Methodological guide: management of industrial sites potentially contaminated by radioactive substances

International Nuclear Information System (INIS)

2001-01-01

At the request of the Ministries of Health and the Environment, IPSN is preparing and publishing the first version of the methodological guide devoted to managing industrial sites potentially contaminated by radioactive substances. This guide describes a procedure for defining and choosing strategies for rehabilitating such industrial sites. (author)

Frederick Soddy and the practical significance of radioactive matter

International Nuclear Information System (INIS)

Freedman, M.I.

1979-01-01

A short account is given of Soddy's interest in the practical significance of radioactive matter, illustrated by his work on mesothorium as a radium substitute and by his publications pointing out the possible exploitation of atomic energy in an industrial society. (U.K.)

Compliance assurance for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2009-01-01

The objectives of this Safety Guide are to assist competent authorities in the development and maintenance of compliance assurance programmes in connection with the transport of radioactive material, and to assist applicants, licensees and organizations in their interactions with competent authorities. In order to increase cooperation between competent authorities and to promote the uniform application of international regulations and recommendations, it is desirable to adopt a common approach to regulatory activities. This Safety Guide is intended to assist in accomplishing such a uniform application by recommending most of the actions for which competent authorities need to provide in their programmes for ensuring compliance with the Transport Regulations. This Safety Guide addresses radiation safety aspects of the transport of radioactive material; that is, the subjects that are covered by the Transport Regulations. Radioactive material may have other dangerous properties, however, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness; these properties are required to be taken into account in the regulatory control of the design and transport of packages. Physical protection and systems for accounting for and control of nuclear material are also discussed in this Safety Guide. These subjects are not within the scope of the Transport Regulations, but information on them is included here because they must be taken into account in the overall regulatory control of transport, especially when the regulatory framework is being established. Section 1 informs about the background, the objective, the scope and the structure of this publication. Section 2 provides recommendations on the responsibilities and functions of the competent authority. Section 3 provides information on the various national and international regulations and guides for the transport of radioactive material. Section 4 provides recommendations on carrying out

Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This Safety Guide provides guidance on the predisposal management of all types of radioactive waste (including spent nuclear fuel declared as waste and high level waste) generated at nuclear fuel cycle facilities. These waste management facilities may be located within larger facilities or may be separate, dedicated waste management facilities (including centralized waste management facilities). The Safety Guide covers all stages in the lifetime of these facilities, including their siting, design, construction, commissioning, operation, and shutdown and decommissioning. It covers all steps carried out in the management of radioactive waste following its generation up to (but not including) disposal, including its processing (pretreatment, treatment and conditioning). Radioactive waste generated both during normal operation and in accident conditions is considered

Original jurisdiction in matters relating to transport of radioactive substances

International Nuclear Information System (INIS)

Anon.

1989-01-01

Decisions on actions for avoidance of government supervision in matters of transport of radioactive substances are placed under the original jurisdiction of administrative courts. (Kassel Administrative Court, decision of 20 December 1988 - 8 A 699/88). (orig.) [de

Condensed matter physics with radioactive ion beams

International Nuclear Information System (INIS)

Haas, H.

1996-01-01

An overview of the present uses of radioactive ion beams from ISOLDE for condensed matter research is presented. As simple examples of such work, tracer studies of diffusion processes with radioisotopes and blocking/channeling measurements of emitted particles for lattice location are discussed. Especially the application of nuclear hyperfine interaction techniques such as PAC or Moessbauer spectroscopy has become a powerful tool to study local electronic and structural properties at impurities. Recently, interesting information on impurity properties in semiconductors has been obtained using all these methods. The extreme sensitivity of nuclear techniques makes them also well suited for investigations of surfaces, interfaces, and biomolecules. Some ideas for future uses of high energy radioactive ion beams beyond the scope of the present projects are outlined: the study of diffusion in highly immiscible systems by deep implantation, nuclear polarization with the tilted-foil technique, and transmutation doping of wide-bandgap semiconductors. (orig.)

Guide relative to the regulatory requirements applicable to the radioactive materials transport in airport area; Guide relatif aux exigences reglementaires applicables au transport des matieres radioactives en zone aeroportuaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-02-15

This guide makes an inventory of all the points necessary for the correct functioning of the transport of radioactive materials in airport zone. Stowage of the parcels, program of radiological protection (P.R.P.), operation of transport, quality assurance, radiation dose evaluation, radiation monitoring, dose optimization, storage management, are the principal points of this guide. (N.C.)

A users guide for the radioactive waste management code 'SIMULATION 2'

International Nuclear Information System (INIS)

Moore, D.; Tymons, B.J.

1984-09-01

This report is a users' guide to the radioactive waste management program SIMULATION. It gives a complete description of the calculational method used (with worked examples) a specification of the input data requirements, and samples of printout from the program. (author)

Security in the transport of radioactive material: Implementing guide. Spanish edition

International Nuclear Information System (INIS)

2013-01-01

This guide provides States with guidance in implementing, maintaining or enhancing a nuclear security regime to protect radioactive material (including nuclear material) in transport against theft, sabotage or other malicious acts that could, if successful, have unacceptable radiological consequences. From a security point of view, a threshold is defined for determining which packages or types of radioactive material need to be protected beyond prudent management practice. Minimizing the likelihood of theft or sabotage of radioactive material in transport is accomplished by a combination of measures to deter, detect, delay and respond to such acts. These measures are complemented by other measures to recover stolen material and to mitigate possible consequences, in order to further reduce the risks

Security in the Transport of Radioactive Material. Implementing Guide (French Edition)

International Nuclear Information System (INIS)

2012-01-01

This guide provides States with guidance in implementing, maintaining or enhancing a nuclear security regime to protect radioactive material (including nuclear material) in transport against theft, sabotage or other malicious acts that could, if successful, have unacceptable radiological consequences. From a security point of view, a threshold is defined for determining which packages or types of radioactive material need to be protected beyond prudent management practice. Minimizing the likelihood of theft or sabotage of radioactive material in transport is accomplished by a combination of measures to deter, detect, delay and respond to such acts. These measures are complemented by other measures to recover stolen material and to mitigate possible consequences, in order to further reduce the risks.

Security in the Transport of Radioactive Material. Implementing Guide (Chinese Edition)

International Nuclear Information System (INIS)

2012-01-01

This guide provides States with guidance in implementing, maintaining or enhancing a nuclear security regime to protect radioactive material (including nuclear material) in transport against theft, sabotage or other malicious acts that could, if successful, have unacceptable radiological consequences. From a security point of view, a threshold is defined for determining which packages or types of radioactive material need to be protected beyond prudent management practice. Minimizing the likelihood of theft or sabotage of radioactive material in transport is accomplished by a combination of measures to deter, detect, delay and respond to such acts. These measures are complemented by other measures to recover stolen material and to mitigate possible consequences, in order to further reduce the risks.

Standard guide for sampling radioactive tank waste

CERN Document Server

American Society for Testing and Materials. Philadelphia

2011-01-01

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Time-Averaged Adiabatic Potentials: Versatile Matter-Wave Guides and Atom Traps

International Nuclear Information System (INIS)

Lesanovsky, Igor; Klitzing, Wolf von

2007-01-01

We demonstrate a novel class of trapping potentials, time-averaged adiabatic potentials (TAAP), which allows the generation of a large variety of traps for quantum gases and matter-wave guides for atom interferometers. Examples include stacks of pancakes, rows of cigars, and multiple rings or sickles. The traps can be coupled through controllable tunneling barriers or merged altogether. We present analytical expressions for pancake-, cigar-, and ring-shaped traps. The ring geometry is of particular interest for guided matter-wave interferometry as it provides a perfectly smooth waveguide of widely tunable diameter and thus adjustable sensitivity of the interferometer. The flexibility of the TAAP would make possible the use of Bose-Einstein condensates as coherent matter waves in large-area atom interferometers

Applicant guide for the demands of expedition and agreement approval of the parcel or radioactive matter models for civil use transported on the public highway; Guide du requerant pour les demandes d'approbation d'expedition et d'agrement des modeles de colis ou de matieres radioactives a usage civil transportes sur la voie publique

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-03-15

This guide applies to the models of parcels or radioactive materials for which an approval of the competent authorities is required by the regulations of the dangerous goods transportations. It is about models used for: radioactive materials under special shape, lowly dispersible radioactive materials, packages containing 0.1 kg or more of uranium hexafluoride, any package containing fissile materials, the B(U) type packages, and the B(M) type packages; the C type packages. (N.C.)

77 FR 36017 - Regulatory Guide 7.3, Procedures for Picking Up and Receiving Packages of Radioactive Material

Science.gov (United States)

2012-06-15

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0139] Regulatory Guide 7.3, Procedures for Picking Up and... Guide (RG) 7.3, ``Procedures for Picking Up and Receiving Packages of Radioactive Material.'' The guide..., please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, or 301-415-4737...

Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Ed.). Safety Guide

International Nuclear Information System (INIS)

2014-01-01

This Safety Guide is issued in support of Regulations for the Safe Transport of Radioactive Material (IAEA Safety Standards Series No. TS-R-1, 2009 Edition). It lists the paragraph numbers of the Transport Regulations that are relevant for specified types of consignment, classified according to their UN numbers. It does not provide additional recommendations. The intended users are consignors and consignees, carriers, shippers, regulators, and end users involved in the transport of radioactive material. A person or organization intending to transport a particular type of consignment of radioactive material must meet requirements in all sections of the Transport Regulations. This Safety Guide aids users by providing a listing of the relevant requirements of the Transport Regulations for each type of radioactive material, package or shipment. Once a consignor has classified the radioactive material to be shipped, the appropriate UN number can be assigned and the paragraph numbers of the requirements that apply for the shipment can be found in the corresponding schedule

Guide relative to the regulatory requirements applicable to the radioactive materials transport in airport area

International Nuclear Information System (INIS)

2006-02-01

This guide makes an inventory of all the points necessary for the correct functioning of the transport of radioactive materials in airport zone. Stowage of the parcels, program of radiological protection (P.R.P.), operation of transport, quality assurance, radiation dose evaluation, radiation monitoring, dose optimization, storage management, are the principal points of this guide. (N.C.)

Ecological transport and radiation doses from ground water borne radioactive matters

International Nuclear Information System (INIS)

Bergman, R.; Bergstroem, U.; Evans, S.

1978-12-01

Turnover of radioactive matter entering the biosphere with ground water has been studied with regard to exposure and dose to critical groups and populations. The main alternatives considered for outflow of radioactive effluents to the biosphere are: outflow in a valley containing wells, outflow to a fresh-water lake, and outflow in a coastal region of the Baltic Sea. Mathematical models of a set of coupled ecosystems on local, regional- intermediate- and global levels have been used for calculations of doses. The intermediate system refers to the Baltic Sea. The mathematical analysis, based on first order kinetics for the exchange of matter in a system according to compartment principles, also includes products in decay chains, i.e. daughter nuclides generated by decay of nuclides under ecological cycling. The time dependent exposures have been studied for certain long-lived nuclides of radiological interest in waste from reprosessed fuel. Dose and dose commitment have been calculted for different release patterns comprising idealised episodes for outflow to the biosphere during short periods and outflow governed by constant leakage from a source on the border between geosphere and biosphere. (author)

Planning and preparing for emergency response to transport accidents involving radioactive material. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The objective of this Safety Guide is to provide guidance to the public authorities and others (including consignors, carriers and emergency response authorities) who are responsible for developing and establishing emergency arrangements for dealing effectively and safely with transport accidents involving radioactive material. It may assist those concerned with establishing the capability to respond to such transport emergencies. It provides guidance for those Member States whose involvement with radioactive material is just beginning. It also provides guidance for those Member States that have already developed their radioactive material industries and the attendant emergency plans but that may need to review and improve these plans

Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (D&D) from restricted use. This would be addressed in the decommissioning plan (E 1281). It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Fig. 1 shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as “candidate for release based on dose.” 1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects. 1.3 Surface contaminated objects are materials externally co...

Lowering the radioactivity of the photomultiplier tubes for the XENON1T dark matter experiment

Energy Technology Data Exchange (ETDEWEB)

Aprile, E.; Contreras, H.; Goetzke, L.W.; Fernandez, A.J.M.; Messina, M.; Plante, G.; Rizzo, A. [Columbia University, Physics Department, New York, NY (United States); Agostini, F. [INFN-Laboratori Nazionali del Gran Sasso (Italy); Gran Sasso Science Institute, L' Aquila (Italy); Bologna Univ., Department of Physics and Astrophysics, Bologna (Italy); INFN, Bologna (Italy); Alfonsi, M. [Nikhef and the University of Amsterdam, Amsterdam (Netherlands); Johannes Gutenberg-Universitaet Mainz, Institut fuer Physik and Exzellenzcluster PRISMA, Mainz (Germany); Arazi, L.; Budnik, R.; Duchovni, E.; Gross, E.; Itay, R.; Landsman, H.; Lellouch, D.; Levinson, L.; Priel, N.; Vitells, O. [Weizmann Institute of Science, Department of Particle Physics and Astrophysics, Rehovot (Israel); Arisaka, K.; Lyashenko, A.; Meng, Y.; Pantic, E.; Teymourian, A.; Wang, H. [University of California, Physics and Astronomy Department, Los Angeles, CA (United States); Arneodo, F.; Di Giovanni, A. [New York University Abu Dhabi, Abu Dhabi (United Arab Emirates); Auger, M.; Barrow, P.; Baudis, L.; Behrens, A.; Galloway, M.; Kessler, G.; Kish, A.; Mayani, D.; Pakarha, P.; Piastra, F. [University of Zurich, Physik-Institut, Zurich (Switzerland); Balan, C.; Cardoso, J.M.R.; Lopes, J.A.M.; Santos, J.M.F. dos [University of Coimbra, Department of Physics, Coimbra (Portugal); Bauermeister, B.; Fattori, S.; Geis, C.; Grignon, C.; Oberlack, U.; Schindler, S. [Johannes Gutenberg-Universitaet Mainz, Institut fuer Physik and Exzellenzcluster PRISMA, Mainz (Germany); Beltrame, P. [Weizmann Institute of Science, Department of Particle Physics and Astrophysics, Rehovot (Israel); University of Edinburgh, Edinburgh (United Kingdom); Brown, A.; Lang, R.F.; Macmullin, S.; Pienaar, J.; Reichard, S.; Reuter, C. [Purdue University, Department of Physics and Astronomy, West Lafayette, IN (United States); Brown, E.; Levy, C. [Rensselaer Polytechnic Institute, Department of Physics, Applied Physics and Astronomy, Troy, NY (United States); Wilhelms-Universitaet Muenster, Institut fuer Kernphysik, Muenster (Germany); Bruenner, S.; Hampel, W.; Kaether, F.; Lindemann, S.; Lindner, M.; Undagoitia, T.M.; Rauch, L.; Schreiner, J.; Simgen, H.; Weber, M. [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany); Bruno, G. [INFN-Laboratori Nazionali del Gran Sasso and Gran Sasso Science Institute, L' Aquila (Italy); Wilhelms-Universitaet Muenster, Institut fuer Kernphysik, Muenster (Germany); Buetikofer, L.; Coderre, D.; Schumann, M. [University of Bern, Albert Einstein Center for Fundamental Physics, Bern (Switzerland); Colijn, A.P.; Decowski, M.P.; Tiseni, A.; Tunnell, C. [Nikhef and the University of Amsterdam, Amsterdam (Netherlands); Cussonneau, J.P.; Le Calloch, M.; Masbou, J.; Lavina, L.S.; Thers, D. [Universite de Nantes, Subatech, Ecole des Mines de Nantes, CNRS/In2p3, Nantes (France); Ferella, A.D.; Fulgione, W.; Laubenstein, M. [INFN-Laboratori Nazionali del Gran Sasso and Gran Sasso Science Institute, L' Aquila (Italy); Fieguth, A.; Murra, M.; Rosendahl, S.; Weinheimer, C. [Wilhelms-Universitaet Muenster, Institut fuer Kernphysik, Muenster (Germany); Garbini, M.; Massoli, F.V.; Sartorelli, G.; Selvi, M. [Bologna Univ., Department of Physics and Astrophysics, Bologna (Italy); INFN, Bologna (Italy); Miguez, B.; Molinario, A.; Trinchero, G. [INFN-Torino and Osservatorio Astrofisico di Torino, Turin (Italy); Naganoma, J.; Shagin, P.; Wall, R. [Rice University, Department of Physics and Astronomy, Houston, TX (United States); Orrigo, S.E.A. [University of Coimbra, Department of Physics, Coimbra (Portugal); IFIC, CSIC-Universidad de Valencia, Valencia (Spain); Persiani, R. [Universite de Nantes, Subatech, Ecole des Mines de Nantes, CNRS/In2p3, Nantes (FR); Bologna Univ., Department of Physics and Astrophysics, Bologna (IT); INFN, Bologna (IT); Collaboration: XENON Collaboration

2015-11-15

The low-background, VUV-sensitive 3-inch diameter photomultiplier tube R11410 has been developed by Hamamatsu for dark matter direct detection experiments using liquid xenon as the target material. We present the results from the joint effort between the XENON collaboration and the Hamamatsu company to produce a highly radio-pure photosensor (version R11410-21) for the XENON1T dark matter experiment. After introducing the photosensor and its components, we show the methods and results of the radioactive contamination measurements of the individual materials employed in the photomultiplier production. We then discuss the adopted strategies to reduce the radioactivity of the various PMT versions. Finally, we detail the results from screening 286 tubes with ultra-low background germanium detectors, as well as their implications for the expected electronic and nuclear recoil background of the XENON1T experiment. (orig.)

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

International Nuclear Information System (INIS)

Nishiwaki, Y.

1981-01-01

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

Standard guide for characterization of radioactive and/or hazardous wastes for thermal treatment

CERN Document Server

American Society for Testing and Materials. Philadelphia

2003-01-01

1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations. The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate wa...

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide

International Nuclear Information System (INIS)

2014-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as … well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives.

Radioactive wastes and discharges

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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

Radioactive wastes and discharges

International Nuclear Information System (INIS)

2000-01-01

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

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

Guide relative to the modalities of statements and to the codification of criteria relative to the significant events involving the safety, the radiation protection or the environment applicable to the base nuclear installations and to the transport of radioactive matters; Guide relatif aux modalites de declaration et a la codification des criteres relatifs aux evenements significatifs impliquant la surete, la radioprotection ou l'environnement applicable aux installations nucleaires de base et au transport de matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

It is necessary to analyze the events detected on an installation in order to be sure that an already occurred event does not be repeated, by taking into account the appropriate remedial measures, to avoid a worsen situation could occur by analyzing the potential consequences of precursory events of more serious ones, to promote the correct practices to improve the safety. The present guide has for vocation to define the arrangements enforceable to nuclear operators about the statements modalities of such events when these ones concern the safety of nuclear facilities, transport of radioactive matters, radiation protection or environmental protection. In any case it can substitute to the specific obligations coming from the work code, public health code and environment code, licensing decrees about releases. (N.C.)

Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide recommendations to the regulatory body, focused on the operational aspects of radiation protection and radioactive waste management in nuclear power plants, and on how to ensure the fulfilment of the requirements established in the relevant Safety Requirements publications. It will also be useful for senior managers in licensee or contractor organizations who are responsible for establishing and managing programmes for radiation protection and for the management of radioactive waste. This Safety Guide gives general recommendations for the development of radiation protection programmes at nuclear power plants. The issues are then elaborated by defining the main elements of a radiation protection programme. Particular attention is paid to area classification, workplace monitoring and supervision, application of the principle of optimization of protection (also termed the 'as low as reasonably achievable' (ALARA) principle), and facilities and equipment. This Safety Guide covers all the safety related aspects of a programme for the management of radioactive waste at a nuclear power plant. Emphasis is placed on the minimization of waste in terms of both activity and volume. The various steps in predisposal waste management are covered, namely processing (pretreatment, treatment and conditioning), storage and transport. Releases of effluents, the application of authorized limits and reference levels are discussed, together with the main elements of an environmental monitoring programme

Radioactive Waste Management Basis

International Nuclear Information System (INIS)

Perkins, B.K.

2009-01-01

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education safety guide

CERN Document Server

2005-01-01

This Safety Guide provides recommendations and guidance on the > fulfilment of the safety requirements established in Safety Standards > Series No. WS-R-2, Predisposal Management of Radioactive Waste, > Including Decommissioning. It covers the roles and responsibilities of > different bodies involved in the predisposal management of radioactive > waste and in the handling and processing of radioactive material. It > is intended for organizations generating and handling radioactive > waste or handling such waste on a centralized basis for and the > regulatory body responsible for regulating such activities.  > Contents: 1. Introduction; 2. Protection of human health and the > environment; 3. Roles and responsibilities; 4. General safety > considerations; 5. Predisposal management of radioactive waste; 6. > Acceptance of radioactive waste in disposal facilities; 7. Record > keeping and reporting; 8. Management systems; Appendix I: Fault > schedule for safety assessment and environmental impact assessment; > Ap...

The management system for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The purpose of this Safety Guide is to provide information to organizations that are developing, implementing or assessing a management system for activities relating to the transport of radioactive material. Such activities include, but are not limited to, design, fabrication, inspection and testing, maintenance, transport and disposal of radioactive material packaging. This publication is intended to assist those establishing or improving a management system to integrate safety, health, environmental, security, quality and economic elements to ensure that safety is properly taken into account in all activities of the organization. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix: Graded approach for management systems for the safe transport of radioactive materials; Annex I: Two examples of management systems; Annex II: Examples of management system standards; Annex III: Example of a documented management system (or quality assurance programme) for an infrequent consignor; Annex IV: Example of a documented management system (or quality assurance programme) description for an infrequent carrier; Annex V: Example of a procedure for control of records; Annex VI: Example of a procedure for handling packages containing radioactive materials, including receipt and dispatch; Annex VII: Example of a packaging maintenance procedure in a complex organization; Annex VIII: Example of an internal audit procedure in a small organization; Annex IX: Example of a corrective and preventive action procedure

Management of Radioactive Waste from the Mining and Milling of Ores. Safety Guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations and guidance on the safe management of radioactive waste resulting from the mining and milling of ores, with the purpose of protecting workers, the public and the environment from the consequences of these activities. It supplements Safety Standards Series No. WS-R-1, Near Surface Disposal of Radioactive Waste. Contents: 1. Introduction; 2. Administrative, legal and regulatory framework; 3. Protection of human health and the environment; 4. Strategy for waste management; 5. Safety considerations in different phases of operations; 6. Safety assessment; 7. Quality assurance; 8. Monitoring and surveillance; 9. Institutional control for the post-closure phase.

