishi, T.)

  6. Scientific capabilities of the advanced light source for radioactive materials

    International Nuclear Information System (INIS)

    Shuh, D.K.

    2007-01-01

    The Advanced Light Source (ALS) of Lawrence Berkeley National Laboratory (LBNL) is a third-generation synchrotron radiation light source and is a U.S. Department of Energy (DOE) national user facility. Currently, the ALS has approximately forty-five operational beamlines spanning a spectrum of scientific disciplines, and provides scientific opportunities for more than 2 000 users a year. Access to the resources of the ALS is through a competitive proposal mechanism within the general user program. Several ALS beamlines are currently being employed for a range of radioactive materials investigations. These experiments are reviewed individually relying on a graded hazard approach implemented by the ALS in conjunction with the LBNL Environmental, Health, and Safety (EH and S) Radiation Protection Program. The ALS provides radiological work authorization and radiological control technician support and assistance for accepted user experimental programs. LBNL has several radioactive laboratory facilities located near the ALS that provide support for ALS users performing experiments with radioactive materials. The capabilities of the ALS beamlines for investigating radioactive materials are given and examples of several past studies are summarised. (author)

  7. The pioneers of radioactivity. From the Museum to the College de France

    International Nuclear Information System (INIS)

    1998-01-01

    This educative guidebook is built like a touristic itinerary threw Paris (France) which follows the footpaths of the French pioneers of radioactivity from the Museum, dominated by the 'Becquerel dynasty', to the College de France. This scientific route is a good way to familiarize oneself with science and its actors. (J.S.)

  8. Radioactivity and food

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1990-01-01

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

  9. Low-level Radioactive waste Management

    International Nuclear Information System (INIS)

    1991-01-01

    This meeting describes low-level radioactive waste management problems and contains 8 papers: 1 Low-level radioactive waste management: exemption concept and criteria used by international organizations. 2 Low-level radioactive waste management: french and foreign regulations 3 Low-level radioactive waste management in EDF nuclear power plants (FRANCE) 4 Low-level radioactive waste management in COGEMA (FRANCE) 5 Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE) 6 Low-level radioactive waste management in hospitals 7 Low-level radioactive waste disposal: radiation protection laws 8 Methods of low-level radioactive materials measurements during reactor dismantling or nuclear facilities demolition (FRANCE)

  10. Radiological observation: 'remanence of radioactivity of artificial origin'. Mission report 2016

    International Nuclear Information System (INIS)

    Aubry, S.; Boulet, B.; Cagnat, X.; Cossonnet, C.; Mekhlouche, D.; Thomas, S.; Vivien, C.; Chevreuil, M.; Malfait, V.; Manach, E.; Claval, D.; Mourier, D.; Pourcelot, L.; Salaun, G.; Metivier, J.M.

    2016-04-01

    Thirty years after the Chernobyl accident, some areas in France, mainly mountain areas, display radioactivity levels higher or even much higher than those noticed in other areas, even at the vicinity of nuclear plants. These areas are called 'areas of remanence of artificial radioactivity'. After having recalled this observation based on radiological measurements, and an overview of an atmospheric deposition of artificial radioactivity (nuclear tests, Chernobyl accident, satellite falls, Fukushima accident), this report describes the adopted strategy (sampling and measurements) to assess and study this phenomenon. It analyses the obtained results in terms of remanence in the continental water environment and in soils, fields and forests. It also proposes a synthesis of previously acquired results. Appendices present methods used for sampling and sample processing, a list of samples, data related to mass activity of artificial radioactivity in soils, inventories of artificial radioactivity in soils, and methods for the calculation of efficient doses

  11. Report of safety of the characterizing system of radioactive waste; Informe de seguridad del sistema caracterizador de desechos radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Angeles C, A; Jimenez D, J; Reyes L, J [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1998-09-15

    Report of safety of the system of radioactive waste of the ININ: Installation, participant personnel, selection of the place, description of the installation, equipment. Proposed activities: operations with radioactive material, calibration in energy, calibration in efficiency, types of waste. Maintenance: handling of radioactive waste, physical safety. Organization: radiological protection, armor-plating, personal dosemeter, risks and emergency plan, environmental impact, medical exams. (Author)

  12. Radioactive waste management policy in the UK of best practicable environmental options for waste disposal and storage

    International Nuclear Information System (INIS)

    Johnson, P.D.; Feates, F.S.

    1986-01-01

    The organisations which produce radioactive waste carry the direct responsibility for safe and effective management of the wastes and for meeting the costs. UK Nirex Ltd., the Nuclear Industry Radioactive Waste Executive, has been set up to develop and operate new disposal facilities. Individual producers of radioactive waste undertake research related to the treatment of their own wastes, and UK Nirex Ltd. commissions research related to the disposal facilities it wishes to develop. Whatever new disposal facilities are developed and used, UK Nirex Ltd. will have to show that any proposed facilities comply with the principles for assessment of proposals for the protection of the human environment issued by the Government Authorising Departments in 1984, and which incorporate basic radiological safety requirements

  13. United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management

    International Nuclear Information System (INIS)

    Stewart, L.