Guide to the design, testing and use of packaging for the safe transport of radioactive materials

International Nuclear Information System (INIS)

1976-01-01

This guide gives to designers, manufacturers and users of packaging, advice supplementary to, or in amplification of, the recommendations made by the International Atomic Energy Agency for the safe transport of radioactive materials as given in IAEA Safety Series No. 6 (1973) and the advisory material given in IAEA Safety Series No. 37 (1973). This guide should be read and used in conjunction with these recommendations, the appropriate national regulations and any applicable regulations or requirements of the carriers concerned. (author)

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-09-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives.

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2014-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives

Management situation and prospect of radioactive waste

International Nuclear Information System (INIS)

Han, Pil Jun

1985-04-01

This book tell US that management situation and prospect of radioactive waste matter, which includes importance of energy, independence, limitation of fossil fuel energy, density of nuclear energy, strategy of supply of energy resource in Korea, nuclear energy development and radioactive waste matter, summary of management of radioactive waste, statistics of radioactive waste, disposal principle of radioactive waste, management on radioactive waste after using, disposal of Trench, La Marche in French, and Asse salt mine in Germany.

Best practice guide for radioactivity measurement laboratories in a post-accident situation

International Nuclear Information System (INIS)

2011-01-01

Published for laboratories likely to be asked to perform radioactivity measurements at the time of or after a radiological or nuclear accident in France or abroad, this guide aims at defining the best practices in terms of laboratory organisation (sample flow management, personnel radioprotection, sample identification and recording, sample cross-contamination risks, result transmission, archiving of data, results and samples, waste dismissal), and in terms of metrology (adaptation to needs in terms of detection limit and measurement uncertainty, preferred use of gamma spectrometry, analysis strategies)

Stepwise approach to decision making for long-term radioactive waste management. Experience, issues and guiding principles

International Nuclear Information System (INIS)

2004-01-01

Radioactive waste exists as a result of both past and current practices. One of the most challenging tasks is the management of long-lived waste that must be isolated from the human environment for many thousands, or even hundreds of thousands, of years. Although significant technical progress has been made in developing management schemes that, according to technical experts, would ensure long-term safety (e.g. engineered geologic disposal), the rate of progress towards implementing such solutions has been slower than expected. The contrast between expected and observed rates may be partly attributable to an earlier technical optimism. More significant, however, are the setbacks, which have arisen mainly from an underestimation of the societal and political dimensions. In long-term radioactive waste management, consideration is increasingly being given to concepts such as stepwise decision making and adaptive staging in which the public, and especially the local public, are to be meaningfully involved in the review and planning of developments. The key feature of these concepts is development by steps or stages that are reversible, within the limits of practicability. This is designed to provide reassurance that decisions can be reversed if experience shows them to have adverse or unwanted effects. A stepwise approach to decision making has thus come to the fore as being of value in advancing long-term radioactive waste management solutions in a societally acceptable manner. Despite its early identification within the radioactive waste management community as an important means for reaching solutions and decisions in which there is broad-based confidence, the bases for and application of stepwise decision making has not been widely reviewed. Guiding principles of any such process are still being formulated, its roots in empirical social science research have not been fully reviewed, nor the difficulties of its implementation analysed. The report reviews current

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Ed.). Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-06-15

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material (2012 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Standards Series No. TS-G-1.1 Rev. 1, which was issued in 2008.

Radioactive wastes and discharges

International Nuclear Information System (INIS)

1993-01-01

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

Methodological guide for the acceptance of waste with a natural radioactivity in the classified elimination facilities. Part 1: methodological guide

International Nuclear Information System (INIS)

Cazala, Ch.; Cessac, B.; Gay, D.

2006-01-01

This document is part of the thought implemented by the Direction of pollution prevention and risk (D.P.P.R.) from the Department of Ecology and Sustainable Development as part of a working group on means for detecting radioactivity at the entrance of waste storage centers (said gantries group). The D.P.P.R. has entrusted the implementation to the I.R.S.N.. The completion of the guide was conducted under the supervision of a steering committee composed of representatives of industrial producers of this control type, operators of storage centers, associations for environmental protection, experts and administration. The content and structure of the guide and the accompanying sheets result of discussions within the Steering Committee between D.P.P.R. and I.R.S.N.. (N.C.)

Radioactive Waste Management BasisApril 2006

Energy Technology Data Exchange (ETDEWEB)

Perkins, B K

2011-08-31

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

A guide to the suitability of elastomeric seal materials for use in radioactive material transport packages

International Nuclear Information System (INIS)

Vince, D.J.

2004-01-01

Elastomeric seals are a frequently favoured method of sealing Radioactive Material Transport (RMT) packages. The sealing technology has been proven for many years in a wide range of industrial applications. The requirements of the RMT package applications, however, are significantly different from those commonly found in other industries. This guide outlines the Regulatory performance requirements placed on an RMT package sealing system by TS-R-1, and then summarises the material, environment and geometry characteristics of elastomeric seals relevant to RMT applications. Tables in the guide list typical material properties for a range of elastomeric materials commonly used in RMT packages

Radioactive Waste Management BasisSept 2001

International Nuclear Information System (INIS)

Goodwin, S.S.

2011-01-01

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Emergency Response to Radioactive Material Transport Accidents

International Nuclear Information System (INIS)

EL-shinawy, R.M.K.

2009-01-01

Although transport regulations issued by IAEA is providing a high degree of safety during transport opertions,transport accidents involving packages containing radioactive material have occurred and will occur at any time. Whenever a transport accident involving radioactive material accurs, and many will pose no radiation safety problems, emergency respnose actioms are meeded to ensure that radiation safety is maintained. In case of transport accident that result in a significant relesae of radioactive material , loss of shielding or loss of criticality control , that consequences should be controlled or mitigated by proper emergency response actions safety guide, Emergency Response Plamming and Prepardness for transport accidents involving radioactive material, was published by IAEA. This guide reflected all requirememts of IAEA, regulations for safe transport of radioactive material this guide provide guidance to the publicauthorites and other interested organziation who are responsible for establishing such emergency arrangements

User's guide for shipping Type B quantities of radioactive and fissile material, including plutonium, in DOT-6M specification packaging configurations

International Nuclear Information System (INIS)

Kelly, D.L.

1994-09-01

The need for developing a user's guide for shipping Type B quantities of radioactive and fissile material, including plutonium, in a US Department of Transportation Specification 6M (DOT-6M) packaging was identified by the US Department of Energy (DOE)-Headquarters, Transportation Management Division (EM-261) because the DOT-6M packaging is widely used by DOE site contractors and the DOE receives many questions about approved packaging configuration. Currently, EM-261 has the authority to approve new DOT-6M packaging configurations for use by the DOE Operations Offices. This user's guide identifies the DOE-approved DOT-6M packaging configurations and explains how to have new configurations approved by the DOE. The packaging configurations described in this guide are approved by the DOE, and satisfy the applicable DOT requirements and the identified DOE restrictions. These packaging configurations are acceptable for transport of Type B quantities of radioactive and fissile material, including plutonium

Legislator's guide to low-level radioactive waste management

International Nuclear Information System (INIS)

Jordan, J.M.; Melson, L.G.

1981-05-01

The purpose of the guide is to provide state legislators and their staff with information on low-level radioactive waste management, issues of special concern to the states, and policy options. During 1979, producers of low-level radioactive wastes (LLW) faced a crisis. Two of the three commercial disposal sites were temporarily closed and some LLW producers were running short on storage space. For hospitals, clinics, research organizations, and some industries, this meant potential curtailment of activities that produced these materials. Commercial nuclear reactors were not as hard hit during the crisis because they have larger storage areas. The two sites at Beatty, Nevada, and Hanford, Washington, reopened and the immediate crisis was averted. However, the longer term problem of shortage of disposal capacity was just beginning to be recognized. States should be concerned with this problem for several reasons. First, all states produce LLW although the volumes differ among states. Second, states have the responsibility to protect the public health and welfare of their citizens. Third, states may be given the authority to regulate LLW disposal if they enter into agreements with the federal government (Agreement States Program), and 26 states have that authority. Fourth, because of the long-term monitoring and surveillance necessary at a disposal site, states rather than private industry will be held responsible for ensuring that the disposal site is performing safely. Finally, Congress established a policy in 1980 that each state is responsible for the safe disposal of LLW generated within its borders. This policy also includes provisions that could lead to excluding states from using disposal facilities unless they have entered into regional agreements with other states. Two primary options exist for a state: developing its own disposal facility for LLW generated within its borders or joining with other states to develop a regional disposal facility

Safe and Secure Transportation of Radioactive Materials in Pakistan and Future Challenges

International Nuclear Information System (INIS)

Muneer, Muhammad; Ejaz, Asad

2016-01-01

PNRA is the sole organization in the country responsible to regulate all matters pertaining to ionizing radiations. For the safety of transport of radioactive material in the country, PNRA has adopted IAEA TS-R-1 as a national regulation. To cover the security aspects and emergency situations, if any, during the transportation of radioactive material, PNRA has issued the regulatory guide on ‘Transportation of Radioactive Material by Road in Pakistan’. In Pakistan, low to medium activity radioactive sources are transported from one place to another by road for the purpose of industrial radiography, well logging, medical application, etc. According to national policy, sealed radioactive sources of half life greater than 1 year and with initial activity of 100 GBq or more imported in the country are required to be returned to country of origin (exported) after its use. Although the activities related to transport of radioactive material remained safe and secure and no major accident/incident has been reported so far, however, the improvement/enhancement in the regulatory infrastructure is a continuous process. In future, more challenges are expected to be faced in the safety of transport packages. This paper will describe the steps taken by PNRA for the safety and security of transport of radioactive material in the country and future challenges. (author)

A guide to archival collections relating to radioactive fallout from nuclear weapon testing

International Nuclear Information System (INIS)

Martin, B.W.

1992-09-01

This ninth edition of A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing constitutes History Associates Incorporated's (HAI) final report of its document collection, processing, and declassification efforts for the Nevada Field Office of the Department of Energy. The most significant feature of this edition is the updated HAI collection effort information. We confirmed the accuracy of this information using our screening, processing, and transmittal records. Unlike previous editions, funding limitations prevented us from systematically revising the collection descriptions and point-of-contact information for this final edition. This guide has been prepared by professional historians who have a working knowledge of many of the record collections included in the following pages. In describing materials, they have tried to include enough information so that persons unfamiliar with the complexities of large record systems will be able to determine that nature of the information in, and the quality of, each record collection

Health problems in connection with radiation from radioactive matter in fertilizers, soils and rocks

International Nuclear Information System (INIS)

Laag, J.

1988-01-01

Under the last world congress of the International Society of Soil Science in Hamburg in August 1986, the working group ''Soil and Geomedicine'' was set up. The symposium on health problems in connection with radiation from radioactive matter in fertilizers, soils and rocks was a joint arrangement of this working group and a permanent committe of The Norwegian Academy of Science and Letters. The book presents the full text of 13 of the papers presented at the symposium. Separate abstacts have been submitted for 12 of these papers

Benchmarking Microwave Cavity Dark Matter Searches using a Radioactive Source

CERN Multimedia

Caspers, F

2014-01-01

A radioactive source is proposed as a calibration device to verify the sensitivity of a microwave dark matter search experiment. The interaction of e.g., electrons travelling in an arbitrary direction and velocity through an electromagnetically “empty” microwave cavity can be calculated numerically. We give an estimation of the energy deposited by a charged particle into a particular mode. Numerical examples are given for beta emitters and two particular cases: interaction with a field free cavity and interaction with a cavity which already contains an electromagnetic field. Each particle delivers a certain amount of energy related to the modal R/Q value of the cavity. The transferred energy is a function of the particles trajectory and its velocity. It results in a resonant response of the cavity, which can be observed using a sensitive microwave receiver, provided that the deposited energy is significantly above the single photon threshold.

The transport safety of radioactive matters

International Nuclear Information System (INIS)

Landier, D.; Louet, Ch.A.; Robert, Ch.; Binet, J.; Malesys, P.; Pourade, C.; Le Meur, A.; Robert, M.; Turquet de Beauregard, G.Y.; Hello, E.; Laumond, A.; Regnault, Ph.; Gourlay, M.; Bruhl, G.; Malvache, P.; Dumesnil, J.; Cohen, B.; Sert, G.; Pain, M.; Green, L.; Hartenstein, M.; Stewart, J.; Cottens, E.; Liebens, M.; Marignac, Y.

2007-01-01

Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

MARS, a new beamline for radioactive matter studies at SOLEIL

International Nuclear Information System (INIS)

Solari, Pier Lorenzo; Schlutig, Sandrine; Hermange, Herve; Sitaud, Bruno

2009-01-01

MARS (Multi Analyses on Radioactive Samples) beamline is the hard X-ray bending magnet beamline dedicated to the study of radioactive matter of the new French synchrotron SOLEIL. The beamline, which has been built thanks to a close partnership and support by the CEA, has been designed to provide X-rays in the energy range of 3.5 keV to 35 keV. This allows to encompass M and L absorption edges of actinides, as well as K edges of transition metals (that are present in alloys and fuel claddings) up to heavy halogens, rare gases and alkalis (fission products in nuclear fuels). The MARS project aims to extend the possibilities of synchrotron based X-ray characterizations towards a wider variety of radioactive elements and a wider variety of techniques than what is currently available at other facilities. Thus, its specific and innovative infrastructure has been optimized in order to carry out analyses on materials with activities up to 18.5 GBq per sample for α and β emitters and 2 GBq for γ and n emitters. So, today, more than 70 different elements and more than 350 different isotopes have been proposed for studies on the beamline by the involved user community. The arrangement of the different elements in the optics hutch is based on an original scheme which permits to have two alternative optical configurations (monochromatic or dispersive) depending on the nature of experiments to be performed. At least three main techniques are progressively being proposed on the three complementary end-stations located in the experimental hutch: transmission and high resolution powder diffraction (TXRD and HRXRD), standard and dispersive X-ray absorption spectroscopy (XAS and EDXAS) and X-ray fluorescence (XRF). In addition, by using the KB optics, a micro-focused beam will be available on the second station of the monochromatic branch. The beamline is currently under commissioning. The first two experimental stations, using the monochromatic branch, are scheduled to be

Radioactivity and its measurement

CERN Document Server

Mann, W B; Garfinkel, S B

1980-01-01

Begins with a description of the discovery of radioactivity and the historic research of such pioneers as the Curies and Rutherford. After a discussion of the interactions of &agr;, &bgr; and &ggr; rays with matter, the energetics of the different modes of nuclear disintegration are considered in relation to the Einstein mass-energy relationship as applied to radioactive transformations. Radiation detectors and radioactivity measurements are also discussed

Treatment of hepatocellular carcinoma adjacent to large blood vessels using 1.5T MRI-guided percutaneous radiofrequency ablation combined with iodine-125 radioactive seed implantation

Energy Technology Data Exchange (ETDEWEB)

Lin, Zheng-Yu, E-mail: linsinlan@yahoo.com.cn [The Department of Radiology, First Affiliated Hospital of Fujian Medical University, 20 Chazhong Road, Fuzhou 350005 (China); Chen, Jin, E-mail: snow8968851@163.com [The Department of Radiology, First Affiliated Hospital of Fujian Medical University, 20 Chazhong Road, Fuzhou 350005 (China); Deng, Xiu-Fen, E-mail: dxf197286@yahoo.com.cn [The Department of Radiology, First Affiliated Hospital of Fujian Medical University, 20 Chazhong Road, Fuzhou 350005 (China)

2012-11-15

Objective: The objective is to study the technology associated with and feasibility of the treatment of hepatocellular carcinoma (HCC) adjacent to large blood vessels using 1.5T MRI-guided radiofrequency ablation combined with iodine-125 (I-125) radioactive seed implantation. Methods: Sixteen patients with a total of 24 HCC lesions (average maximum diameter: 2.35 {+-} 1.03 cm) were pathologically confirmed by biopsy or clinically diagnosed received 1.5T MRI-guided percutaneous radiofrequency ablation (RFA) treatment. Each patient had one lesion adjacent to large blood vessels ({>=}3 mm); after the ablation, I-125 radioactive seeds were implanted in the portions of the lesions that were adjacent to the blood vessels. Results: All the ablations and I-125 radioactive seed implantations were successful; a total of 118 seeds were implanted. The ablated lesions exhibited hypointense signals on the T2WI sequence with a thin rim of hyperintense signals; they also exhibited significant hyperintense signals on the T1WI sequence with clear boundaries. The average follow-up period was 11.1 {+-} 6.2 months. There were 23 complete responses and one partial response in the 24 lesions. The alpha-fetoprotein (AFP) levels of the patients significantly decreased. Conclusion: The 1.5T MRI-guided RFA combined with I-125 radioactive seed implantation for the treatment of HCC adjacent to large blood vessels is an effective technology.

Guide to sampling airborne radioactive materials in nuclear facilities

International Nuclear Information System (INIS)

Glissmeyer, J.A.

1995-01-01

The ANSI N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities is currently being revised. The revision is being drafted by a working group under the auspices of the Health Physics Society Standards Committee. The main differences between the original standard and the proposed revision are a narrowed scope, a greater emphasis on the design process, and the verification of meeting performance criteria. Compliance with the revised standard will present new challenges, especially in the area of performance validation. The progress made in the revision and key portions of the standard are discussed. The DOE has recently petitioned EPA for alternate approaches to complying with air-sampling regulations. Dealing with compliance issues until the revised standard is adopted will be a challenge for both designers and regulators. The objective of this paper is to briefly describe the content of the proposed revision in order to point out significant differences from the old standard and to describe the new challenges that the proposed revision will present

Guide to sampling airborne radioactive materials in nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Glissmeyer, J.A. [Pacific Northwest Laboratory, Richland, WA (United States)

1995-02-01

The ANSI N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities is currently being revised. The revision is being drafted by a working group under the auspices of the Health Physics Society Standards Committee. The main differences between the original standard and the proposed revision are a narrowed scope, a greater emphasis on the design process, and the verification of meeting performance criteria. Compliance with the revised standard will present new challenges, especially in the area of performance validation. The progress made in the revision and key portions of the standard are discussed. The DOE has recently petitioned EPA for alternate approaches to complying with air-sampling regulations. Dealing with compliance issues until the revised standard is adopted will be a challenge for both designers and regulators. The objective of this paper is to briefly describe the content of the proposed revision in order to point out significant differences from the old standard and to describe the new challenges that the proposed revision will present.

Management of radioactive waste: A review

OpenAIRE

Luis Paulo Sant'ana; Taynara Cristina Cordeiro

2016-01-01

The issue of disposal of radioactive waste around the world is not solved by now and the principal reason is the lack of an efficient technologic system. The fact that radioactive waste decays of radioactivity with time are the main reasons for setting nuclear or radioactive waste apart from the other common hazardous wastes management. Radioactive waste can be classified according to the state of matter and level of radioactivity and this classification can be differently interpreted from co...

Mind over Matter. Teacher's Guide.

Science.gov (United States)

National Inst. on Drug Abuse (DHHS/PHS), Rockville, MD.

This teacher's guide aims to develop an understanding among students in grades 5-9 about the biological effects of drug use. The guide provides background information on the anatomy of the brain, nerve cells and neurotransmission, and the effects of drugs on the brain. Drugs described in this guide include marijuana, opiates, inhalants,…

A guide to radiation and radioactivity levels near high energy particle accelerators

International Nuclear Information System (INIS)

Sullivan, A.H.

1992-01-01

An estimate of likely radiation and radioactivity levels is needed at the design stage of an accelerator for deciding the radiation safety features to be incorporated in the infrastructure of the machine and for predicting where radiation damage possibilities will have to be taken into account. Both these aspects can have a significant influence on the machine layout and cost. Failure to make a reasonable assessment at the right time may have far reaching consequences for future costs. The purpose of this guide is to bring together basic data and methods that have been found useful in assessing radiation situations around accelerators and to provide a practical means of arriving at the radiation and induced radioactivity levels that could occur under a wide variety of circumstances. An attempt is made to present the information in a direct and unambiguous way with sufficient confidence that the necessity for large safety factors is avoided. In many cases assumptions and simplifications have been made and reliance placed on extrapolating from experimental data into regions where the basic physics is too complicated to make meaningful absolute calculations. Wherever possible such extrapolations have been tied to real or otherwise acceptable data originating from independent sources. (Author)

Analysis of radioactivity concentration in naturally occurring radioactive materials used in coal-fired plants in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Geom; Kim, Si Young; Ji, Seung Woo; Park, Il; Kim, Min Jun; Kim, Kwang Pyo [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

2017-02-15

Coals and coal ashes, raw materials and by-products, in coal-fired power plants contain naturally occurring radioactive materials (NORM). They may give rise to internal exposure to workers due to inhalation of airborne particulates containing radioactive materials. It is necessary to characterize radioactivity concentrations of the materials for assessment of radiation dose to the workers. The objective of the present study was to analyze radioactivity concentrations of coals and by-products at four coal-fired plants in Korea. High purity germanium detector was employed for analysis of uranium series, thorium series, and potassium 40 in the materials. Radioactivity concentrations of {sup 226}Ra, {sup 228}Ra, and {sup 40}K were 2⁓53 Bq kg{sup -1}, 3⁓64 Bq kg{sup -1}, and 14⁓431 Bq kg{sup -1} respectively in coal samples. For coal ashes, the radioactivity concentrations were 77⁓133 Bq kg{sup -1}, 77⁓105 Bq kg{sup -1}, and 252⁓372 Bq kg{sup -1} in fly ash samples and 54⁓91 Bq kg{sup -1}, 46⁓83 Bq kg{sup -1}, and 205⁓462 Bq kg{sup -1} in bottom ash samples. For flue gas desulfurization (FGD) gypsum, the radioactivity concentrations were 3⁓5 Bq kg{sup -1}, 2⁓3 Bq kg{sup -1}, and 22⁓47 Bq kg{sup -1}. Radioactivity was enhanced in coal ash compared with coal due to combustion of organic matters in the coal. Radioactivity enhancement factors for {sup 226}Ra, {sup 228}Ra, and {sup 40}K were 2.1⁓11.3, 2.0⁓13.1, and 1.4⁓7.4 for fly ash and 2.0⁓9.2, 2.0⁓10.0, 1.9⁓7.7 for bottom ash. The database established in this study can be used as basic data for internal dose assessment of workers at coal-fred power plants. In addition, the findings can be used as a basic data for development of safety standard and guide of Natural Radiation Safety Management Act.