    2004-01-01

    The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas

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

    International Nuclear Information System (INIS)

    Pravdivyj, A.A.

    2003-01-01

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

  15. Investigation on supervising and monitoring of major radioactive pollution source

    International Nuclear Information System (INIS)

    Zeng Yibing; Zhang Zongrang; Men Meng; Zhang Peng

    2005-01-01

    Objective: In order to optimize the supervisory monitoring proposal of the major radioactive enterprises. Methods: The authors have worked out the public doses within the range of 0-1 km as well as 1-2 km through monitoring analysis of the radioactive pollutant enterprises on the samples of its surrounding air, water, soil and organism. Results: Generally the pollutant range of the enterprises runs from 0 to 1.5 km. Conclusion: Unnecessary working hours can be shortened as long as we keep the routine supervisory monitor of pollutant enterprises within the range of 2 km. (authors)

  16. Session 1984-85. Radioactive waste. Minutes of evidence, Monday 20 May 1985. Greenpeace

    International Nuclear Information System (INIS)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from Greenpeace on radioactive waste, including the following aspects: UK nuclear power programme; Government policies; origins and inventories of waste; fuel reprocessing plants; waste storage, processing and disposal; classification of active wastes; transport; functions of some organisations concerned with radioactive wastes in UK; relevant international law; ICRP safety standards; London Dumping Convention; dispersal of radioactive wastes from Windscale - radiological impacts; discussion of particular proposals for disposal sites; sea dumping; deep sub-seabed disposal. Representatives of Greenpeace were examined on the subject of the memorandum and the Minutes of Evidence are recorded. (U.K.)

  17. Preparation of the National Radioactive Waste and Spent Fuel Management Programme in Slovenia

    International Nuclear Information System (INIS)

    Kralj, M.; Zeleznik, N.; Mele, I.; Veselic, M.

    2006-01-01

    The first separate National Radioactive Waste and Spent Fuel Management Programme (National Programme) was prepared in Slovenia in 2005, as a separate part of the National Environmental Action Programme that was adopted in June 2005. In the previous National Environmental Action Programme from the year 1999, the radioactive waste and spent fuel management was mentioned only briefly in the paragraph on radiation and nuclear safety with two main objectives: to provide an effective management of radioactive waste, and to keep the environmental ionising radiation under control. The new National Programme from 2005 includes all topics being relevant for the management of the radioactive waste and spent fuel, from the legislation and identification of different waste streams in Slovenia, to the management of radioactive waste and spent fuel, the decommissioning of nuclear facilities and management of (TE)NORM. It deals also with the relevant actors in the radioactive waste management, communication and information activities, and the financial aspects of the radioactive waste and spent fuel management. The National Programme was already adopted by the Slovenian Government in October 2005 and will go to Parliament proceedings. The Technical bases for the National Programme was prepared by ARAO and presented to the government in the beginning of 2005. The frames for this document were taken from relevant strategic documents: the Programme of decommissioning the nuclear power plant Krsko and the radioactive waste and spent fuel management, prepared in 2004 by Slovenian and Croatian experts (ARAO and APO), the Proposal of LILW Management Strategy (1999), the Strategy of Spent Fuel Management (1996), and the Resolution on the National Energy Programme (2004). ARAO made a detailed study on the amount and types of radioactive waste produced in Slovenia and future arising with emphasis on the minimization on radioactive waste production. It considered all producers of LILW and

  18. An overview of U.S. plant performance improvement through effective radioactive waste management

    International Nuclear Information System (INIS)

    Sieberling, R.; Lyons, P.W.

    1986-01-01

    Radioactive waste volumes in the United States commercial nuclear power industry have declined over the last five years after increasing steadily in the late 1970's. This decline is considered to be especially significant because major backfits/modifications and major component repair/replacement at U.S. nuclear power stations have been accomplished during this period. This paper analyzes the key reasons for this performance and outlines the positive effects that this trend has upon overall nuclear plant performance. In reviewing plant performance data, there appears to be a direct correlation between overall plant performance and radioactive waste performance. For example, plants with high capacity factors, strong industrial safety programs, low collective man-rem, and good contamination controls, generally have a history of low radioactive waste volumes. The reasons for this excellent performance is the result of direct management and supervisory involvement in plant operations, implementation of high standards of performance, and monitoring performance against these standards. Using the techniques outlined in this paper, the U.S. nuclear power industry can continue to reduce the volume of low-level solid radioactive waste being generated

  19. An industry perspective on commercial radioactive waste disposal conditions and trends.

    Science.gov (United States)

    Romano, Stephen A

    2006-11-01

    The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

  20. Exclusion, Exemption and Clearance in the Frame of the Control and Management of Inadvertent Radioactive Material in Scrap Metal

    International Nuclear Information System (INIS)

    Gonzalez, Abel J.

    2011-01-01

    Radioactive substances are incorporated into materials, goods, merchandises, products and in scrap and, as scrap would recycle into new produce, the process of introduction of radioactive susbtanaces into commodities will continue. The situation is unstoppable and requires straightforward solutions. The problem is global and therefore the solution(s) should be global. A clear intergovernmental agreement is needed establishing to what extent commodities should be regulated