Design and operation of radioactive waste incineration facilities

International Nuclear Information System (INIS)

1992-01-01

The purpose of this guide is to provide safety guidance for the design and operation of radioactive waste incineration facilities. The guide emphasizes the design objectives and system requirements to be met and provides recommendations for the procedure of process selection and equipment design and operation. It is recognized that some incinerators may handle only very low or 'insignificant' levels of radioactivity, and in such cases some requirements or recommendations of this guide may not fully apply. Nevertheless, it is expected that any non-compliance with the guide will be addressed and justified in the licensing process. It is also recognized that the regulatory body may place a limit on the level of the radioactivity of the waste to be incinerated at a specific installation. For the purpose of this guide an insignificant level of release of radioactivity may typically be defined as either the continuous or single event release of the design basis radionuclide inventory that represents a negligible risk to the population, the operating personnel, and/or the environment. The guidance on what constitutes a negligible risk and how to translate negligible risk or dose into level of activity can be found in Safety Series No. 89, IAEA, Vienna. 20 refs, 1 fig

Predisposal Management of Low and Intermediate Level Radioactive Waste. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established for the predisposal management of low and intermediate level waste. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. General safety considerations; 5. Safety features for the predisposal management of LILW; 6. Record keeping and reporting; 7. Safety assessment; 8. Quality assurance; Annex I: Nature and sources of LILW from nuclear facilities; Annex II: Development of specifications for waste packages; Annex III: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Postulated initiating events for consideration in a safety assessment (internal phenomena).

Treatment and storage of radioactive waste at a nuclear power plant

International Nuclear Information System (INIS)

1996-01-01

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

Guide for decontaminating swimming pool at schools

International Nuclear Information System (INIS)

Matsuhashi, Shimpei; Kurikami, Hiroshi; Yasuda, Ryo; Takano, Takao; Seko, Noriaki; Naganawa, Hirochika; Kuroki, Ryota; Saegusa, Jun

2012-07-01

Because of TEPCO Fukushima Dai-ichi Nuclear Power Plant accident due to the Great East Japan Earthquake, a huge amount of radioactive materials was widely dispersed and precipitated into the environment. Swimming pools in Fukushima prefectures were contaminated with the radioactives. We JAEA carried out several demonstration tests to decontaminate the radioactives and discharge the pool water safely. We concluded the results obtained from the tests as 'Guide for decontaminating Swimming Pool at School' and released it quickly. Following this, we also released the guide in English. This manuscript, as an experimental report of the swimming pool water decontamination, is consisted from the guide in Japanese and English prepared. (author)

Guide for decontaminating swimming pool at schools

Energy Technology Data Exchange (ETDEWEB)

Matsuhashi, Shimpei; Kurikami, Hiroshi; Yasuda, Ryo; Takano, Takao; Seko, Noriaki; Naganawa, Hirochika; Kuroki, Ryota; Saegusa, Jun

2012-07-15

Because of TEPCO Fukushima Dai-ichi Nuclear Power Plant accident due to the Great East Japan Earthquake, a huge amount of radioactive materials was widely dispersed and precipitated into the environment. Swimming pools in Fukushima prefectures were contaminated with the radioactives. We JAEA carried out several demonstration tests to decontaminate the radioactives and discharge the pool water safely. We concluded the results obtained from the tests as 'Guide for decontaminating Swimming Pool at School' and released it quickly. Following this, we also released the guide in English. This manuscript, as an experimental report of the swimming pool water decontamination, is consisted from the guide in Japanese and English prepared. (author)

Security in the transport of radioactive material: Implementing guide. Spanish edition; La seguridad fisica en el transporte de materiales radiactivos. Guia de aplicacion

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

This guide provides States with guidance in implementing, maintaining or enhancing a nuclear security regime to protect radioactive material (including nuclear material) in transport against theft, sabotage or other malicious acts that could, if successful, have unacceptable radiological consequences. From a security point of view, a threshold is defined for determining which packages or types of radioactive material need to be protected beyond prudent management practice. Minimizing the likelihood of theft or sabotage of radioactive material in transport is accomplished by a combination of measures to deter, detect, delay and respond to such acts. These measures are complemented by other measures to recover stolen material and to mitigate possible consequences, in order to further reduce the risks.

Treatment of short-lived radioactive wastes

International Nuclear Information System (INIS)

Yamaguchi, Chiri

1976-01-01

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

Radioactive air sampling methods

CERN Document Server

Maiello, Mark L

2010-01-01

Although the field of radioactive air sampling has matured and evolved over decades, it has lacked a single resource that assimilates technical and background information on its many facets. Edited by experts and with contributions from top practitioners and researchers, Radioactive Air Sampling Methods provides authoritative guidance on measuring airborne radioactivity from industrial, research, and nuclear power operations, as well as naturally occuring radioactivity in the environment. Designed for industrial hygienists, air quality experts, and heath physicists, the book delves into the applied research advancing and transforming practice with improvements to measurement equipment, human dose modeling of inhaled radioactivity, and radiation safety regulations. To present a wide picture of the field, it covers the international and national standards that guide the quality of air sampling measurements and equipment. It discusses emergency response issues, including radioactive fallout and the assets used ...

Sellafield (release of radioactivity)

Energy Technology Data Exchange (ETDEWEB)

Cunningham, J; Goodlad, A; Morris, M

1986-02-06

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

Handbook for Response to Suspect Radioactive Materials

International Nuclear Information System (INIS)

Cliff, William C.; Pappas, Richard A.; Arthur, Richard J.

2005-01-01

This document provides response actions to be performed following the initial port, airport, or border crossing discovery of material that is suspected of being radioactive. The purpose of this guide is to provide actions appropriate for handling radioactive material

The management system for the disposal of radioactive waste. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The objective of this Safety Guide is to provide recommendations on developing and implementing management systems for all phases of facilities for the disposal of radioactive waste and related activities. It covers the management systems for managing the different stages of waste disposal facilities, such as siting, design and construction, operation (i.e. the activities, which can extend over several decades, involving receipt of the waste product in its final packaging (if it is to be disposed of in packaged form), waste emplacement in the waste disposal facility, backfilling and sealing, and any subsequent period prior to closure), closure and the period of institutional control (i.e. either active control - monitoring, surveillance and remediation; or passive control - restricted land use). The management systems apply to various types of disposal facility for different categories of radioactive waste, such as: near surface (for low level waste), geological (for low, intermediate and/or high level waste), boreholes (for sealed sources), surface impoundment (for mining and milling waste) and landfill (for very low level waste). It also covers management systems for related processes and activities, such as extended monitoring and surveillance during the period of active institutional control in the post-closure phase, safety and performance assessments and development of the safety case for the waste disposal facility and regulatory authorization (e.g. licensing). This Safety Guide is intended to be used by organizations that are directly involved in, or that regulate, the facilities and activities described in paras 1.15 and 1.16, and by the suppliers of nuclear safety related products that are required to meet some or all of the requirements established in IAEA Safety Standards Series No. GS-R-3 'The Management System for Facilities and Activities'. It will also be useful to legislators and to members of the public and other parties interested in the nuclear

Emergency response planning and preparedness for transport accidents involving radioactive material

International Nuclear Information System (INIS)

1988-01-01

The purpose of this Guide is to provide assistance to public authorities and others (including consignors and carriers of radioactive materials) who are responsible for ensuring safety in establishing and developing emergency response arrangements for responding effectively to transport accidents involving radioactive materials. This Guide is concerned mainly with the preparation of emergency response plans. It provides information which will assist those countries whose involvement with radioactive materials is just beginning and those which have already developed their industries involving radioactive materials and attendant emergency plans, but may need to review and improve these plans. The need for emergency response plans and the ways in which they are implemented vary from country to country. In each country, the responsible authorities must decide how best to apply this Guide, taking into account the actual shipments and associated hazards. In this Guide the emergency response planning and response philosophy are outlined, including identification of emergency response organizations and emergency services that would be required during a transport accident. General consequences which could prevail during an accident are described taking into account the IAEA Regulations for the Safe Transport of Radioactive Material. 43 refs, figs and tabs

Radioactive waste processing device

International Nuclear Information System (INIS)

Seki, Shuji.

1992-01-01

Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

Handheld single photon emission computed tomography (handheld SPECT) navigated video-assisted thoracoscopic surgery of computer tomography-guided radioactively marked pulmonary lesions.

Science.gov (United States)

Müller, Joachim; Putora, Paul Martin; Schneider, Tino; Zeisel, Christoph; Brutsche, Martin; Baty, Florent; Markus, Alexander; Kick, Jochen

2016-09-01

Radioactive marking can be a valuable extension to minimally invasive surgery. The technique has been clinically applied in procedures involving sentinel lymph nodes, parathyroidectomy as well as interventions in thoracic surgery. Improvements in equipment and techniques allow one to improve the limits. Pulmonary nodules are frequently surgically removed for diagnostic or therapeutic reasons; here video-assisted thoracoscopic surgery (VATS) is the preferred technique. VATS might be impossible with nodules that are small or located deep in the lung. In this study, we examined the clinical application and safety of employing the newly developed handheld single photon emission tomography (handheld SPECT) device in combination with CT-guided radioactive marking of pulmonary nodules. In this pilot study, 10 subjects requiring surgical resection of a pulmonary nodule were included. The technique involved CT-guided marking of the target nodule with a 20-G needle, with subsequent injection of 25-30 MBq (effective: 7-14 MBq) Tc-99m MAA (Macro Albumin Aggregate). Quality control was made with conventional SPECT-CT to confirm the correct localization and exclude possible complications related to the puncture procedure. VATS was subsequently carried out using the handheld SPECT to localize the radioactivity intraoperatively and therefore the target nodule. A 3D virtual image was superimposed on the intraoperative visual image for surgical guidance. In 9 of the 10 subjects, the radioactive application was successfully placed directly in or in the immediate vicinity of the target nodule. The average size of the involved nodules was 9 mm (range 4-15). All successfully marked nodules were subsequently completely excised (R0) using VATS. The procedure was well tolerated. An asymptomatic clinically insignificant pneumothorax occurred in 5 subjects. Two subjects were found to have non-significant discrete haemorrhage in the infiltration canal of the needle. In a single subject, the

Radioactive waste management regulatory framework in Mexico

International Nuclear Information System (INIS)

Barcenas, M.; Mejia, M.

2001-01-01

The purpose of this paper is to present an overview of the current regulatory framework concerning the radioactive waste management in Mexico. It is intended to show regulatory historical antecedents, the legal responsibilities assigned to institutions involved in the radioactive waste management, the sources of radioactive waste, and the development and preparation of national standards for fulfilling the legal framework for low level radioactive waste. It is at present the most important matter to be resolved. (author)

The transport safety of radioactive matters; La surete des transports des matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

Landier, D.; Louet, Ch.A.; Robert, Ch. [Autorite de Surete Nucleaire, 75 - Paris (France); Binet, J. [Commission europeenne, DG Energie et transports, Bruxelles (Belgium); Malesys, P. [TN International, 75 - Paris (France); Pourade, C. [Societe Dangexpress, 78 - St Remy l' Honore (France); Le Meur, A.; Robert, M. [Societe Nationale des Chemins de fer Francais, 75 - Paris (France); Turquet de Beauregard, G.Y.; Hello, E. [CIS bio, 91 - Gif sur Yvette (France); Laumond, A. [Electricite de France (EDF), 75 - Paris (France); Regnault, Ph.; Gourlay, M. [AREVA NC, 78 - Velizy Villacoublay (France); Bruhl, G. [CEA Fontenay-aux-Roses, Dir. de la Protection et de la Surete Nucleaire, 92 (France); Malvache, P.; Dumesnil, J. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Cohen, B. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Sert, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Pain, M. [Ministere de l' Interieur, et de l' Amenagement du Territoire, Dir. de la Defense et la Securite Civiles, 75 - Paris (France); Green, L.; Hartenstein, M. [World Nuclear Transport Institute, London (United Kingdom); Stewart, J. [Ministere des Transport, Royaume Uni (United Kingdom); Cottens, E.; Liebens, M. [Agence Federale de Controle Nucleaire (Belgium); Marignac, Y. [Wise, 75 - Paris (France)

2007-02-15

Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

The radiation protection and the radioactive wastes management

International Nuclear Information System (INIS)

Servais, F.; Woiche, Ch.; Hunin, Ch.

2003-01-01

This chapter concerns the radiation protection in relation with the radioactive waste management. Three articles make the matter of this file, the management of radioactive medical waste into hospitals, a new concept of waste storage on site, the protection devices on the long term with some lessons for the radioactive waste management. (N.C.)

ORNL radioactive waste operations

International Nuclear Information System (INIS)

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

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

Are mushrooms radioactive?

International Nuclear Information System (INIS)

Randa, Z.; Benada, J.; Singert, M.; Horyna, J.

1988-01-01

Tabulated is the content of 137 Cs in dry matter of higher mushrooms collected in the years 1986 to 1987. The radioactive level of mushrooms collected in Czechoslovakia such as Boletus badius and B. chrysenteron reached 20 to 50 kBq/kg of dry matter. The individual dose at mean consumption of these mushrooms was estimated at 0.2 to 0.3 mSv/year which amounted to 20 to 30% of the dose from the natural background. (J.B.). 1 tab

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The IAEA issues Safety Requirements and Safety Guides pertaining to nuclear power plants and activities in the field of nuclear energy, on the basis of its Safety Fundamentals publication on The Safety of Nuclear Installations. The present Safety Guide, which supplements the Code on the Safety of Nuclear Power Plants: Siting, concerns the effects of a nuclear power plant on the surrounding region and the consideration of population distribution in the siting of a plant. This Safety Guide makes recommendations on how to meet the requirements of the Code on the Safety of Nuclear Power Plants: Siting, on the basis of knowledge of the mechanisms for the dispersion of effluents discharged into the atmosphere and into surface water and groundwater. Relevant site characteristics and safety considerations are discussed. Population distribution, the projected population growth rate, particular geographical features, the capabilities of local transport networks and communications networks, industry and agriculture in the region, and recreational and institutional activities in the region should be considered in assessing the feasibility of developing an emergency response plan. In the selection of a site for a facility using radioactive material, such as a nuclear power plant, account should be taken of any local features that might be affected by the facility and of the feasibility of off-site intervention, including emergency response and protective actions. This is in addition to the evaluation of any features of the site itself that might affect the safety of the facility. This Safety Guide recommends methods for the assessment of regional and local characteristics. This Safety Guide supersedes four earlier IAEA Safety Guides, namely: Atmospheric Dispersion in Nuclear Power Plant Siting (Safety Series No. 50-SG-S3 (1980)). Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution (Safety Series No. 50-SG-S4 (1980)). Hydrological

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The IAEA issues Safety Requirements and Safety Guides pertaining to nuclear power plants and activities in the field of nuclear energy, on the basis of its Safety Fundamentals publication on The Safety of Nuclear Installations. The present Safety Guide, which supplements the Code on the Safety of Nuclear Power Plants: Siting, concerns the effects of a nuclear power plant on the surrounding region and the consideration of population distribution in the siting of a plant. This Safety Guide makes recommendations on how to meet the requirements of the Code on the Safety of Nuclear Power Plants: Siting, on the basis of knowledge of the mechanisms for the dispersion of effluents discharged into the atmosphere and into surface water and groundwater. Relevant site characteristics and safety considerations are discussed. Population distribution, the projected population growth rate, particular geographical features, the capabilities of local transport networks and communications networks, industry and agriculture in the region, and recreational and institutional activities in the region should be considered in assessing the feasibility of developing an emergency response plan. In the selection of a site for a facility using radioactive material, such as a nuclear power plant, account should be taken of any local features that might be affected by the facility and of the feasibility of off-site intervention, including emergency response and protective actions. This is in addition to the evaluation of any features of the site itself that might affect the safety of the facility. This Safety Guide recommends methods for the assessment of regional and local characteristics. This Safety Guide supersedes four earlier IAEA Safety Guides, namely: Atmospheric Dispersion in Nuclear Power Plant Siting (Safety Series No. 50-SG-S3 (1980)); Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution (Safety Series No. 50-SG-S4 (1980)); Hydrological

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.)

From the discovery of radioactivity to the production of radioactive beams

International Nuclear Information System (INIS)

Bimbot, R.

1999-01-01

The evolution of the projectiles used to explore the nucleus influenced strongly the development of Nuclear Physics. The alpha particles from radioactivity were the projectiles mostly used up to the second world war. This period was marked by fundamental discoveries, as those of artificial radioactivity and of fission. From the 1930's to 1070, light accelerated particles (electrons, protons, deuterons, isotopes of helium) became universally used. A third period began in the 1960's with the emergence of heavy ion accelerators, the use of which led to a true revolution in the study of nuclear matter. Finally, the fourth period started in 1985 when the first secondary beams of radioactive nuclei were produced, and opened new ways in physics. (authors)

Inventory of radioactive material entering the marine environment: Sea disposal of radioactive waste

International Nuclear Information System (INIS)

1991-03-01

Variable amounts of packaged low level radioactive waste have been disposed at more than 50 sites in the northern parts of the Atlantic and Pacific Oceans. The last known disposal operation was in 1982, at a site about 550 km off the European continental shelf in the Atlantic Ocean. Since 1957, the IAEA has provided specific guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. In 1972, the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter designated the IAEA as the competent international authority in matters related to sea disposal of radioactive waste. The Contracting Parties requested the IAEA to develop an inventory of radioactive wastes entering the marine environment from all sources as an information base with which the impact of radioactive materials from disposal operations can be more adequately assessed. The continuous compilation of these data could ensure that the IAEA recommendations on the disposal rate in a single basin are not overstepped. The inventory shows that between 1946 to 1982 an estimated 46 PBq 1 (1.24 MCi) of radioactive waste coming from research, medicine, the nuclear industry and military activities were packaged, usually in metal drums lined with a concrete or bitumen matrix, and disposed of at sea. This inventory includes some unpackaged wastes and liquid wastes which were disposed of from 1950 to 1960. Beta-gamma emitters represent more than 98% of the total radioactivity of the waste and tritium alone represents one third of the total radioactivity disposed at the North East Atlantic sites. The other beta-gamma emitters radionuclides include 90 Sr, 137 Cs, 55 Fe, 58 Co, 60 Co, 125 I and 14 C. The wastes also contain low quantities of alpha-emitting nuclides with plutonium and americium isotopes representing

Multimedia instructions for carriers of radioactive material

International Nuclear Information System (INIS)

Sahyun, A.; Sordi, G. M.; Simpson, J.; Ghobril, C. N.; Perez, C. F.

2014-08-01

For some operators the transport regulations for transporting radioactive material are considered to be complicated and not user friendly and as a result for some operators it is difficult to identify all the transport regulatory requirements they must comply with for each type of package or radioactive material. These difficulties can result in self-checking being ineffective and as a consequence the first and important step in the safety chain is lost. This paper describes a transport compliance guide for operators that is currently under development for the South American market. This paper describes the scope and structure of the guide and examples of the information provided is given, which will be available in English, Portuguese and Spanish. It is intended that when the guide is launched before the end of 2013 it will be accessed using a bespoke software program that can run on Pc platform to provide a checklist for the operator before the shipment begins By identifying the regulatory requirements the guide is also intended to provide operators with an understanding of the structure of the transport regulations and an appreciation of the logic behind the regulatory requirements for each Un numbered package and material type listed in the transport regulations for radioactive material. It is foreseen that the interactive program can be used both operationally on a day-to-day basis and as a training tool, including refresher training, as the guide will be updated when the transport regulations are periodically changed. (Author)

Multimedia instructions for carriers of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Sahyun, A.; Sordi, G. M. [Instituto de Pesquisas Energeticas e Nucleares, Av. Prof. Lineu Prestes 2242, Cidade Universitaria, 05508-000 Sao Paulo (Brazil); Simpson, J. [Class 7 Limited, 9 Irk Vale Drive, Chadderton, Oldham OL1 2TW (United Kingdom); Ghobril, C. N. [Governo de Sao Paulo, Instituto de Economia Agricola, 04301-903 Sao Paulo (Brazil); Perez, C. F., E-mail: adelia@atomo.com.br [Centro Tecnologico da Marinha em Sao Paulo, Av. Prof. Lineu Prestes 2468, Cidade Universitaria, 05508-000 Sau Paulo (Brazil)

2014-08-15

For some operators the transport regulations for transporting radioactive material are considered to be complicated and not user friendly and as a result for some operators it is difficult to identify all the transport regulatory requirements they must comply with for each type of package or radioactive material. These difficulties can result in self-checking being ineffective and as a consequence the first and important step in the safety chain is lost. This paper describes a transport compliance guide for operators that is currently under development for the South American market. This paper describes the scope and structure of the guide and examples of the information provided is given, which will be available in English, Portuguese and Spanish. It is intended that when the guide is launched before the end of 2013 it will be accessed using a bespoke software program that can run on Pc platform to provide a checklist for the operator before the shipment begins By identifying the regulatory requirements the guide is also intended to provide operators with an understanding of the structure of the transport regulations and an appreciation of the logic behind the regulatory requirements for each Un numbered package and material type listed in the transport regulations for radioactive material. It is foreseen that the interactive program can be used both operationally on a day-to-day basis and as a training tool, including refresher training, as the guide will be updated when the transport regulations are periodically changed. (Author)

Radioactive material in residues of health services residues

International Nuclear Information System (INIS)

Costa R, A. Jr.; Recio, J.C.

2006-01-01

The work presents the operational actions developed by the one organ responsible regulator for the control of the material use radioactive in Brazil. Starting from the appearance of coming radioactive material of hospitals and clinical with services of nuclear medicine, material that that is picked up and transported in specific trucks for the gathering of residuals of hospital origin, and guided one it manufactures of treatment of residuals of services of health, where they suffer radiological monitoring before to guide them for final deposition in sanitary embankment, in the city of Sao Paulo, Brazil. The appearance of this radioactive material exposes a possible one violation of the norms that govern the procedures and practices in that sector in the country. (Author)

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)

Radioactivity in the environment

International Nuclear Information System (INIS)

Fernandez Niello, Jorge

2005-01-01

The book summarizes general concepts on radiation, nuclear structure, radioactivity and the interaction of the nuclear radiation with matter. It describes also the basic principles of radio dosimetry. Natural and artificial sources of radiation are reviewed as well as the effects of radiation in man. Medical and industrial applications of ionizing radiation and the pollution produced by the discharge of radioactive materials are outlined. A short review is made of the safety rules and the regulations concerning the protection of the environment [es

Radioactive action code

International Nuclear Information System (INIS)

Anon.

1988-01-01

A new coding system, 'Hazrad', for buildings and transportation containers for alerting emergency services personnel to the presence of radioactive materials has been developed in the United Kingdom. The hazards of materials in the buildings or transport container, together with the recommended emergency action, are represented by a number of codes which are marked on the building or container and interpreted from a chart carried as a pocket-size guide. Buildings would be marked with the familiar yellow 'radioactive' trefoil, the written information 'Radioactive materials' and a list of isotopes. Under this the 'Hazrad' code would be written - three symbols to denote the relative radioactive risk (low, medium or high), the biological risk (also low, medium or high) and the third showing the type of radiation emitted, alpha, beta or gamma. The response cards indicate appropriate measures to take, eg for a high biological risk, Bio3, the wearing of a gas-tight protection suit is advised. The code and its uses are explained. (U.K.)

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2001-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advice the nuclear and non-nuclear industry in matters concerning radioactive contamination and/or low-level radioactivity measurements; (4) to maintain the quality assurance system according to the EN45001/ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2000 are reported

Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education. Safety guide

International Nuclear Information System (INIS)

2009-01-01

activity measurement systems (such as those employing liquid scintillation counters). Gaseous waste is generated at a number of facilities in the production and radiolabelling of chemical compounds and organisms and in the treatment of solid and liquid waste. In view of the variable range of waste types encountered and the possibility of changes occurring in the ways in which the waste is generated and then managed, particular attention should be paid to the safety issues that may arise in their management and regulatory control. Regimes for both management and regulatory control should be sensitive and responsive to these factors. In facilities in which only small amounts of waste are generated, there may be limited knowledge among the staff of the safety issues relating to radioactive waste management. The safety culture among the staff may not be particularly focused on radioactive waste management because of this limited knowledge and/or because insufficient emphasis is placed on the related issues by the operating organization. Good operating practice can significantly reduce the amounts of radioactive waste generated but in general such waste cannot be entirely eliminated. The waste may contain sufficient quantities of radionuclides that it has the potential to present serious risks to human health and the environment if it is not managed properly. This Safety Guide provides recommendations and guidance on the fulfilment of the safety requirements established in Ref. It covers the roles and responsibilities of different bodies involved in the predisposal management of radioactive waste and in the handling and processing of radioactive material

Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education. Safety guide

International Nuclear Information System (INIS)

2006-01-01

activity measurement systems (such as those employing liquid scintillation counters). Gaseous waste is generated at a number of facilities in the production and radiolabelling of chemical compounds and organisms and in the treatment of solid and liquid waste. In view of the variable range of waste types encountered and the possibility of changes occurring in the ways in which the waste is generated and then managed, particular attention should be paid to the safety issues that may arise in their management and regulatory control. Regimes for both management and regulatory control should be sensitive and responsive to these factors. In facilities in which only small amounts of waste are generated, there may be limited knowledge among the staff of the safety issues relating to radioactive waste management. The safety culture among the staff may not be particularly focused on radioactive waste management because of this limited knowledge and/or because insufficient emphasis is placed on the related issues by the operating organization. Good operating practice can significantly reduce the amounts of radioactive waste generated but in general such waste cannot be entirely eliminated. The waste may contain sufficient quantities of radionuclides that it has the potential to present serious risks to human health and the environment if it is not managed properly. This Safety Guide provides recommendations and guidance on the fulfilment of the safety requirements established in Ref. It covers the roles and responsibilities of different bodies involved in the predisposal management of radioactive waste and in the handling and processing of radioactive material

Method of processing radioactive wastes

International Nuclear Information System (INIS)

Katada, Katsuo.

1986-01-01

Purpose: To improve the management for radioactive wastes containers thereby decrease the amount of stored matters by arranging the radioactive wastes containers in the order of their radioactivity levels. Method: The radiation doses of radioactive wastes containers arranged in the storing area before volume-reducing treatment are previously measured by a dosemeter. Then, a classifying machine is actuated to hoist the containers in the order to their radiation levels and the containers are sent out passing through conveyor, surface contamination gage, weight measuring device and switcher to a volume-reducing processing machine. The volume-reduced products are packed each by several units to the storing containers. Thus, the storing containers after stored for a certain period of time can be transferred in an assembled state. (Kawakami, Y.)

Radioactive transformations

CERN Document Server

Rutherford, Ernest

2012-01-01

Radioactive Transformations describes Ernest Rutherford's Nobel Prize-winning investigations into the mysteries of radioactive matter. In this historic work, Rutherford outlines the scientific investigations that led to and coincided with his own research--including the work of Wilhelm Rӧntgen, J. J. Thomson, and Marie Curie--and explains in detail the experiments that provided a glimpse at special relativity, quantum mechanics, and other concepts that would shape modern physics. This new edition features a comprehensive introduction by Nobel Laureate Frank Wilczek which engagingly explains how Rutherford's early research led to a better understanding of topics as diverse as the workings of the atom's nucleus, the age of our planet, and the fusion in stars.

Fire protection in laboratories and factories. Guide for nuclear operator

International Nuclear Information System (INIS)

Savornin, J.; Hebrard, L.; Michard, J.; Muller, G.; Vasseur, C.

1987-12-01

Putting in place a nuclear industry is possible only if is taken into account the systematic risks connecting with the manipulation of radioactive matters. The measures taken are essentially the putting in place of static or dynamic barriers confinement. Therefore in case of fire their efficiencies can be reduced. The basic safety rule no. I-4.a serie U defines the objectives but do not give all the means to arrive. The present guide has for objective to propose the means which allow to satisfy these objectives. It permits to define the importance of precautions to take in terms of possible consequences. This document is not a rule. It has for objective to give advices [fr

Risk Informed Approach for Nuclear Security Measures for Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

International Nuclear Information System (INIS)

2015-01-01

This publication provides guidance to States for developing a risk informed approach and for conducting threat and risk assessments as the basis for the design and implementation of sustainable nuclear security systems and measures for prevention of, detection of, and response to criminal and intentional unauthorised acts involving nuclear and other radioactive material out of regulatory control. It describes concepts and methodologies for a risk informed approach, including identification and assessment of threats, targets, and potential consequences; threat and risk assessment methodologies, and the use of risk informed approaches as the basis for informing the development and implementation of nuclear security systems and measures. The publication is an Implementing Guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, law enforcement agencies and experts from competent authorities and other relevant organizations involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures related to nuclear and other radioactive material out of regulatory control

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)

Radioactive effluents, Portsmouth Gaseous Diffusion Plant, calendar year 1982

International Nuclear Information System (INIS)

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

1983-03-01

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

Integrated coherent matter wave circuits

International Nuclear Information System (INIS)

Ryu, C.; Boshier, M. G.

2015-01-01

An integrated coherent matter wave circuit is a single device, analogous to an integrated optical circuit, in which coherent de Broglie waves are created and then launched into waveguides where they can be switched, divided, recombined, and detected as they propagate. Applications of such circuits include guided atom interferometers, atomtronic circuits, and precisely controlled delivery of atoms. We report experiments demonstrating integrated circuits for guided coherent matter waves. The circuit elements are created with the painted potential technique, a form of time-averaged optical dipole potential in which a rapidly moving, tightly focused laser beam exerts forces on atoms through their electric polarizability. Moreover, the source of coherent matter waves is a Bose-Einstein condensate (BEC). Finally, we launch BECs into painted waveguides that guide them around bends and form switches, phase coherent beamsplitters, and closed circuits. These are the basic elements that are needed to engineer arbitrarily complex matter wave circuitry

Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

International Nuclear Information System (INIS)

2013-01-01

Nuclear terrorism and the illicit trafficking of nuclear and other radioactive material threaten the security of all States. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The possibility that nuclear and other radioactive material may be used for terrorist acts cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material, and to establish capabilities for detection and response to nuclear and other radioactive material out of regulatory control. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This approach recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in nuclear and other radioactive material; national response plans; and contingency measures. Within its nuclear security programme, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking; and to detect and respond to nuclear security events. This is an Implementing Guide on nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control. The objective of the publication is to provide guidance to Member States for the

Waste minimization for commercial radioactive materials users generating low-level radioactive waste

International Nuclear Information System (INIS)

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S.; Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L.

1991-07-01

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature

Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

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)

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)

Development of an application simulating radioactive sources; Conception d'une application de simulation de sources radioactives

Energy Technology Data Exchange (ETDEWEB)

Riffault, V.; Locoge, N. [Ecole des Mines de Douai, Dept. Chimie et Environnement, 59 - Douai (France); Leblanc, E.; Vermeulen, M. [Ecole des Mines de Douai, 59 (France)

2011-05-15

This paper presents an application simulating radioactive gamma sources developed in the 'Ecole des Mines' of Douai (France). It generates raw counting data as an XML file which can then be statistically exploited to illustrate the various concepts of radioactivity (exponential decay law, isotropy of the radiation, attenuation of radiation in matter). The application, with a spread sheet for data analysis and lab procedures, has been released under free license. (authors)

Security guide for subcontractors

Energy Technology Data Exchange (ETDEWEB)

Adams, R.C.

1991-01-01

This security guide of the Department of Energy covers contractor and subcontractor access to DOE and Mound facilities. The topics of the security guide include responsibilities, physical barriers, personnel identification system, personnel and vehicular access controls, classified document control, protecting classified matter in use, storing classified matter repository combinations, violations, security education clearance terminations, security infractions, classified information nondisclosure agreement, personnel security clearances, visitor control, travel to communist-controlled or sensitive countries, shipment security, and surreptitious listening devices.

CT-guided radioactive 125I-seed implantation for the treatment of pancreatic carcinoma: a clinical observation of 19 cases

International Nuclear Information System (INIS)

Lu Jian; Zheng Yunfeng; Zhang Huan; Wang Zhongmin; Chen Kemin

2010-01-01

Objective: To explore the dynamic changes of serum tumor markers after CT-guided radioactive 125 I-seed implantation treatment in patients with pancreatic carcinoma and to assess the therapeutic effectiveness of 125 I-seed implantation. Methods: CT-guided radioactive 125 I-seed implantation was performed in 19 patients with unresectable advanced pancreatic cancer. Treatment planning system was used to reconstruct 3-dimentional images of the tumor, and the quantity and distribution of 125 I-seeds to be implanted were thus determined. Under CT guidance 125 I-seeds were embedded into pancreatic cancer. Before and after the 125 I-seed implantation the levels of serum tumor markers, including CEA, CA19-9 and CA50, were determined by using radioimmunoassay method. The clinical effects were observed and the therapeutic results were statistically analyzed. Results: The pain stared to be relieved 2 to 5 days after implantation. The total effective rate (CR + PR) at one and three months after treatment was 68.42% (13 /19) and 63.16% (12 /19) respectively. One month after 125 I-seed implantation, the levels of serum CEA, CA19-9 and CA50 were significantly different to that determined before implantation in all cases (P 125 I-seed implantation is a safe and effective interventional treatment for advanced pancreatic cancer with reliable short-term result and remarkable pain-relieving effect. Moreover, this therapy can significantly lower the levels of many serum tumor markers, which play some suggestive roles in evaluating the clinical curativeness. (authors)

The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

The development of guided inquiry-based learning devices on photosynthesis and respiration matter to train science literacy skills

Science.gov (United States)

Choirunnisak; Ibrahim, M.; Yuliani

2018-01-01

The purpose of this research was to develop a guided inquiry-based learning devices on photosynthesis and respiration matter that are feasible (valid, practical, and effective) to train students’ science literacy. This research used 4D development model and tested on 15 students of biology education 2016 the State University of Surabaya with using one group pretest-posttest design. Learning devices developed include (a) Semester Lesson Plan (b) Lecture Schedule, (c) Student Activity Sheet, (d) Student Textbook, and (e) testability of science literacy. Research data obtained through validation method, observation, test, and questionnaire. The results were analyzed descriptively quantitative and qualitative. The ability of science literacy was analyzed by n-gain. The results of this research showed that (a) learning devices that developed was categorically very valid, (b) learning activities performed very well, (c) student’s science literacy skills improved that was a category as moderate, and (d) students responses were very positively to the learning that already held. Based on the results of the analysis and discussion, it is concluded that the development of guided inquiry-based learning devices on photosynthesis and respiration matter was feasible to train students literacy science skills.

A user's guide to the GoldSim/BLT-MS integrated software package:a low-level radioactive waste disposal performance assessment model

International Nuclear Information System (INIS)

Knowlton, Robert G.; Arnold, Bill Walter; Mattie, Patrick D.

2007-01-01

Sandia National Laboratories (Sandia), a U.S. Department of Energy National Laboratory, has over 30 years experience in the assessment of radioactive waste disposal and at the time of this publication is providing assistance internationally in a number of areas relevant to the safety assessment of radioactive waste disposal systems. In countries with small radioactive waste programs, international technology transfer program efforts are often hampered by small budgets, schedule constraints, and a lack of experienced personnel. In an effort to surmount these difficulties, Sandia has developed a system that utilizes a combination of commercially available software codes and existing legacy codes for probabilistic safety assessment modeling that facilitates the technology transfer and maximizes limited available funding. Numerous codes developed and endorsed by the United States Nuclear Regulatory Commission (NRC) and codes developed and maintained by United States Department of Energy are generally available to foreign countries after addressing import/export control and copyright requirements. From a programmatic view, it is easier to utilize existing codes than to develop new codes. From an economic perspective, it is not possible for most countries with small radioactive waste disposal programs to maintain complex software, which meets the rigors of both domestic regulatory requirements and international peer review. Therefore, revitalization of deterministic legacy codes, as well as an adaptation of contemporary deterministic codes, provides a credible and solid computational platform for constructing probabilistic safety assessment models. This document is a reference users guide for the GoldSim/BLT-MS integrated modeling software package developed as part of a cooperative technology transfer project between Sandia National Laboratories and the Institute of Nuclear Energy Research (INER) in Taiwan for the preliminary assessment of several candidate low

Radioactive rare gases emission at underground nuclear explosions

International Nuclear Information System (INIS)

Dubasov, Yu.V.

2016-01-01

The examples of radioactive rare gases emission at underground nuclear explosions conducted in the USSR on the Novaya Zemlya and Semipalatinsk test sites are considered. It is pointed out that in the case of evasive explosion in vertical wells without apparent radioactive gases emission the samples of subsurface gas must contain the traces of radioactive rare gases. Under the inspection of evasive explosion in horizontal workings of rock massif, one should guided by the analysis of atmospheric air samples in the inspected area [ru

INFX GUIDE: DEPARTMENT OF ENERGY BILATERAL AGREEMENTS FOR COOPERATION IN THE FIELD OF RADIOACTIVE WASTE MANAGEMENT (INFX: INTERNATIONAL INFORMATION EXCHANGE)

Energy Technology Data Exchange (ETDEWEB)

Harman, K. M.; Lakey, L. T.; Leigh, I. W.; Jeffs, A. G.

1985-07-01

As the U. S. Department of Energy (DOE) and DOE contractors have increased the magnitude and scope of their cooperative activities with other nations in the nuclear fuel cycle and waste management field, a need has developed for ready sources of information concerning foreign waste management programs, DOE technology exchange policies, bilateral fuel cycle and waste management agreements and plans and activities to implement those agreements. The INFX (International InLormation E~change) Guide is one of a series of documents that have been prepared to provide that information. The INFX Guide has been compiled under the charter of PNL's International Support Office (IPSO) to maintain for DOE a center to collect, organize, evaluate and disseminate information on foreign and international radioactive waste management programs. Because the information in this document is constantly subject to change, the document is assembled in loose-leaf form to accommodate frequent updates.

Development of an application simulating radioactive sources

International Nuclear Information System (INIS)

Riffault, V.; Locoge, N.; Leblanc, E.; Vermeulen, M.

2011-01-01

This paper presents an application simulating radioactive gamma sources developed in the 'Ecole des Mines' of Douai (France). It generates raw counting data as an XML file which can then be statistically exploited to illustrate the various concepts of radioactivity (exponential decay law, isotropy of the radiation, attenuation of radiation in matter). The application, with a spread sheet for data analysis and lab procedures, has been released under free license. (authors)

Competent authority regulatory control of the transport of radioactive material

International Nuclear Information System (INIS)

1987-04-01

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

Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication provides guidance to Member States for the development, or improvement of nuclear security systems and measures for the detection of criminal or unauthorized acts with nuclear security implications involving nuclear and other radioactive material out of regulatory control. It describes the elements of an effective nuclear security detection architecture which is composed of an integrated set of nuclear security systems and measures, and is based on an appropriate legal and regulatory framework for the implementation of the national detection strategy. The publication is an implementing guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, legislative bodies, competent authorities, institutions, and individuals involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control

Radioactive waste management; the realities as against the myths

International Nuclear Information System (INIS)

Williams, I.

1980-01-01

Nuclear power generation is now an essential requirement for the mankind in the current energy difficulties. The problem of radioactive waste management is arousing the opposition, but it must not inhibit the utilization of nuclear energy. Radioactive waste management concerns the whole course from its occurrence to its final disposal. The purpose of the management is then to protect absolutely the human beings of present and future generations from the danger of radioactivity. Radioactive wastes are varied much in their kinds and natures. While the management technology is nearly all established, the amounts of wastes are increasing. The following matters are described. Definition of radioactive waste management, fundamental strategies of the management, kinds of radioactive wastes, the present situation of radioactive waste management, and problems in the management. (J.P.N.)

Preparation of a guide on radioactive waste management

International Nuclear Information System (INIS)

Efremov, G.F.; Pasysaev, V.A.

2000-01-01

There is shown the method on enhancing of radioecological literacy of population including mining regions under the framework of ISTC project development. Authors make a base of necessity of liquidation of radioactive waste on Kazakhstan territory. The recommend some basic types of terminal disposal for that. (author)

Radiation safety in educational, medical and research institutions. Regulatory guide G-121

International Nuclear Information System (INIS)

2000-05-01

This regulatory guide is intended to help educational, medical and research institutions design and implement radiation protection programs that meed regulatory requirements. This guide applied to educational, medical or research institutions that require a licence from the CNSC to posses or use radioactive materials. It describes programs to assure that radioactive materials are used safely during licensed activities. (author)

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Radioactive waste processing method

International Nuclear Information System (INIS)

Kikuchi, Makoto; Kamiya, Kunio; Yusa, Hideo.

1976-01-01

Object: To form radioactive wastes into a pellet-like solid body having high strength. Structure: Liquid waste containing a radioactive material is heated into a powdery body. Granular solid matter such as sand greater in diameter than grain size of the powdery body are mixed into the powdery body, and thereafter the mixture is formed by a granulator into a pellet-like solid body. The thus formed material is introduced into a drum can, into which a thermoplastic material such as asphalt is poured into the can and cooled so that the asphalt is impregnated inside the pellet to obtain a solid having high strength. (Furukawa, Y.)

An experiment on radioactive equilibrium and its modelling using the ‘radioactive dice’ approach

Science.gov (United States)

Santostasi, Davide; Malgieri, Massimiliano; Montagna, Paolo; Vitulo, Paolo

2017-07-01

In this article we describe an educational activity on radioactive equilibrium we performed with secondary school students (17-18 years old) in the context of a vocational guidance stage for talented students at the Department of Physics of the University of Pavia. Radioactive equilibrium is investigated experimentally by having students measure the activity of 214Bi from two different samples, obtained using different preparation procedures from an uraniferous rock. Students are guided in understanding the mathematical structure of radioactive equilibrium through a modelling activity in two parts. Before the lab measurements, a dice game, which extends the traditional ‘radioactive dice’ activity to the case of a chain of two decaying nuclides, is performed by students divided into small groups. At the end of the laboratory work, students design and run a simple spreadsheet simulation modelling the same basic radioactive chain with user defined decay constants. By setting the constants to realistic values corresponding to nuclides of the uranium decay chain, students can deepen their understanding of the meaning of the experimental data, and also explore the difference between cases of non-equilibrium, transient and secular equilibrium.

Transport of proximity nuclear radioactive materials

International Nuclear Information System (INIS)

2010-01-01

This brief publication gives an overview of the international and national regulatory framework for the transport of radioactive substances, outlines progress orientations identified by the French Nuclear Safety Authority (ASN), indicates the parcel classification and shipment radiological criteria, and how to declare events occurring during the transport of radioactive substances, which number to phone in case of a radiological incident. Finally, the role of the ASN and its field of activity in matters of control are briefly presented with a table of its office addresses in France

Preparing regulations for radioactive waste transport

International Nuclear Information System (INIS)

Robles, Fernando

2002-01-01

The article describes the diferent stages in preparing the regulation on safe transport of radioactive materials. The first stage was the support given by the International Atomic Energy Agency in to provide expertise in drafting the national regulation on this matter. The draft is based on the publication from IAEA Regulation on the safe transport of radioactive materials. Also a description of activities made by the Radiation Protection Department of the Energy Directorate of Guatemala is made by the Chief of the Department Dr. Fernando Robles

Radioactive mineral deposits

Energy Technology Data Exchange (ETDEWEB)

1948-01-01

This publication was designed as a guide for uranium and thorium prospectors in Australia. Physical properties, such as color, streak, luster, hardness, fracture, and specific gravity of the uranium and thorium-bearing minerals are summarized and the various methods suitable for detecting radioactivity in minerals are described. Two colored plates show samples of pitchblende (uraninite), autunite, carnotite, monazite, and others of the most important minerals sources of uranium and thorium.

Report of radioactivity survey research in fiscal year 1988

International Nuclear Information System (INIS)

1989-12-01

The National Institute of Radiological Sciences has been surveyed, as part of the radioactivity research project by the Science and Technology Agency, radioactivity levels in the environment and safety analysis for radioactive fallouts associated with nuclear weapons tests since 1959 and effluents from nuclear installations. With a remarkable advent of the peaceful applications of radionuclides, radioactivity in the environment has been becoming a matter of concern for the population in Japan. Radioactivity research is considered to become more important because it may provide clues for the basis of its influences upon the human body and environment. This report gives a survey of the radioactivity research project performed in the fiscal year 1988. The following topics are covered: (1) radioactivity levels and dosimetry in the environment, foods, and human body; (2) radioactivity levels surrounding nuclear installations; (3) services in the Radioactivity Survey Data Center; (4) basic survey of evaluation for the results of radioactivity levels; (5) training of technichians for monitoring environmental radioactivity; and (6) survey research for dosimetry and countermeasures at emergency. (N.K.)

Security of radioactive sources in radiation facilities

International Nuclear Information System (INIS)

2011-03-01

Safety codes and safety standards are formulated on the basis of internationally accepted safety criteria for design, construction and operation of specific equipment, systems, structures and components of nuclear and radiation facilities. Safety codes establish the objectives and set requirements that shall be fulfilled to provide adequate assurance for safety. Safety guides and guidelines elaborate various requirements and furnish approaches for their implementation. Safety manuals deal with specific topics and contain detailed scientific and technical information on the subject. These documents are prepared by experts in the relevant fields and are extensively reviewed by advisory committees of the Board before they are published. The documents are revised when necessary, in the light of experience and feedback from users as well as new developments in the field. In India, radiation sources are being widely used for societal benefits in industry, medical practices, research, training and agriculture. It has been reported from all over the world that unsecured radioactive sources caused serious radiological accidents involving radiation injuries and fatalities. Particular concern was expressed regarding radioactive sources that have become orphaned (not under regulatory control) or vulnerable (under weak regulatory control and about to be orphaned). There is a concern about safety and security of radioactive sources and hence the need of stringent regulatory control over the handling of the sources and their security. In view of this, this guide is prepared which gives provisions necessary to safeguard radiation installations against theft of radioactive sources and other malevolent acts that may result in radiological consequences. It is, therefore, required that the radiation sources are used safely and managed securely by only authorised personnel. This guide is intended to be used by users of radiation sources in developing the necessary security plan for

Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the 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. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

Decommissioning of medical, industrial and research facilities. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the 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. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

Guide book of radioactive wastes collecting. Producers, from collection to storage

International Nuclear Information System (INIS)

2003-01-01

This document, more particularly devoted to radioactive waste producers (except electronuclear industry), defines the technical specifications and the financial conditions relative to the taking over of their wastes by the ANDRA, the French national agency of radioactive wastes. Content: general principles, instructions manual of the taking over demand, practical conditions of wastes collecting, packaging and containers, specifications for each category of waste, particular cases, price table, disputes. (J.S.)

Help guide for the application of regulatory requirements on the transport of radioactive material; Guia de ayuda para la aplicacion de requisitos reglementarios sobr el transporte de material radiactivo

Energy Technology Data Exchange (ETDEWEB)

Martin Rodriguez, S.; Acena Moreno, V.; Zamora Martin, F.; Rubio de Juan, E.

2011-07-01

The regulation of transport of radioactive material by road in Spain refers to compliance with the requirements of the European Agreement concerning the International Carriage of Dangerous Goods by Road (ADR) in force. The structure presented by this legislation, which is international, and the inclusion in it of requirements that apply to other dangerous goods makes it difficult to consult the requirements that specifically apply to the transport of radioactive material. Therefore, the Nuclear Safety Council (CSN) has found it necessary to publish a guide that facilitates users to comply with its provisions and, consequently, this transport security.

The detector for dark matter search

International Nuclear Information System (INIS)

Li Jin

2004-01-01

The dark matter search and dark matter detection is very importance project in Particle Physics, Astrophysics and Cosmology. The paper introduces the current status of the dark matter search in the world and points out that the development of detector with larger scale, lower threshold, very low radioactive background and building of underground laboratory is important developing direction. So far, there is no such detector and underground laboratory in our county. We should change such situation as soon as possible. (authors)

Radioactive effluents, Portsmouth Uranium Enrichment Complex, calendar year 1983

International Nuclear Information System (INIS)

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

1984-03-01

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

Analysis of radioactive-matter interaction near thermodynamical equilibrium states

International Nuclear Information System (INIS)

Damamme, G.

1993-01-01

We study the absorption/emission process of photon by matter in the framework of a radiativo-collisionnal model of atom, a thermodynamical approach being used. The considered matter description is the atomic sphere one. First we give the expression of the balance equation around an equilibrium state. Then we express the atomic populations in function of the characteristics of the radiation and of the free electrons and of their time history. This permit us to interpret the photon balance as being due to true emission/absorption process of photons as well as fluorescence terms, all these processes being affected by relaxation effects. The total energy balance between matter and radiation can also be analyzed in the same way and conduct to introduce one photon effective interactions terms for each radiative proper mode, terms also affected by retardation effects. Such a taking into account of atom populations has no consequence on the radiative flux equation (i.e. the transfer opacity) but can considerably modify the energy balance between matter and radiation. (author). 11 refs., 3 figs

Direct Dark Matter Searches: Status and Perspectives

CERN Multimedia

CERN. Geneva

2016-01-01

There is overwhelming indirect evidence that dark matter exists, however, the dark matter particle has not yet been directly detected in laboratory experiments. In order to be able to identify the rare dark matter interactions with the target nuclei, such instruments have to feature a very low threshold and an extremely low radioactive background. They are therefore installed in underground laboratories to reduce cosmic ray backgrounds. I will review the status of direct dark matter searches and will discuss the perspectives for the future.

Radioactive wastes. Commune convention about the safety of spent fuel management and about the radioactive waste management

International Nuclear Information System (INIS)

Anon.

1997-01-01

This common convention do not give detailed safety standards but general obligations whom objective is the development of a safety culture in the world. It concerns the spent fuels (valuable and valued by the reprocessing) and radioactive wastes (matter without any later use). (N.C.)

Plastic solidification of radioactive wastes

International Nuclear Information System (INIS)

Moriyama, Noboru

1981-01-01

Over 20 years have elapsed after the start of nuclear power development, and the nuclear power generation in Japan now exceeds the level of 10,000 MW. In order to meet the energy demands, the problem of the treatment and disposal of radioactive wastes produced in nuclear power stations must be solved. The purpose of the plastic solidification of such wastes is to immobilize the contained radionuclides, same as other solidification methods, to provide the first barrier against their move into the environment. The following matters are described: the nuclear power generation in Japan, the radioactive wastes from LWR plants, the position of plastic solidification, the status of plastic solidification in overseas countries and in Japan, the solidification process for radioactive wastes with polyethylene, and the properties of solidified products, and the leachability of radionuclides in asphalt solids. (J.P.N.)

Michigan high-level radioactive waste program. Technical progress report for 1985

International Nuclear Information System (INIS)

1986-01-01

In 1985, five crystalline rock formations located in Michigan's Upper Peninsula were under consideration in the regional phase of the Department of Energy's (DOE) search for the site of the nation's second high-level radioactive waste repository. The Michigan Department of Public Health has been designated by the Governor as lead state agency in matters related to high-level radioactive waste (HLRW). Mr. Lee E. Jager, Chief of the Department's Bureau of Environmental and Occupational Health, has been designated as the state contact person in this matter, and the Bureau's Division of Radiological Health, Office of Radioactive Waste Management (ORWM), has been designated to provide staff support. Recognizing that adequate state involvement in the various aspects of the Federal high-level radioactive waste (HLRW) programs would require a range of expertise beyond the scope of any single state agency, Governor Blanchard established the High-Level Radioactive Waste Task Force in 1983. In support of the Task Force efforts concerning the implementation of its change, the Department negotiated and concluded an agreement with the DOE, under which federal funds are provided to support state HLRW activities. This report outlines state activities for the calendar year 1985, funded under that agreement

The basics in transportation of low-level radioactive waste

International Nuclear Information System (INIS)

Allred, W.E.

1998-06-01

This bulletin gives a basic understanding about issues and safety standards that are built into the transportation system for radioactive material and waste in the US. An excellent safety record has been established for the transport of commercial low-level radioactive waste, or for that matter, all radioactive materials. This excellent safety record is primarily because of people adhering to strict regulations governing the transportation of radioactive materials. This bulletin discusses the regulatory framework as well as the regulations that set the standards for packaging, hazard communications (communicating the potential hazard to workers and the public), training, inspections, routing, and emergency response. The excellent safety record is discussed in the last section of the bulletin

Radioactive dumping in the Arctic Ocean

International Nuclear Information System (INIS)

Lamb, J.; Gizewski, P.

1993-01-01

Recent revelations concerning the possible environmental hazards posed by the sunken Soviet nuclear submarine Komsomolets and the disposal of radioactive materials in the Arctic and North Atlantic oceans have generated much controversy and debate. Too often, however, the key scientific and policy issues that the dumping raises are treated as two solitudes. In reality, decisions taken by national governments and international agencies in connection with remediation, regulation, and even research must be based on both science and policy. Indeed, a sound approach to the dumping issue must integrate scientific evidence and policy considerations relating to legal, political, social, and economic matters. Radioactive waste disposal is an exceedingly difficult problem. Information detailing the Soviet Navy's past dumping practices, and increasing awareness of the problems that Russia and other states may encounter in the future disposal of radioactive waste, indicate that the global inventory of radioactive wastes requiring storage and disposal is large and growing

Identification of radioactive sources and devices. Reference manual

International Nuclear Information System (INIS)

2007-01-01

This publication is intended to be a basic guide and not a comprehensive tool kit to identify and provide detailed emergency handling instructions for radioactive sources, devices and transport containers. In addition, this publication helps to identify sources and highlight the risks they present, and provides information on appropriate action. It is a small but significant step in the international community's continuing efforts to strengthen control of radioactive sources and nuclear material, increase safety and security, and thereby make the benefits of radioactive sources ever more broadly accessible. This publication was partly funded through the Nuclear Security Fund established under the Nuclear Security Plan

Bonded carbon or ceramic fiber composite filter vent for radioactive waste

Science.gov (United States)

Brassell, Gilbert W.; Brugger, Ronald P.

1985-02-19

Carbon bonded carbon fiber composites as well as ceramic or carbon bonded ceramic fiber composites are very useful as filters which can separate particulate matter from gas streams entraining the same. These filters have particular application to the filtering of radioactive particles, e.g., they can act as vents for containers of radioactive waste material.

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

Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

International Nuclear Information System (INIS)

2010-01-01

There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

International Nuclear Information System (INIS)

2009-01-01

There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

Artificial radioactivity is fifty: 1934-1984

International Nuclear Information System (INIS)

Amaldi, E.; Biquard, P.; Goldstein, L.

1984-01-01

This book has been published on the occasion of the fiftieth anniversary celebration of the artificial radioactivity discovery; contributions from men who have been near the Joliot at the beginning of the artificial radioactivity, or whose work have been marked by this discovery are gathered in this book. Subjects have been choosed very freely by the authors; that explains their great diversity. The reader will find precious memories from direct witnesses of this great time; he will find also descriptions of the following works; he will even find audacious dreams on matter utilization possibilities, which may rise to-morrow [fr

Radioactive waste management

International Nuclear Information System (INIS)

Kizawa, Hideo

1982-01-01

A system of combining a calciner for concentrated radioactive liquid waste and an incinerator for miscellaneous radioactive solid waste is being developed. Both the calciner and the incinerator are operated by fluidized bed method. The system features the following points: (1) Inflammable miscellaneous solids and concentrated liquid can be treated in combination to reduce the volume. (2) Used ion-exchange resin can be incinerated. (3) The system is applicable even if any final waste disposal method is adopted; calcinated and incinerated solids obtained as intermediate products are easy to handle and store. (4) The system is readily compatible with other waste treatment systems to form optimal total system. The following matters are described: the principle of fluidized-bed furnaces, the objects of treatment, system constitution, the features of the calciner and incinerator, and the current status of development. (J.P.N.)

Research programme on radioactive wastes

International Nuclear Information System (INIS)

Eckhardt, A.; Hufschmid, P.; Jordi, S.; Schanne, M.; Vigfusson, J.

2009-11-01

This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

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

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

Radioactive waste management in Tanzania

International Nuclear Information System (INIS)

Banzi, F.P.; Bundala, F.M.; Nyanda, A.M.; Msaki, P.

2002-01-01

Radioactive waste, like many other hazardous wastes, is of great concern in Tanzania because of its undesirable health effects. The stochastic effects due to prolonged exposure to ionizing radiation produce cancer and hereditary effects. The deterministic effects due to higher doses cause vomiting, skin reddening, leukemia, and death to exposed victims. The aim of this paper is to give an overview of the status of radioactive wastes in Tanzania, how they are generated and managed to protect humans and the environment. As Tanzania develops, it is bound to increase the use of ionizing radiation in research and teaching, industry, health and agriculture. Already there are more than 42 Centers which use one form of radioisotopes or another for these purposes: Teletherapy (Co-60), Brach-therapy (Cs-137, Sr-89), Nuclear Medicine (P-32, Tc-99m, 1-131, 1-125, Ga-67, In-111, Tl-206), Nuclear gauge (Am-241, Cs- 137, Sr-90, Kr-85), Industrial radiography (Am-241, C-137, Co-60, lr-92), Research and Teaching (1-125, Am241/Be, Co-60, Cs-137, H-3 etc). According to IAEA definition, these radioactive sources become radioactive waste if they meet the following criteria: if they have outlived their usefulness, if they have been abandoned, if they have been displaced without authorization, and if they contaminate other substances. Besides the origin of radioactive wastes, special emphasis will also be placed on the existing radiation regulations that guide disposal of radioactive waste, and the radioactive infrastructure Tanzania needs for ultimate radioactive waste management. Specific examples of incidences (theft, loss, abandonment and illegal possession) of radioactive waste that could have led to serious deterministic radiation effects to humans will also be presented. (author)

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the 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. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the 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. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the 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. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Non-destructive nuclear forensics of radioactive samples

Energy Technology Data Exchange (ETDEWEB)

Rogge, R.B. [Canadian Neutron Beam Centre, Chalk River, ON (Canada); Alexander, Q.; Bentoumi, G.; Dimayuga, F. [Atomic Energy of Canada Limited, Chalk River, ON (Canada); Flacau, R. [Canadian Neutron Beam Centre, Chalk River, ON (Canada); Li, G.; Li, L.; Sur, B. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

It is a matter of public safety and security to be able to examine suspicious packages of unknown origin. If the package is radioactive and sealed (i.e., the radioactive materials contained in the package, including their chemical and physical forms, are unknown), there is a significant risk on how to handle the package and eventually safely dispose of its contents. Within the context of nuclear security, nuclear forensics helps address the key issue of identifying the nature and origin of radioactive and nuclear material in order to improve physical protection measures and prevent future theft or diversion of these materials. Nuclear forensics utilizes analytical techniques, destructive and non-destructive, developed for applications related to nuclear fuel cycles. This paper demonstrates the non-destructive examination techniques that can be used to inspect encapsulated radioactive samples. Results of γ spectroscopy, X-ray spectroscopy, neutron imaging, neutron diffraction, and delayed neutron analysis as applied to an examination of sealed capsules containing unknown radioactive materials are presented. The paper also highlights the value of these techniques to the overall nuclear forensic investigation to determine the origin of these unknown radioactive materials. (author)

Soil organic matter

International Nuclear Information System (INIS)

1976-01-01

The nature, content and behaviour of the organic matter, or humus, in soil are factors of fundamental importance for soil productivity and the development of optimum conditions for growth of crops under diverse temperate, tropical and arid climatic conditions. In the recent symposium on soil organic matter studies - as in the two preceding ones in 1963 and 1969 - due consideration was given to studies involving the use of radioactive and stable isotopes. However, the latest symposium was a departure from previous efforts in that non-isotopic approaches to research on soil organic matter were included. A number of papers dealt with the behaviour and functions of organic matter and suggested improved management practices, the use of which would contribute to increasing agricultural production. Other papers discussed the turnover of plant residues, the release of plant nutrients through the biodegradation of organic compounds, the nitrogen economy and the dynamics of transformation of organic forms of nitrogen. In addition, consideration was given to studies on the biochemical transformation of organic matter, characterization of humic acids, carbon-14 dating and the development of modern techniques and their impact on soil organic matter research

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

Low-level radioactive waste treatment technology. Low-level radioactive waste management handbook series

International Nuclear Information System (INIS)

1984-07-01

Each generator of low-level radioactive waste must consider three sequential questions: (1) can the waste in its as-generated form be packaged and shipped to a disposal facility; (2) will the packaged waste be acceptable for disposal; and (3) if so, is it cost effective to dispose of the waste in its as-generated form. These questions are aimed at determining if the waste form, physical and chemical characteristics, and radionuclide content collectively are suitable for shipment and disposal in a cost-effective manner. If not, the waste management procedures will involve processing operations in addition to collection, segregation, packaging, shipment, and disposal. This handbook addresses methods of treating and conditioning low-level radioactive waste for shipment and disposal. A framework is provided for selection of cost-effective waste-processing options for generic categories of low-level radioactive waste. The handbook is intended as a decision-making guide that identifies types of information required to evaluate options, methods of evaluation, and limitations associated with selection of any of the processing options

Centennial of the discovery of radioactivity - 1896-1898/1996-1998

International Nuclear Information System (INIS)

Bimbot, R.; Casse, M.

2009-01-01

This document summarizes the impacts that the discovery of radioactivity in 1896 has had on the scientific world: 1 - historical aspects (biographies of Henri Becquerel, Pierre Curie and Marie Curie-Sklodowska; context; history of radioactivity discovery; examples of radioactive half-lives); 2 - development of matter sciences (radiochemistry; nuclear and particle physics; nuclear and particle astrophysics); 3 - dating and energy applications: isotope dating; power generation (fission, fusion, nuclear reactor components, reactor types, radioactive wastes); 4 - biological, medical and agronomic applications (biological researches, medical diagnosis, clinical exploration and therapies, man's exposure to ionizing radiations, natural and artificial radioactivity, sources, doses and radiation effects, radioactivity in the Saclay area, radioactivity changes with places, research tool in plants biology and agronomic. Reprints of original communications presented by H. Becquerel and P. and M. Curie at the sessions of the French Academy of Sciences between 1896 and 1906, as well as the talks given at the Academy for the funerals of H. Becquerel, are attached to the document. (J.S.)

Neutronic measurements of radioactive waste; Les mesures neutroniques des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Perot, B

1997-12-31

This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author).

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.)

RADWASS update. Radioactive Waste Safety Standards Programme

International Nuclear Information System (INIS)

Delattre, D.

2000-01-01

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

Radiological design guide

International Nuclear Information System (INIS)

Evans, R.A.

1994-01-01

The purpose of this design guide is to provide radiological safety requirements, standards, and information necessary for designing facilities that will operate without unacceptable risk to personnel, the public, or the environment as required by the US Department of Energy (DOE). This design guide, together with WHC-CM-4-29, Nuclear Criticality Safety, WHC-CM-4-46, Nonreactor Facility Safety Analysis, and WHC-CM-7-5, Environmental Compliance, covers the radiation safety design requirements at Westinghouse Hanford Company (WHC). This design guide applies to the design of all new facilities. The WHC organization with line responsibility for design shall determine to what extent this design guide shall apply to the modifications to existing facilities. In making this determination, consideration shall include a cost versus benefit study. Specifically, facilities that store, handle, or process radioactive materials will be covered. This design guide replaces WHC-CM-4-9 and is designated a living document. This design guide is intended for design purposes only. Design criteria are different from operational criteria and often more stringent. Criteria that might be acceptable for operations might not be adequate for design

Ionizing radiation sources. Ionizing radiation interaction with matter

International Nuclear Information System (INIS)

Popits, R.

1976-01-01

Fundamentals of nuclear physics are reviewed under the headings: obtaining of X-rays and their properties; modes of radioactive decay of natural or man-made radionuclides; radioactive neutron sources; nuclear fission as basis for devising nuclear reactors and weapons; thermonuclear reactions; cosmic radiation. Basic aspects of ionizing radiation interactions with matter are considered with regard to charged particles, photon radiation, and neutrons. (A.B.)

Nuclear plant refurbishment calls for patience. [Construction of radioactive effluent plant

Energy Technology Data Exchange (ETDEWEB)

Henly, Anna

1989-08-01

All nuclear power plants produce a small quantity of liquid effluent from wash hand basins, showers and surface drains on the site. The effluent is termed low-level radioactive waste and under the 'Radioactive Substances Act' can be discharged into estuaries or the sea. Before a controlled discharge can be made the effluent has to be chemically treated and have any radioactive particulate matter removed. The replacing of the radioactive effluent plant at the Berkeley nuclear power station in the United Kingdom is described, with particular reference to the vigorous safety standards and quality assurance programme operated by the Central Electricity Generating Board. (author).

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Radioactive waste management: a utility view

International Nuclear Information System (INIS)

Draper, E.L.

1982-01-01

The management of radioactive waste continues to be a matter of public concern and discussion. There is broad agreement among members of the technical community that the various types of waste radioactive species can be managed without jeopardizing public health and safety. Despite this consensus, one of the major reasons cited by opponents of commercial nuclear power for their opposition is the lack of a fully deployed waste management program. Such a program has been suggested but implementation is not yet complete. It is essential that a program be undertaken so as to dispel the impression that past inaction on waste disposal represents an inability to deal safely with wastes

The radiation protection and the radioactive wastes management; La radioprotection et la gestion des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Servais, F. [CHR Hopital de Warquignies, Service de Medecine Nucleaire (Belgium); Woiche, Ch. [Universite Libre de Bruxelles, Service Interne et de Prevention et Protection (Belgium); Hunin, Ch. [Agence Federale de Controle Nucleaire, Service Controle Etablissements Classes, Brexelles (Belgium)] [and others

2003-07-01

This chapter concerns the radiation protection in relation with the radioactive waste management. Three articles make the matter of this file, the management of radioactive medical waste into hospitals, a new concept of waste storage on site, the protection devices on the long term with some lessons for the radioactive waste management. (N.C.)

The IAEA radioactive waste safety standards programme

International Nuclear Information System (INIS)

Tourtellotte, James R.

1995-01-01

The IAEA is currently reviewing more than thirty publications in its Safety Series with a view toward consolidating and organizing information pertaining to radioactive waste. the effort is entitled Radioactive Waste Safety Standards programme (RADWASS). RADWASS is a significant undertaking and may have far reaching effects on radioactive waste management both in the international nuclear community and in individual nuclear States. This is because IAEA envisions the development of a consensus on the final document. In this circumstance, the product of RADWASS may ultimately be regarded as an international norm against which future actions of Member States may be measured. This program is organized in five subjects: planning, pre-disposal, disposal, uranium and thorium waste management and decommissioning, which has four levels: safety fundamentals, safety standards, safety guides and safety practices. (author)

Guide to the declaration procedure and coding system for criteria concerning significant events related to safety, radiation protection or the environment, applicable to basic nuclear installations and the transport of radioactive materials

International Nuclear Information System (INIS)

Lacoste, Andre-Claude

2005-01-01

This guide notably contains various forms associated with the declaration of significant events, and explanations to fill them in: significant event declaration form for a basic nuclear installation, significant event declaration form for radioactive material transport, significant event report for a basic nuclear installation, significant event report for radioactive material transport, declaration criteria for significant events related to the safety of non-PWR basic nuclear installations, declaration criteria for significant events related to PWR safety, significant events declared further to events resulting in group 1 unavailability and non-compliance with technical operating specifications, declaration criteria for significant events concerning radiation protection for basic nuclear installations, declaration criteria for significant events concerning environmental protection, applicable to basic nuclear installations, and declaration criteria for significant events concerning radioactive material transport

Proton radioactivity lifetimes using Skyrme interactions

International Nuclear Information System (INIS)

Routray, T.R.; Tripathy, S.K.; Mishra, Abhishek; Basu, D.N.

2011-01-01

The phenomena of proton radioactivity is recent and has been possible with the advent of the radioactive ion beams facilities. The neutron deficient nuclei lying above the proton drip line has positive Q values for protons and are spontaneous proton emitters. This limits the possibilities of the creation of ever more exotic nuclei in the proton rich side of the β stability valley. Limited number of works have been done in calculating the half lives of proton emitting nuclei using different models. But calculation of lifetimes of the proton emitting nuclei using Skyrme interaction has not yet been reported. More than 110 Skyrme sets are available, constructed for different purposes, all having the common feature of giving finite nuclei ground state properties and saturation conditions in nuclear matter. Skyrme sets constructed in the late 90's, particularly the construction of SLy sets and others Skyrme sets developed thereafter, have additional care in constraining the parameters for applications to nuclear matter under extreme conditions. Stone et al. have analyzed the Skyrme sets on the basis of available constraints and have sorted out finally 27 Skyrmes sets which can be admitted for calculation of isospin rich dense nuclear matter. The objective of the work is to examine the predictions of the Skyrme sets on the half lives of the proton emitters

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

California's response to the Low-Level Radioactive Waste Policy Act of 1980: policy and progress

International Nuclear Information System (INIS)

Pasternak, A.D.

1985-01-01

The public and private corporations and institutions in California that use radioactive materials and generate low-level radioactive waste have played a major role in shaping and guiding California's response to the federal Low-Level Radioactive Waste Policy Act of 1980. Working together as the California Radioactive Materials Management Forum (CAL RAD FORUM), these organizations carry out legislative and public education programs with the objective of establishing, in California, a low-level radioactive waste disposal facility and maintaining access to existing disposal facilities in other states until the California facility is licensed and operating

Legal and regulator framework of radioactive waste

International Nuclear Information System (INIS)

Chavez Cassanello, Griselda; Mels Siningen, Celeste; Reina, Mariana; Vega, Hernan

2009-01-01

The present work intends to develop the legislative and regulatory framework in the matter of radioactive waste. The legal frame of the radioactive waste conformed by the National Constitution, the treaties and conventions, laws and decrees and regulatory norm in Argentine . The subject is approached from the international point of view considering the slogan of 36 The Annual Meeting of the Association Argentine de Nuclear Technology: 'The Nuclear Energy in the Present World'. This work also contains a special paragraph dedicated to the analysis of practical cases related to the subject and the activity of the National Commission of Atomic Energy. (author)

Physical chemistry characterization of soils of the Storage Center of Radioactive Wastes

International Nuclear Information System (INIS)

Hernandez T, U. O.; Fernandez R, E.; Monroy G, F.; Anguiano A, J.

2011-11-01

Any type of waste should be confined so that it does not causes damage to the human health neither the environment and for the storage of the radioactive wastes these actions are the main priority. In the Storage Center of Radioactive Wastes the radioactive wastes generated in Mexico by non energy applications are storage of temporary way. The present study is focused in determining the physical chemistry properties of the lands of the Storage Center of Radioactive Wastes like they are: real density, ph, conductivity percentage of organic matter and percentage of humidity. With what is sought to make a characterization to verify the reaction capacity of the soils in case of a possible flight of radioactive material. The results show that there are different density variations, ph and conductivity in all the soil samples; the ph and conductivity vary with regard to the contact time between the soil and their saturation point in water, for the case of the density due to the characteristics of the same soil; for what is not possible to establish a general profile, but is necessary to know the properties of each soil type more amply. Contrary case is the content of organic matter and humidity since both are in minor proportions. (Author)

Radioactive wastes: underground laboratories implantation

International Nuclear Information System (INIS)

Bataille, Ch.

1997-01-01

This article studies the situation of radioactive waste management, more especially the possible storage in deep laboratories. In front of the reaction of public opinion relative to the nuclear waste question, it was essential to begin by a study on the notions of liability, transparence and democracy. At the beginning, it was a matter of underground researches with a view to doing an eventual storage of high level radioactive wastes. The Parliament had to define, through the law, a behaviour able to come to the fore for anybody. A behaviour which won recognition from authorities, from scientists, from industrial people, which guarantees the rights of populations confronted to a problem whom they were not informed, on which they received only few explanations. (N.C.)

Natural radioactivity of the rocks from the Moon and planets

Energy Technology Data Exchange (ETDEWEB)

Surkov, Yu.A. (AN SSSR, Moscow. Inst. Geokhimii i Analiticheskoj Khimii)

1982-01-01

Tha data on natural radioactivity of rocks (U, Th and K contents) from the Moon, Venus and Mars obtained by means of cosmic means are analyzed. The Moon rock radioactivity has been measured in situ (from orbital vehicles) as well as in the samples of lunar material delivered to the Earth and as for Venus and Mars rocks - by landing vehicles. It has been found that the main specific feature of the Moon and the Earth group planets is the presence of two geomorphological types of the structure of their surface composed by two different types of the matter. The ancient continent regions are made up by feldspar rock - gabbroanorthosite at the Moon (and possibly at the Mars) and granite-metamorphic at the Earth (and possibly at the Venus). The younger ''marine'' regions are composed by basalt rock. The presence at the Moon of two types of crust (marine and continental ones) having a different nature is clearly reflected on the Moon radioactivity map where marine regions (15% of the total surface) which have high radioactivity and continental regions with a relatively low radioactivity can be seen. The discovery of rocks on the Venus surface highly enriched by U, Th and K speaks of their melting from the primary matter in the depth of the Earth. The Marsian rock by the natural radioelement content is close to igneous rocks of the Earth crust of the basic composition and lunar marine basalts.

Natural radioactivity of the rocks from the Moon and planets

International Nuclear Information System (INIS)

Surkov, Yu.A.

1982-01-01

Tha data on natural radioactivity of rocks (U, Th and K contents) from the Moon, Venus and Mars obtained by means of cosmic means are analyzed. The Moon rock radioactivity has been measured in situ (from orbital vehicles) as well as in the samples of lunar material delivered to the Earth and as for Venus and Mars rocks - by landing vehicles. It has been found that the main specific feature of the Moon and the Earth group planets is the presence of two geomorphological types of the structure of their surface composed by two different types of the matter. The ancient contineent regions are made up by feldspar rock - gabbroanorthosite at the Moon (and possibly at the Mars) and granite-metamorphic at the Earth (and possibly at the Venus). The younger ''marine'' regions are composed by basalt rock. The presence at the Moon of two types of crust (marine and continental ones) having a different nature is clearly reflected on the Moon radioactivity map where marine regions (15% of the total surface) which have high radioactivity and continental regions with a relatively low radioactivity can be seen. The discovery of rocks on the Venus surface highly enriched by U, Th and K speaks of their melting from the primary matter in the depth of the Earth. The Marsian rock by the natural radioelement content is close to igneous rocks of the Earth crust of the basic composition and lunar marine basalts

Accumulation of radioactive iron in marine organisms

International Nuclear Information System (INIS)

Tateda, Yuzuru

1985-01-01

The accumulation and excretion of radioactive iron in some marine organisms was investigated by radio-tracer experiments. The concentration factor, biological half-life, distribution in body, and combining form in some organs, are compared and discussed between mollusks and fishes. The results obtained are: 1) The concentration factor of seaweed was higher than those of worm and fish in uptake from seawater. Abalone showed a higher concentration factor than fish. 2) The first component of excretion curve was small in case of a longer period of uptake from seawater. 3) Abalone and octopus showed a higher radioactivity retention than flounder and black-fish. 4) The fish fed labelled seaweed showed a lower radioactivity retention than fish fed labelled worm. 5) The fish fed radioisotopes with prey showed a higher radioactivity retention than fish fed labelled prey. 6) Biological half-lives were longer in abalone and octopus than in fishes. The biological half-lives of radioactive iron in fishes varied according to the uptake modes. 7) The distribution ratio of radioactive iron in organisms were large in the liver and degestive tract. 8) The GFC profile of 59 Fe in some organs of organisms showed combining form of same molecular weight of proteinous matter. (author)

Inventory of radioactive waste disposals at sea

International Nuclear Information System (INIS)

1999-08-01

The IAEA was requested by the Contracting Parties to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (London Convention 1972) to develop and maintain an inventory of radioactive material entering the marine environment from all sources. The rationale for having such an inventory is related to its use as an information base with which the impact of radionuclides from different sources entering the marine environment can be assessed and compared. To respond to the request of the London Convention, the IAEA has undertaken the development of the inventory to include: disposal at sea of radioactive wastes, and accidents and losses at sea involving radioactive materials. This report addresses disposal at sea of radioactive waste, a practice which continued from 1946 to 1993. It is a revision of IAEA-TECDOC-588, Inventory of Radioactive Material Entering the Marine Environment: Sea Disposal of Radioactive Waste, published in 1991. In addition to the data already published in IAEA-TECDOC-588, the present publication includes detailed official information on sea disposal operations carried out by the former Soviet Union and the Russian Federation provided in 1993 as well as additional information provided by Sweden in 1992 and the United Kingdom in 1997 and 1998

Radioactivity and health

International Nuclear Information System (INIS)

Stannard, J.N.; Baalman, R.W. Jr.

1988-01-01

This book details the knowledge of the biological effects of ionizing radiation from the discovery of radium to about 1980. Research findings and conclusions are presented largely as the investigators saw and reported them except where the work under discussion was markedly iconoclastic and obviously wrong according to the author's comments. Findings from over 100 personal interviews and literature searches including unpublished or little-known materials are summarized. The material in the book is divided into six sections. The first section deals with naturally occurring radioactive elements. The next section covers material on man-made radioisotopes. Inhalation toxicology (radioactive dusts and particles and respirable gases) is the subject of Section 3. Section 4 deals with environmental matters - radioecology, fallout from nuclear weapons tests, transport of radionuclides, testing and standard settings, and Section 5 consists of information on laboratory and field instrumentation. The development of the therapy for exposure and of nuclear medicine is traced in the final section

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.)

Mind Over Matter: Methamphetamine

Science.gov (United States)

... Teaching Guide and Series / Methamphetamine Mind Over Matter: Methamphetamine (Meth) Print Order Free Publication in: English Spanish ... paranoia, aggressiveness, and hallucinations. The Brain's Response to Methamphetamine Hi, my name's Sara Bellum. Welcome to my ...

Protective action guides: theory and application lessons from the Three Mile Island Accident

International Nuclear Information System (INIS)

Shleien, B.

1980-01-01

Protective action guides define the projected dose commitment to individuals in the general population that warrants protective action following the release of radioactive materials. Protective action would be warranted if the expected individual dose reduction is not offset by negative social, economic or health effects. Proposed or recommended protective action guides are available for the accidental radioactive contamination of human food and animal feeds, contamination of drinking water, evacuation and shelter, and administration of thyroid-blocking agents in a radiation emergency. This presentation discusses 1) the bases and status of the guides, 2) their interpretation and use, and 3) problems that were encountered in their interpretation. The available protective action guides proved effective during a nuclear accident emergency in protecting the public's health, in preventing unnecessary economic loss, and in diminishing social disruption. (author)

Measurement and analysis of radioactive substances; Mesure et analyse de substances radioactives

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

The discovery of radioactivity: a bend in sciences history

International Nuclear Information System (INIS)

Dautray, R.

1997-01-01

One hundred years after the discovery of radioactivity, it is possible to see what are the consequences of this discovery for the science. Four consequences are studied in this article: the acquisition of a new knowledge about matter and universe. Secondly, the observation that the radioactivity has given a clock of world history and open to us the past and how this past forged the present world. Thirdly, the fact that radioactivity gave tracers, markers which allow to sound the internal structure of the human body as well as these one of earth and solar system and to unveil the mechanisms. The fourth consequence, is all the applications, electro-nuclear energy, national defence, nuclear medicine. (N.C.)

Colloid Facilitated Transport of Radioactive Cations in the Vadose Zone: Field Experiments Oak Ridge

Energy Technology Data Exchange (ETDEWEB)

James E. Saiers

2012-09-20

The overarching goal of this study was to improve understanding of colloid-facilitated transport of radioactive cations through unsaturated soils and sediments. We conducted a suite of laboratory experiments and field experiments on the vadose-zone transport of colloids, organic matter, and associated contaminants of interest to the U.S. Department of Energy (DOE). The laboratory and field experiments, together with transport modeling, were designed to accomplish the following detailed objectives: 1. Evaluation of the relative importance of inorganic colloids and organic matter to the facilitation of radioactive cation transport in the vadose zone; 2. Assessment of the role of adsorption and desorption kinetics in the facilitated transport of radioactive cations in the vadose zone; 3. Examination of the effects of rainfall and infiltration dynamics and in the facilitated transport of radioactive cations through the vadose zone; 4. Exploration of the role of soil heterogeneity and preferential flow paths (e.g., macropores) on the facilitated transport of radioactive cations in the vadose zone; 5. Development of a mathematical model of facilitated transport of contaminants in the vadose zone that accurately incorporates pore-scale and column-scale processes with the practicality of predicting transport with readily available parameters.

Code of practice for the design of laboratories using radioactive substances for medical purposes

International Nuclear Information System (INIS)

1981-01-01

This Code has been prepared to supplement the radioactive substances acts and regulations implemented in Australia. It is intended as a guide to safe practices but is not legislation. Areas covered include siting, layout, surface finishes, laboratory furniture and fittings, ventilation, containment and release of airborne effluent and storage of radioactive substances

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

International Nuclear Information System (INIS)

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

2003-01-01

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

Condensed matter physics

CERN Document Server

Isihara, A

2007-01-01

More than a graduate text and advanced research guide on condensed matter physics, this volume is useful to plasma physicists and polymer chemists, and their students. It emphasizes applications of statistical mechanics to a variety of systems in condensed matter physics rather than theoretical derivations of the principles of statistical mechanics and techniques. Isihara addresses a dozen different subjects in separate chapters, each designed to be directly accessible and used independently of previous chapters. Topics include simple liquids, electron systems and correlations, two-dimensional

Natural radioactivity at Podravina gas fields

International Nuclear Information System (INIS)

Kovac, J.; Marovic, G.

2006-01-01

In Croatia, natural gas is an important source of energy, where its use exceeds other sources by one third. Composed primarily of the methane, natural gas from Croatian Podravina gas fields, beside other impurities, contains small amounts of radioactive elements. At Gas Treatment Plant (GTP) Molve, technological procedures for purification of natural gas and its distribution are performed. With yearly natural gas production of 3.5 109 m3 GTP Molve is major Croatian energy resource. Its safety and environment impact is matter of concern. Using different radioactivity measuring techniques the exposure of population to ionizing radiation were calculated at Central Natural Gas Station Molve and the underground wells. The measurement techniques included in-situ gamma spectrometric measurements, from which contribution to absorbed dose of the natural radionuclide in soil were calculated. Exposure dose measurements were performed using T.L.-dosimeters, and L.A.R.A. electronic dosimeters as well as field dose rate meter. Comparing used different radioactivity measuring methods, the correlations have been calculated. (authors)

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

International Nuclear Information System (INIS)

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

1991-12-01

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

[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.)

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

Dumping of low-level radioactive waste in the deep ocean

International Nuclear Information System (INIS)

Templeton, W.L.

1980-01-01

Two international agreements relate to the dumping of packaged radioactive waste into the oceans - the Convention on the Prevention of Marine Pollution by Dumping Wastes and Other Matter of 1972 (London Convention) and the Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste of 1977 under the Organization for Economic Co-operation and Development (OECD). The International Atomic Energy Agency was given the responsibility to define high-level radioactive wastes which are unsuitable for dumping in the oceans and to make recommendations for the dumping of other radioactive wastes. A revised Definition and Recommendations was submitted and accepted by the London Convention. This paper reviews the technical basis for the Definition and describes how it has been applied to the radiological assessment of the only operational dumping site in the North East Atlantic

Manual of respiratory protection against airborne radioactive materials

International Nuclear Information System (INIS)

Caplin, J.L.; Held, B.J.; Catlin, R.J.

1976-10-01

The manual supplements Regulatory Guide 8.15, ''Acceptable Programs for Respiratory Protection''. It provides broad guidance for the planned use of respirators to protect individuals from airborne radioactive materials that might be encountered during certain operations. The guidance is intended for use by management in establishing and supervising programs and by operating personnel in implementing programs. Guidance is primarily directed to the use of respirators to prevent the inhalation of airborne radioactive materials. Protection against other modes of intake (e.g., absorption, swallowing, wound injection) is, in general, not covered nor is the use of protective equipment for head, eye, or skin protection

Regulatory inspection of nuclear facilities and enforcement by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on the inspection of nuclear facilities, regulatory enforcement and related matters. The objective is to provide the regulatory body with a high level of confidence that operators have the processes in place to ensure compliance and that they do comply with legal requirements, including meeting the safety objectives and requirements of the regulatory body. However, in the event of non-compliance, the regulatory body should take appropriate enforcement action. This Safety Guide covers regulatory inspection and enforcement in relation to nuclear facilities such as: enrichment and fuel manufacturing plants; nuclear power plants; other reactors such as research reactors and critical assemblies; spent fuel reprocessing plants; and facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Section 2 sets out the objectives of regulatory inspection and enforcement. Section 3 covers the management of regulatory inspections. Section 4 covers the performance of regulatory inspections, including internal guidance, planning and preparation, methods of inspection and reports of inspections. Section 5 deals with regulatory enforcement actions. Section 6 covers the assessment of regulatory inspections and enforcement activities. The Appendix provides further details on inspection areas for nuclear facilities

Applicant's guide related to requests of shipping approval and of acceptance of parcel models or radioactive products aimed at civilian use transported on public road - Guide nr 7 - Index 0, release of the 07/04/2009

International Nuclear Information System (INIS)

2009-01-01

This guide presents the recommendations made by the ASN to applicants in order to facilitate approval requests and shipping approvals related to the transportation of radioactive products. After a recall of the legal context, these recommendations address the documents to be provided in support of an approval request or of a shipping approval, the content of the safety file, the instruction delay, the approval certificate, and changes brought to the parcel model. Appendices contain issues raised by expertise based on experiences, the European PDSR (Package Design Safety Report), and a model for the elaboration of a certificate project

Examination advice of the location-independent Environmental-impact report and advice-direction guides for the location-dependent environmental-impact report concerning storage and processing of radioactive waste

International Nuclear Information System (INIS)

1986-01-01

This document is the examination advice made by the Provisional Committee for the environmental-impact reporting (VCmer) in view of the decision-making in behalf of which the location-independent environmental-impact report (MER) has been drawn up. Besides the examination by the VCmer of the location-independent MER in accordance with article 41z, part 1 and 2, this document covers an advice for direction guides for the, still to be drawn up, location-dependent MER on the storage and processing of radioactive wastes produced in the Netherlands, in accordance with article 41n, part 1 of the enactment m.e.r. The MER has been drawn up in behalf of the decision-making about location, design and construction of an aboveground, temporal storage of radioactive waste for the coming 50-100 years. In the MER two scenarios are distinguished: scenario 1 in fact reflects the actual situation in which, besides the amount of low- and medium-level radioactive waste, the high-level radioactive waste from the two nuclear power plants in the Netherlands have to be taken into account. Scenario 2 includes, besides the waste production of scenario 1, an extension with regard to the waste which would be produced in a 30-year operation time of a, still to be isntalled, nuclear power of 2000 MWe, to be increased up to 4000 MWe eventually. In this scenario finally about three quarter of the total volume of all radioactive waste would be produced by nuclear power plants. In that case emphasis will lay upon an installation which in particular has to be appropriate for a longtime, be it still temporary, storage of radioactive waste originating, largely, from the new nuclear power plant to be build in the Netherlands. (author)

Completion of the radioactive materials packaging handbook

International Nuclear Information System (INIS)

Shappert, L.B.

1998-01-01

'The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance', which will serve as a replacement for the 'Cask Designers Guide'(1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US DOE and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials. Even though the Handbook is concerned with both small and large packagings, most of the emphasis is placed on large packagings that are capable of transporting fissile, radioactive sources (e.g. spent fuels). The safety analysis reports for packagings (SARPs) must address the widest range of technical topics in order to meet United States and/or international regulations, all of which are covered in the Handbook. One of the primary goals of the Handbook is to provide information which would guide designers of radioactive materials packages to make decisions that would most likely be acceptable to regulatory agencies during the approval process of the packaging. It was therefore important to find those authors who not only were experts in one or more of the areas that are addressed in a SARP, but who also had been exposed to the regulatory process or had operational experience dealing with a wide variety of package types. Twenty-five such people have contributed their time and talents to the development of this document, mostly on a volunteer basis

Security of radioactive sources and materials

International Nuclear Information System (INIS)

Rodriguez, C.; D'Amato, E.; Fernandez Moreno, S.

1998-01-01

The activities involving the use of radiation sources and radioactive materials are subject to the control of the national bodies dedicated to the nuclear regulation. The main objective of this control is to assure an appropriate level of radiological protection and nuclear safety. In Argentina, this function is carried out by the 'Nuclear Regulatory Authority' (ARN) whose regulatory system for radiation sources and radioactive materials comprises a registration, licensing and inspection scheme. The system is designed to keep track of such materials and to allow taking immediate corrective actions in case some incident occurs. Due to the appearance of a considerable number of illicit traffic events involving radiation sources and radioactive materials, the specialized national and international community has begun to evaluate the adoption of supplementary measures to those of 'safety' guided to its prevention and detection (i.e. 'security measures'). This paper presents a view on when the adoption of complementary 'security' measures to those of 'safety' would be advisable and which they would be. This will be done through the analysis of two hypothesis of illicit traffic, the first one with sources and radioactive materials considered as 'registered' and the second, with the same materials designated as 'not registered'. It will also describe succinctly the measures adopted by the ARN or under its analysis regarding the 'security' measures to sources and radioactive materials. (author)

Completion of the Radioactive Materials Packaging Handbook

International Nuclear Information System (INIS)

Shappert, L.B.

1998-02-01

The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance, which will serve as a replacement for the Cask Designers Guide (Shappert, 1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US Department of Energy (DOE) and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials

Medical and biohazardous waste generator's guide: Revision 1

International Nuclear Information System (INIS)

1994-09-01

This Guide describes the procedures required to comply with all federal and state laws and regulations and Lawrence Berkeley Laboratory (LBL) policy applicable to medical and biohazardous waste. The members of the LBL Biological Safety Subcommittee participated in writing these policies and procedures. The procedures and policies in this Guide apply to LBL personnel who work with infectious agents or potentially infectious agents, publicly perceived infectious items or materials (e.g., medical gloves, culture dishes), and sharps (e.g., needles, syringes, razor blades). If medical or biohazardous waste is contaminated or mixed with a hazardous chemical or material, with a radioactive material, or with both, the waste will be handled in accordance with the applicable federal and State of California laws and regulations for hazardous, radioactive, or mixed waste

Radioactivity in a mountain ecosystem: the Haut Bassin du Var

International Nuclear Information System (INIS)

2002-01-01

After the Chernobyl accident, the IPSN realized a study of the radioactive fallout in the mountain area of the Var (France). Today the main radionuclides are the cesium 134 and 137, others disappeared because of their short half-life. In this paper, the artificial radioactivity of soils and sediments is concerned. The study shows a concentration of the contamination in some specific areas, especially in soils abounding in organic matter. The dose measured can not lead to significant exposures. (A.L.B.)

Summary of the Law relating to Atomic Energy and Radioactive Subtances as at March 1979

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1979-01-01

This Note contains summaries of new laws and regulations on atomic energy and radioactive substances and amendments made to previous ones in the United Kingdom as at March 1979, including international regulations and agreements. New materials referred to includes the Nuclear Installations (Excepted Matter) Regulations 1978, the Medicines (Radioactive Substances) Order 1978, the Medicines (Committee on Radiation from Radioactive Medicinal Products) Order 1978 and the Medicines (Administration of Radioactive Substances) Regulations 1978. The Note also reproduces other amendments in nuclear legislation, already referred to in a previous Note dated March 1978. (NEA) [fr

Application of international maritime protection conventions to radioactive pollution

International Nuclear Information System (INIS)

Stein, R.M.; Walden, R.M.

1975-01-01

The application of international maritime protection conventions to radioactive pollution is discussed with particular emphasis on the 1972 London Convention on prevention of marine pollution by dumping of wastes and other matter. Under that Convention, wastes are divided into three categories according to their radioactivity. High level wastes, whose dumping is prohibited, and low level wastes which require a special dumping permit are studied on the basis of definitions established by the International Atomic Energy Agency. Mention is made of the IAEA-recommended procedures for issue of the specific dumping as well as of the exceptions provided for ships and aircraft enjoying State immunity and cases of force majeure or emergencies. Also dealt with are the other international Conventions applying to prevention of radioactive marine pollution [fr

Observation of environmental radioactivity at definite time and definite point

International Nuclear Information System (INIS)

Inokoshi, Yukio; Fukuchi, Ryoichi; Irie, Takayuki; Hosoda, Nagako; Okano, Yasuhiro; Shindo, Koutaro

1990-01-01

The measurement of environmental radioactivity in Tokyo Metropolis was carried out. The objects of measurement were rainwater, atmospheric floating dusts, spatial dose and the activated sludge in sewage treatment plants. Rainwater, atmospheric floating dusts and spatial dose were analyzed mainly considering radioactive fallout, and activated sludge was analyzed mainly considering radioactive medical matters. For the analysis of nuclides, a Ge(Li) semiconductor detector was used, and spatial dose rate was measured with a DBM type dose rate meter. In activated sludge, the nuclides used for radioactive medicines were found, but in rainwater, atmospheric floating dusts and spatial dose, particular abnormality was not found. The objective of this investigation is to collect over long period at definite time and definite points the data on environmental radioactivity in Tokyo, thus to grasp the level of normal values, and in abnormal case, to clarify the cause and to evaluate the exposure dose. The instruments used, the method of measuring each object and the results are reported. (K.I.)

Contents of management plans for incidents and accidents involving the transport of radioactive substances. Guide no. 17, Version of 22/12/2014

International Nuclear Information System (INIS)

2014-01-01

This guide presents the essential topics to be developed in a management plan for incidents and accidents involving the transport of radioactive substances for civil use. It does not aim to be exhaustive and could be added to by each party involved in the transport, who can make the necessary adaptations and additions, taking account of the particularities of its shipments and its organisation, as well as those of the company or group to which it belongs. The radioactive substances transport incident and accident management plan is a document comprising a descriptive part and an operational part. It presents the overall response of the party involved in the transport operation to an incident or accident situation concerning one of its shipments and the steps it intends to make in order to support the authorities in charge of this situation, in the best possible conditions. This response is designed to cover the cases of incidents or accidents whether or not they lead to a radiological emergency situation. The guide exclusively concerns: - road transport; - rail transport; - the 'road' and 'rail' parts of multimodal transport operations. The case of an incident or an accident occurring during a particular stop such as a transit site, in a transhipment area (port, airport, railway station, etc.), or in a transport infrastructure, is also covered by the radioactive substances transport incident and accident management plan, which then supports the entities in charge of managing this situation (operator of the transhipment area or the transport infrastructure and - as applicable - their supervisory authorities). The level of risk associated with transport incidents and accidents varies widely, according to the nature and quantities of the materials being carried, the number of shipments made and the package model used. The incident and accident management plan must therefore be tailored to the specific nature of the shipments by the party concerned. The radioactive

Radioactive waste management

International Nuclear Information System (INIS)

Anon.

1988-01-01

The dossier published in this issue deals with all matters relating to radioactive waste management. It describes in detail the guidelines implemented by France in this field and provides a general overview of actions carried out at international level. The articles are assembled in several chapters, treating the following subjects: I. Upstream storage management. II. Storage (surface and underground). III. Research to back up the management program. There then follows a description of various processes and equipment developed by research laboratories and industrialists to provide, at the different stages, a number of operations required by the management programs [fr

Radioactive sealed sources production process for industrial radiography

International Nuclear Information System (INIS)

Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S.

2017-01-01

providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

Radioactive sealed sources production process for industrial radiography

Energy Technology Data Exchange (ETDEWEB)

Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: hobeddaniel@gmail.com, E-mail: jrcamara@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energética s e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

Benefits of standard format and content for approval of packaging for radioactive material

International Nuclear Information System (INIS)

Pstrak, D.; Osgood, N.

2004-01-01

The U.S. Nuclear Regulatory Commission (NRC) uses Regulatory Guide 7.9, ''Standard Format and Content of Part 71 Applications for Approval of Packaging for Radioactive Material'' to provide recommendations on the preparation of applications for approval of Type B and fissile material packages. The purpose of this Regulatory Guide is to assist the applicant in preparing an application that demonstrates the adequacy of a package in meeting the 10 CFR Part 71 packaging requirements. NRC recently revised Regulatory Guide 7.9 to reflect current changes to the regulations in Part 71 as a result of a recent rulemaking that included changes to the structural, containment, and criticality requirements for packages. Overall, the NRC issues Regulatory Guides to describe methods that are acceptable to the NRC staff for implementing specific parts of the NRC's regulations, to explain techniques used by the NRC staff in evaluating specific problems, and to provide guidance to applicants. It is important to note the specific purpose of this Regulatory Guide. As the name indicates, this Guide sets forth a standard format for application submission that is acceptable to the NRC staff that, when used by the applicant, will accomplish several objectives. First, use of the guide provides a consistent and repeatable approach that indicates the information to be provided by the applicant. Second, the organization of the information in the application will assist the reviewer(s) in locating information. Ultimately, accomplishing these objectives will help to ensure the completeness of the information in the application as well as decrease the review time. From an international perspective, use of a standard format approach could enhance the efficiency with which Competent Authorities certify and validate packages for use in the packaging and transportation of radioactive material worldwide. This streamlined approach of preparing package applications could ultimately lead to uniform

Code of practice on the international transboundary movement of radioactive waste

International Nuclear Information System (INIS)

1990-11-01

This Code of Practice should serve as guidelines of the IAEA to the States for the development and harmonization of policies and laws on the international transboundary movement of radioactive wastes. It relies on international standards for the safe transport of radioactive material and the physical protection of nuclear material, as well as the standards for basic nuclear safety and radiation protection and radioactive waste management; it does not establish separate guidance in these areas. Furthermore, this Code, which is advisory, does not affect in any way existing and future arrangements among States which relate to matters covered by it and are compatible with its objectives

Strengthening the safety and security of radioactive sources worldwide: a perspective on Philippine contributions

International Nuclear Information System (INIS)

Murray, Allan

2009-01-01

Radioactive sources have been used for many decades in a wide variety of applications in all countries. The safety of radioactive sources and the associated radiation protection have been implemented by national and international programs during this time with cooperation through the IAEA intended to achieve application of minimum standards and harmonization of approach. The security of radioactive sources is however relatively new consideration. A perspective on the Philippine contributions to the safety and security of radioactive sources will be provided with reference to the following: What is radioactive source security and why it is important?; International cooperation, including the IAEA Code of Conduct; Regulation for radioactive source security; Implementation of radioactive source security measures for licenses, operators and others; Impact of regulatory and operational matters such as professional development and training, emergency preparedness and response, and radiation protection. (author)

Low-level radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

Ishihara, T [Radioactive Waste Management Center, Tokyo (Japan)

1980-08-01

In the development and utilization of nuclear energy, variety of radioactive wastes arise. A largest part is low level radioactive wastes. In Japan, they are concentrated and solidified, and stored in drums. However, no low level wastes have yet been finally disposed of; there are now about 260,000 drums of such wastes stored on the sites. In Japan, the land is narrow, and its structure is geologically unstable, so that the sea disposal is sought. On the other hand, the development of technology for the ground disposal has lagged behind the sea disposal until recently because of the law concerned. The following matters are described: for the sea disposal, preparatory technology studies, environment safety assessment, administrative measures, and international control; for the ground disposal, experiments, surveys, disposal site selection, and the concept of island repositories.

Resolution 2/2004 Guidelines for the implementation of regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

2004-01-01

This guide is intended to supplement the provisions of Resolution no. 121/2000 of the Ministry of Science Technology and Environment Regulations the Security of Radioactive Materials Transport, hereinafter Regulation, Regarding the administrative requirements for the application process Certificates of Approval for the shipments of radioactive material and for Special arrangements.

Neotectonic movement feature in preselection area for high level radioactive waste repository

International Nuclear Information System (INIS)

Huang Xianfang; Gao Yang; He Jianguo; Li Jianzhong; Gao Honglei; Xu Guoqing

2010-01-01

Neotectonic activity intensity is an important criteria for evaluating high level radioactive waste repository. The guiding ideology, methods and application of neotectonic study are elaborated in the paper. According to comparison research between the south and north part of east Tianshan area, the south part of east Tianshan is regarded as relative stable or relative weak in neotectonic movement in Neogene period and was selected as preselection area for high level radioactive waste repository. (authors)

Artificial radioactive products in the atmosphere at Paris. [In French

Energy Technology Data Exchange (ETDEWEB)

Abribat, M; Pouradier, J; Venet, A M

1952-01-01

The radioactivity of solid matter in rain water and air collected near Paris in November 1951, and in April and May 1952, follows the same decay law as that observed for fission products after a nuclear detonation in Nevada in November 1951.

Sub-seabed burial of radioactive waste and liabilities

International Nuclear Information System (INIS)

Reyners, Patrick.

1982-10-01

The author of this report discusses the problems raised by application of the special third party liability system to damage which may result from embedding radioactive waste in the sub-seabed. The matter of general liability of the State for nuclear damage caused to the environment is also dealt with in this paper. (NEA) [fr

X rays and radioactivity: a complete surprise

International Nuclear Information System (INIS)

Radvanyi, P.; Bordry, M.

1995-01-01

The discoveries of X rays and of radioactivity came as complete experimental surprises; the physicists, at that time, had no previous hint of a possible structure of atoms. It is difficult now, knowing what we know, to replace ourselves in the spirit, astonishment and questioning of these years, between 1895 and 1903. The nature of X rays was soon hypothesized, but the nature of the rays emitted by uranium, polonium and radium was much more difficult to disentangle, as they were a mixture of different types of radiations. The origin of the energy continuously released in radioactivity remained a complete mystery for a few years. The multiplicity of the radioactive substances became soon a difficult matter: what was real and what was induced ? Isotopy was still far ahead. It appeared that some radioactive substances had ''half-lifes'': were they genuine radioactive elements or was it just a transitory phenomenon ? Henri Becquerel (in 1900) and Pierre and Marie Curie (in 1902) hesitated on the correct answer. Only after Ernest Rutherford and Frederick Soddy established that radioactivity was the transmutation of one element into another, could one understand that a solid element transformed into a gaseous element, which in turn transformed itself into a succession of solid radioactive elements. It was only in 1913 - after the discovery of the atomic nucleus -, through precise measurements of X ray spectra, that Henry Moseley showed that the number of electrons of a given atom - and the charge of its nucleus - was equal to its atomic number in the periodic table. (authors)

X rays and radioactivity: a complete surprise

Energy Technology Data Exchange (ETDEWEB)

Radvanyi, P. [Laboratoire National Saturne, Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France); Bordry, M. [Institut du Radium, 75 - Paris (France)

1995-12-31

The discoveries of X rays and of radioactivity came as complete experimental surprises; the physicists, at that time, had no previous hint of a possible structure of atoms. It is difficult now, knowing what we know, to replace ourselves in the spirit, astonishment and questioning of these years, between 1895 and 1903. The nature of X rays was soon hypothesized, but the nature of the rays emitted by uranium, polonium and radium was much more difficult to disentangle, as they were a mixture of different types of radiations. The origin of the energy continuously released in radioactivity remained a complete mystery for a few years. The multiplicity of the radioactive substances became soon a difficult matter: what was real and what was induced ? Isotopy was still far ahead. It appeared that some radioactive substances had ``half-lifes``: were they genuine radioactive elements or was it just a transitory phenomenon ? Henri Becquerel (in 1900) and Pierre and Marie Curie (in 1902) hesitated on the correct answer. Only after Ernest Rutherford and Frederick Soddy established that radioactivity was the transmutation of one element into another, could one understand that a solid element transformed into a gaseous element, which in turn transformed itself into a succession of solid radioactive elements. It was only in 1913 - after the discovery of the atomic nucleus -, through precise measurements of X ray spectra, that Henry Moseley showed that the number of electrons of a given atom - and the charge of its nucleus - was equal to its atomic number in the periodic table. (authors).

Manual of respiratory protection against airborne radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Caplin, J.L.; Held, B.J.; Catlin, R.J.

1976-10-01

The manual supplements Regulatory Guide 8.15, ''Acceptable Programs for Respiratory Protection''. It provides broad guidance for the planned use of respirators to protect individuals from airborne radioactive materials that might be encountered during certain operations. The guidance is intended for use by management in establishing and supervising programs and by operating personnel in implementing programs. Guidance is primarily directed to the use of respirators to prevent the inhalation of airborne radioactive materials. Protection against other modes of intake (e.g., absorption, swallowing, wound injection) is, in general, not covered nor is the use of protective equipment for head, eye, or skin protection.

Impact factors on radioactive waste management. Legal and institutional matters

International Nuclear Information System (INIS)

Dejonghe, P.

1979-03-01

This paper deals with clear definitions of the responsibilities of all parties involved on short and long-term, adequate financial assurance and some international standards with regard to the specifications on conditioning, storage and disposal. Furthermore, a light is thrown on the specific institutional problems in radioactive waste management, that might arise from the application of the various fuel cycles considered in the INFCE Study

The IAEA's role in safe radioactive waste management

International Nuclear Information System (INIS)

Flory, D.; Bruno, G.

2011-01-01

In accordance with its statute, IAEA is authorized to develop and maintain safety standards. This mission is reflected in the main programme of the IAEA on nuclear safety and security. In the field of the safety of radioactive waste management the IAEA is responsible for the delineation of a global safety regime to protect the public and the environment from harmful effects of ionizing radiation. This delineation is established on the basis of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, as well as on the development of safety standards for the management of all radioactive waste. The safety standards are the fruit of an international consensus on a high level of safety for the protection of people and environment. Safety guides are edited by IAEA, 7 volumes concern general safety requirements and 6 volumes deal with specific safety requirements (for instance for research reactors or for radioactive waste disposal facilities). Furthermore the IAEA assists Member States in the implementation of the safety standards and provides related services

Hydrogeochemical radioactive features and prospecting in granopegmatite type uranium ore district in Danfeng area

International Nuclear Information System (INIS)

Feng Zhangsheng

2011-01-01

Hydrochemical radioactive prospecting plays an important role in the all stages of grano-pegmatite type uranium deposit exploration in Danfeng area dut to its fast, simple, economic and high effective advantage. Radioactive anomalous halo in the shallow underground water has identical distribution scopes with the ore-bearing biotite granite-pegmatite, which can be used to delineate uranium ore-forming prospective area, reconnaissance area and detailed prospecting area. Deep underground water close to the ore is characterized by hydrogeochemical radioactive features with high uranium and radon content. Through prospecting engineering of radioactive hydrogeochemical, the situation of blind ore bodies can be used to guide the layout. (authors)

Code of practice for the control and safe handling of radioactive sources used for therapeutic purposes (1988)

International Nuclear Information System (INIS)

1988-01-01

This Code is intended as a guide to safe practices in the use of sealed and unsealed radioactive sources and in the management of patients being treated with them. It covers the procedures for the handling, preparation and use of radioactive sources, precautions to be taken for patients undergoing treatment, storage and transport of radioactive sources within a hospital or clinic, and routine testing of sealed sources [fr

Radioactive waste communication policy in Spain

International Nuclear Information System (INIS)

Gonzalez, V.

1993-01-01

ENRESA (Empresa Nacional de Residuos Radiactivos, S.A.), is a State-owned company, founded in 1985 and is responsible for radioactive waste management in Spain. ENRESA's activities are developed following a General Radioactive Waste Plan approved by the Spanish Government. As in most countries, Spanish public opinion is concerned with the most activities related to radioactivity or rad-waste management due to different facts but mainly to a lack of information on the matter. This situation provides misuse of information on it by some politicians, green groups and media which increases distrust of public on responsible companies and institutions. To gain public acceptance, it would be necessary to develop long-term information policy, due to the fact that results in communication are reached in the long term. ENRESA is carrying out a Communication Plan (CP) which has been implemented in a continuous way with success around the area of the disposal site of low and intermediate level wastes as well as around an old uranium mill factory in which remedial actions are being implemented. The implantation of CP at a national level is being done stepwise. The more relevant issues related to the radioactive waste situation in Spain, as well as the communication actions are explained in this document

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

Literature in focus: The history of radioactivity

CERN Document Server

2006-01-01

René Bimbot, an expert in nuclear physics, will be coming to present his book - The History of Radioactivity. The work provides a summary of our accumulated knowledge of radioactivity and its applications, from its discovery to the present day. Presented in layman's terms, and backed by plenty of illustrations, the work creates the link between the rudimentary knowledge available in the times of Becquerel and the Curies and contemporary physics. It takes us on a great physics adventure, from the nucleus to the quark, from artificial radioactivity to radiotherapy, from the discovery of fission to nuclear reactors, not forgetting dating methods. Finally, the work provides a wealth of practical information on radiation and on matters relating to nuclear waste. A former Research Director at the CNRS, a heavy-ion physicist at the Orsay Nuclear Physics Institute, René Bimbot is no stranger to CERN. At the beginning of the 1980s, he worked on the CERN Synchrocyclotron, before joining the GANIL experiment in 1985...

Model Regulations for Borehole Disposal Facilities for Radioactive Waste

International Nuclear Information System (INIS)

2017-10-01

This publication is designed to assist in the development of an appropriate set of regulations for the predisposal management and disposal of disused sealed radioactive sources and small volumes of associated radioactive waste using the IAEA borehole disposal concept. It allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference by those States developing regulations for the first time. The model regulations set out in this publication will need to be adapted to take account of the existing national legal and regulatory framework and other local conditions in the State.

LRT 2006: 2. topical workshop in low radioactivity techniques

International Nuclear Information System (INIS)

Cushman, P.; Piquemal, F.; Ford, R.; Yakushev, E.; Pandola, L.; Franco, D.; Bellini, F.; Hubert, Ph.; Laubenstein, M.; Abt, I.; Bongrand, M.; Schnee, R.; Dusan, B.; Chen, M.; Piquemal, F.; Nachab, A.; Zuzel, G.; Simgen, H.; Navick, X.F.; Pedretti, M.; Wojcik, M.; Sekiya, H.; Kim, Y.; Kishimoto, T.; Dawson, J.; Borjabad, S.; Perrot, F.; Gurriaran, R.; Nikolayko, A.; Hubert, Ph.

2006-01-01

This second topical workshop in low radioactivity techniques is intended to bring together experts in the field of low background techniques, especially applied to dark matter experiments, double beta decay experiments and neutrino detection in underground laboratories. This workshop has been organized into 7 sessions: 1) underground facilities (where a worldwide review is made), 2) neutron and muon induced background, isotope production, 3) low background counting techniques and low background detectors, 4) techniques for radon reduction, purified noble gases and liquid scintillator purification, 5) low levels on Pb-Bi-Po 210 and surface background, 6) low radioactivity detector components and material purification, and 7) low radioactive techniques in other applications (particularly to check the geographical origin of food-products or to date wine. This document is made up of the slides of the presentations

LRT 2006: 2. topical workshop in low radioactivity techniques

Energy Technology Data Exchange (ETDEWEB)

Cushman, P; Piquemal, F; Ford, R; Yakushev, E; Pandola, L; Franco, D; Bellini, F; Hubert, Ph; Laubenstein, M; Abt, I; Bongrand, M; Schnee, R; Dusan, B; Chen, M; Piquemal, F; Nachab, A; Zuzel, G; Simgen, H; Navick, X F; Pedretti, M; Wojcik, M; Sekiya, H; Kim, Y; Kishimoto, T; Dawson, J; Borjabad, S; Perrot, F; Gurriaran, R; Nikolayko, A; Hubert, Ph

2006-07-01

This second topical workshop in low radioactivity techniques is intended to bring together experts in the field of low background techniques, especially applied to dark matter experiments, double beta decay experiments and neutrino detection in underground laboratories. This workshop has been organized into 7 sessions: 1) underground facilities (where a worldwide review is made), 2) neutron and muon induced background, isotope production, 3) low background counting techniques and low background detectors, 4) techniques for radon reduction, purified noble gases and liquid scintillator purification, 5) low levels on Pb-Bi-Po{sup 210} and surface background, 6) low radioactivity detector components and material purification, and 7) low radioactive techniques in other applications (particularly to check the geographical origin of food-products or to date wine. This document is made up of the slides of the presentations.

Introduction to the problems of the radioactive wastes

International Nuclear Information System (INIS)

Barrachina, M.

1990-01-01

Small book intended to provide basic information to non-specialists about the nature and the risks of radioactive wastes. The subject is developed through five chapters: Ch. I underlines the idea that the XX Century nuclear reactors and 'artificial' radioactivity to that naturally occurring in the Earth since the last event of the nucleosynthesis of the elements in the Solar System, some 4500 millions of years ago; Ch. II describes the ordered universal set of atomic units (nucleidic chart) responsible for all the kinds of known matter, and their transformation rules by which radioactivity is created. Ch. III explains the properties of radioactive wastes as a result of their radionuclide content; Ch. IV puts into perspective the hazards of this kink of wastes by comparison to other common occurring wastes generated by human activity; and finally; Ch. V refers to the risks of the Earth (as a cosmic repository), in order to provide a natural reference level to assess the risk legacy that we will afford to future generations. (Author)

Radioactivity and Man Minicourse, Career Oriented Pre-Technical Physics.

Science.gov (United States)

Dallas Independent School District, TX.

This instructional guide, intended for student use, develops the subject of radioactivity and man through a series of sequential activities. A technical development of the subject is pursued with examples stressing practical aspects of the concepts. Included in the minicourse are: (1) the rationale, (2) terminal behavioral objectives, (3) enabling…

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Spanish Edition); Control de fuentes huérfanas y otros materiales radiactivos en las industrias de reciclado y producción de metales. Guía de seguridad específica

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-12-15

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives.

Design of Radioactive Waste Management Systems at Nuclear Power Plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide is addressed to the administrative and technical authorities and specialists dealing with the design, construction and operation of nuclear power plants, and in particular waste management facilities at nuclear power plants. This Guide has been prepared as part of the IAEA Waste Handling, Treatment and Storage programme. It is a follow-up document to the Code of Practice on Management of Radioactive Wastes from Nuclear Power Plants published in 1985 in the IAEA Safety Standards, Safety Series No. 69, in which basic principles for management of radioactive wastes at nuclear power plants are set out. The IAEA has established wide ranging programmes to provide Member States with guidance on different aspects of safety and technology related to thermal neutron power reactors and associated nuclear fuel cycle operations, including those for management of radioactive wastes. There are many IAEA publications related to various technical and safety aspects of different nuclear energy applications. All these publications are issued by the Agency for the use of Member States in connection with their own nuclear technological safety requirements. They are based on national experience contributed by experts from different countries and relate to common features in approaches to the problems discussed. However, the final decision and legal responsibility in any regulatory procedure always rest with the Member State. This particular Guide aims to provide general and detailed principles for the design of waste management facilities at nuclear power plants. It emphasizes what and how specific safety requirements for the management of radioactive wastes from nuclear power plants can be met in the design and construction stage. The safety requirements for operation of such facilities will be considered in the Agency's next Safety Series publication, Safety Guide 50-SG-011, Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants

Medical and biohazardous waste generator`s guide: Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This Guide describes the procedures required to comply with all federal and state laws and regulations and Lawrence Berkeley Laboratory (LBL) policy applicable to medical and biohazardous waste. The members of the LBL Biological Safety Subcommittee participated in writing these policies and procedures. The procedures and policies in this Guide apply to LBL personnel who work with infectious agents or potentially infectious agents, publicly perceived infectious items or materials (e.g., medical gloves, culture dishes), and sharps (e.g., needles, syringes, razor blades). If medical or biohazardous waste is contaminated or mixed with a hazardous chemical or material, with a radioactive material, or with both, the waste will be handled in accordance with the applicable federal and State of California laws and regulations for hazardous, radioactive, or mixed waste.

Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules.

Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

Radioactivity and radiation what they are, what they do, and how to harness them

CERN Document Server

Grupen, Claus

2016-01-01

This book lays the foundations for you to understand all that you always wanted to know about radioactivity. It begins by setting out essential information about the structure of matter, how radiation occurs and how it can be measured. It goes on to explore the substantial benefits of radioactivity through its many applications, and also the possible risks associated with its use. The field of radioactivity is explained in layman’s terms, so that everybody who is interested can improve their understanding of issues such as nuclear power, radiation accidents, medical applications of radiation and radioactivity from the environment. Everything is radioactive. There is natural radioactivity in the homes that we live in, the food that we eat and the air that we breath. For over 100 years, people have recognised the potential for radioactivity to help solve problems and improve our standard of living. This has led to the creation of radioactivity levels in some places that are much higher than naturally-occurr...

Security of radioactive sources. Interim guidance for comment

International Nuclear Information System (INIS)

2003-06-01

In previous IAEA publications, there have been only rather general security requirements for non-nuclear radioactive material. These requirements were primarily directed to such issues as unintentional exposure to radiation, negligence and inadvertent loss. However, it is clear that more guidance is needed to not only try and prevent further events involving orphan sources, but also to prevent the deliberate attempt to acquire radioactive sources for malevolent purposes. Member States have requested guidance on the type and nature of security measures that might be put in place and on the methodology to be used in choosing such measures. These requests were also endorsed in the findings of the international conference on 'Security of Radioactive Sources' held in March 2003. Practical advice on assessing and implementing security measures complements the general commitments in the proposed Revised Code of Conduct on Safety and Security of radioactive Sources. A Safety Guide entitled 'Safety and Security of Radiation Sources' that, amongst other things, discusses these issues is being drafted. However, it is recognized that guidance material is required before this document will be finalized in order to allow Member States opportunity to put in place appropriate actions and planning to address current issues. Hence the purpose of the current document is to provide advice on security approaches and to allow comment on detailed recommendations for levels of security on radioactive sources that may be incorporated within the Safety Guide. This report is primarily addressed to Regulatory Authorities but it is also intended to provide guidance to manufacturers, suppliers and users of sources. Its objective is to assist Member States in deciding which security measures are needed to ensure consistency with the International Basic Safety Standards and the Revised Code of Conduct for the Safety and Security of Radioactive Sources. It is recognized that there must be a

Definition and recommendations for the convention on the prevention of marine pollution by dumping of wastes and other matter, 1972. 1986 ed.

International Nuclear Information System (INIS)

1986-01-01

Under the terms of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, the IAEA is the organization with the responsibility for defining high level radioactive wastes or other high level radioactive matter which is unsuitable for dumping at sea, and for making recommendations to Contracting Parties about the issue of permits for dumping radioactive waste or other radioactive matter. The IAEA established a provisional Definition and Recommendations in 1974 and a revised version in 1978. This Safety Series document contains the second revised Definition and Recommendations, which were established in 1985. The Annexes to the document contain a description of the calculations which form the basis of the quantitative Definition, a comparison between the new and the previous version and a list of all the meetings held during the process of establishing the new document

Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste

International Nuclear Information System (INIS)

1984-01-01

Sea disposal operations of packaged low-level radioactive waste are carried out under the provisions of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, also referred to as the London Dumping Convention. The environmental impact of this disposal method is continuously kept under review, in particular within the IAEA which has provided the ''Definition of High-Level Radioactive Waste or Other High-Level Radioactive Matter Unsuitable for Dumping at Sea'' for the purpose of the Convention and within the OECD-NEA in the framework of its Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. The NEA Co-Ordinated Research and Environmental Surveillance Programme (CRESP) is focussed on the actual North-East Atlantic dump site. Its objective is to increase the available scientific data base related to the oceanographic and biological characteristics of the dump site and elaborate a site specific model of the transfers of radionuclides to human populations. Future site suitability reviews, as periodically requested under the terms of the Multilateral Consultation and Surveillance Mechanism, will therefore be based on a more accurate and comprehensive scientific basis

Application of the Dose Limitation System to the Mining and Milling of Radioactive Ores

International Nuclear Information System (INIS)

1987-01-01

This publication is one of the Safety Guides to the Code of Practice on Radiation Protection of Workers in the Mining and Milling of Radioactive Ores, 1983 Edition, which was published as a joint IAEA/ILO/WHO publication (IAEA Safety Series No.26). This Safety Guide is intended to demonstrate as well as facilitate the application of the principles of optimization in the control of risk among the workers engaged in the mining and milling of radioactive ores and to give some guidance on suitable technology. The International Atomic Energy Agency, jointly with the World Health Organization, the International Labour Organisation and the OECD Nuclear Energy Agency, published the Basic Safety Standards for Radiation Protection, 1982 Edition (IAEA Safety Series No. 9). The Basic Safety Standards outline the principles of radiation protection and also the basic requirements to be followed in the implementation of radiation protection control. These principles are further developed in the case of mining and milling of radioactive ores in the joint IAEA/ILO/WHO Code of Practice on Radiation Protection of Workers in the Mining and Milling of Radioactive Ores (IAEA Safety Series No. 26). This Safety Guide on the Application of the Dose Limitation System to the Mining and Milling of Radioactive Ores was prepared by an Advisory Group which met for the first time in Portoroz, Yugoslavia, from 22 to 26 August 1983, and then again from 6 to 10 August 1984, in Vienna. Following the second Advisory Group meeting the draft was further reviewed by A. Dory from Canada who also was a participant of the two Advisory Group meetings held earlier. After the consultant's review the draft was circulated among the members of the Advisory Group for a further check. The final version of the draft was prepared by the Secretariat with the help of a consultant

Research programme on radioactive wastes; Forschungsprogramm Radioaktive Abfaelle

Energy Technology Data Exchange (ETDEWEB)

Eckhardt, A. [Eidgenoessische Kommission fuer die Sicherheit der Kernanlagen (KSA), Brugg (Switzerland); Hufschmid, P. [Kommission Nukleare Entsorgung (KNE), Bern (Switzerland); Jordi, S. [Swiss Federal Office of Energy, Berne (Switzerland); Schanne, M. [Institut fuer Angewandte Medienwissenschaft (IAM), Zuercher Hochschule, Winterthur (Switzerland); Vigfusson, J. [Hauptabteilung fuer die Sicherheit der Kernanlagen (HSK), Brugg (Switzerland)

2009-11-15

This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

Method of processing radioactive wastes

International Nuclear Information System (INIS)

Nomura, Ichiro; Hashimoto, Yasuo.

1984-01-01

Purpose: To improve the volume-reduction effect, as well as enable simultaneous procession for the wastes such as burnable solid wastes, resin wastes or sludges, and further convert the processed materials into glass-solidified products which are much less burnable and stable chemically and thermally. Method: Auxiliaries mainly composed of SiO 2 such as clays, and wastes such as burnable solid wastes, waste resins and sludges are charged through a waste hopper into an incinerating melting furnace comprising an incinerating and a melting furnace, while radioactive concentrated liquid wastes are sprayed from a spray nozzle. The wastes are burnt by the heat from the melting furnace and combustion air, and the sprayed concentrated wastes are dried by the hot air after the combustion into solid components. The solid matters from the concentrated liquid wastes and the incinerating ashes of the wastes are melted together with the auxiliaries in the melting furnace and converted into glass-like matters. The glass-like matters thus formed are caused to flow into a vessel and gradually cooled to solidify. (Horiuchi, T.)

Natural radioactivity of bedrock bath instruments and hot spring instruments in Japan

International Nuclear Information System (INIS)

Kazuki Iwaoka; Hiroyuki Tabe; Hidenori Yonehara

2013-01-01

In Japan, bedrock bath instruments and hot spring instruments that contain natural radioactive nuclides are commercially available. In this study, such instruments containing natural radioactive nuclides, currently distributed in Japan, were collected and the radioactivity concentration of 238 U series, 232 Th series, and 40 K in them was determined by gamma ray spectrum analyses. Effective doses to workers and general consumers handling the materials were estimated, revealing the radioactivity concentration of 238 U series, 232 Th series, and 40 K to be lower than critical values given in the IAEA Safety Guide. The maximum effective doses to workers and general consumers were 210 and 6.1 μSv y -1 , respectively. These values are lower than the intervention exemption level (1,000 μSv y -1 ) given in ICRP Publ. 82. (author)

The PACKTRAM database on national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. User's guide for compiled system program

International Nuclear Information System (INIS)

1995-01-01

The PACKTRAM system program enables Member States to prepare data diskettes on national competent authorities' approval certificates for package design, special form material and shipment of radioactive material, for submission to the IAEA, and facilitates data manipulation and report preparation for the IAEA. The system program is provided as a 424 kbyte executable file, for which this document is the User Guide. The system is fully menu-driven and requires an IBM-compatible personal computer with a minimum of 640 kbyte random access memory, a hard drive and one 3-1/2 inch diskette drive. 3 refs, 6 tabs

Radioactive contamination of plants in Japan covered with fallout from H-bomb detonations in March-May 1954 at Bikini Atoll, Marshall Islands. I. Distribution of deposited radioactivity

Energy Technology Data Exchange (ETDEWEB)

Yatazawa, M; Ishihara, T

1955-01-01

In May 1954 rains contained radioactivity up to 0.2 muc./liter. The provisional permissible level of unknown radioisotopes in H/sub 2/O is given as 10/sup -7/ muc./ml for ..beta..- or ..gamma..-emitters. The safety factor for these values is at least 100. From these values the permissible level for foods was calculated as 0.22 muc./day. Food plants tested ranged 0 to 1.25 muc./10g dry matter. It is concluded that serious radioactive contamination of plants was probable.

Radiation monitoring in the mining and milling of radioactive ores

International Nuclear Information System (INIS)

1989-01-01

The present Guide is a revision of IAEA Safety Series No. 43. It explains the recommendations on administrative requirements for the organization of radiation protection in the mining and milling of radioactive ores, and the monitoring requirements, including methods, techniques, instrumentation and strategy. 146 refs, 9 figs, 14 tabs

Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The Definition Required by Annex I, paragraph 6 to the Convention and the Recommendations Required by Annex II, Section D

Energy Technology Data Exchange (ETDEWEB)

NONE

1975-01-10

Paragraph 6 of Annex I to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter provides for the Agency to define high-level radioactive wastes or other high-level radioactive matter as unsuitable for dumping at sea, and section D of Annex II provides for the Agency to make recommendations which the Contracting Parties to the Convention should take fully into account in issuing permits for the dumping at sea of radioactive wastes or other radioactive matter ''not included in Annex I''.

Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The Definition Required by Annex I, paragraph 6 to the Convention and the Recommendations Required by Annex II, Section D

International Nuclear Information System (INIS)

1975-01-01

Paragraph 6 of Annex I to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter provides for the Agency to define high-level radioactive wastes or other high-level radioactive matter as unsuitable for dumping at sea, and section D of Annex II provides for the Agency to make recommendations which the Contracting Parties to the Convention should take fully into account in issuing permits for the dumping at sea of radioactive wastes or other radioactive matter ''not included in Annex I''.

Utilization of crushed radioactive concrete for mortar to fill waste container void space

International Nuclear Information System (INIS)

Ishikura, Takeshi; Ohnishi, Kazuhiko; Oguri, Daiichiro; Ueki, Hiroyuki

2004-01-01

Minimizing the volume of radioactive waste generated during dismantling of nuclear power plants is a matter of great importance. In Japan waste forms buried in a shallow burial disposal facility as low level radioactive waste must be solidified by cement or other materials with adequate strength and must provide no harmful opening. The authors have developed an improved method to minimize radioactive waste volume by utilizing radioactive concrete for fine aggregate for mortars to fill void space in waste containers. Tests were performed with pre-placed concrete waste and with filling mortar using recycled fine aggregate produced from concrete. It was estimated that the improved method substantially increases the waste fill ratio in waste containers, thereby decreasing the total volume of disposal waste. (author)

Influence of hydrogen in the presence of organic matter on bacterial activity under radioactive waste disposal conditions

Energy Technology Data Exchange (ETDEWEB)

Chautard, C. [IRSN, PRP-DGE/SEDRAN/BERIS, B.P. 17, 92262 Fontenay-aux-Roses Cedex (France); CEA, DEN/DTN/SMTM/LMTE, bat 307, 13108 Saint Paul Lez Durance Cedex (France); Ritt, A. [IRSN, PRP-DGE/SRTG/LAME, B.P. 17, 92262 Fontenay-aux-Roses Cedex (France); Libert, M. [CEA, DEN/DTN/SMTM/LMTE, bat 307, 13108 Saint Paul Lez Durance Cedex (France); De Windt, L. [Mines-ParisTech, Geosciences Dpt., 77305 Fontainebleau Cedex (France)

2013-07-01

According to the French design for the disposal of high-level radioactive waste (HLW), waste will be emplaced in an environment involving metallic materials into a geological clay formation. The presence of microorganisms has recently been evidenced in such environments. Therefore, based on current knowledge, the introduction of microbial species during the construction and operational phases, as well as the survival of bacteria after the disposal closure, have to be accounted for within the context of safety assessment. Sulphate-reducing bacteria (SRB) activity is notably expected to have an impact on corrosion processes, and thus influence the evolution of metallic and clay materials involved in a HLW disposal cell. The present work investigates the potential development of a SRB, Thermo-desulfovibrio hydrogeniphilus, in order to better assess its metabolism in the presence of dissolved organic matter (DOM) that is representative of the DOM present in an argillaceous pore water, as well as hydrogen that will be produced by the anaerobic corrosion of metallic materials. After 49 days of batch experiments, hydrogen enhances the bacterial development in presence of a low amount of DOM, whereas the DOM alone does not seem to sustain bacteria activities. (authors)

Radioactive waste storage issues

International Nuclear Information System (INIS)

Kunz, D.E.

1994-01-01

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state's boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected

Matter and energy

International Nuclear Information System (INIS)

Rocha, A.F.G. da

1976-01-01

Rutherford's and Bhor's atomic models are presented, as well as the general configuration of the atom. In the study of energy, emphasis is given to its forms and unities, to equivalence between mass and energy and to the energy levels of the atom. Electrons and nuclear constituents, nuclear forces, stability and nuclear potential barrier are studied. The concepts of radioactive state, activity and nuclear decay are analysed, as well as nuclear reactions, fission, radioisotope production and cosmic rays. Interactions between radiation and matter are also analysed [pt

Dark Matter Benchmark Models for Early LHC Run-2 Searches. Report of the ATLAS/CMS Dark Matter Forum

Energy Technology Data Exchange (ETDEWEB)

Abercrombie, Daniel [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). et al.

2015-07-06

One of the guiding principles of this report is to channel the efforts of the ATLAS and CMS collaborations towards a minimal basis of dark matter models that should influence the design of the early Run-2 searches. At the same time, a thorough survey of realistic collider signals of Dark Matter is a crucial input to the overall design of the search program.

Natural and induced radioactivity in food

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-04-01

radioactivity in unirradiated food. There are no adverse effect from consumption of irradiated food which contains radioactivity well below background level. This publication should provide valuable information to anyone who has interest in food irradiation especially regulatory authorities for food safety and radiation applications as well as to consumers who might be interested in scientific matters of irradiated food.

Natural and induced radioactivity in food

International Nuclear Information System (INIS)

2002-04-01

radioactivity in unirradiated food. There are no adverse effect from consumption of irradiated food which contains radioactivity well below background level. This publication should provide valuable information to anyone who has interest in food irradiation especially regulatory authorities for food safety and radiation applications as well as to consumers who might be interested in scientific matters of irradiated food

Security guide for subcontractors

Energy Technology Data Exchange (ETDEWEB)

Adams, R.C.

1993-06-01

This guide is provided to aid in the achievement of security objectives in the Department of Energy (DOE) contractor/subcontractor program. The objectives of security are to protect information that, if released, would endanger the common defense and security of the nation and to safeguard plants and installations of the DOE and its contractors to prevent the interruption of research and production programs. The security objective and means of achieving the objective are described. Specific security measures discussed in this guide include physical barriers, personnel identification systems, personnel and vehicular access control, classified document control, protection of classified matter in use, storing classified matter, and repository combinations. Means of dealing with security violations and security infractions are described. Maintenance of a security education program is discussed. Also discussed are methods of handling clearance terminations, visitor control, travel to sensitive countries, and shipment security. The Technical Surveillance Countermeasures Program (TSCM), the Computer Security Program, and the Operations Security Plan (OPSEC) are examined.

Measurement and analysis of radioactive substances

International Nuclear Information System (INIS)

2001-01-01

Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

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

The Physical Tourist A Science Guide for the Traveler

CERN Document Server

Rigden, John S

2009-01-01

Typical travel guides have sections on architecture, art, literature, music and cinema. Rarely are any science-related sites identified. For example, a current travel guide for Germany contains one tidbit on science: Einstein is identified as the most famous citizen of Ulm. By contrast, this travel guide walks a tourist through Berlin and identifies where Max Planck started the quantum revolution, where Einstein lived and gave his early talks on general relativity, and where, across the street, Einstein’s books were burned by the Nazis. Or, if you are walking in Paris, this guide tells you where radioactivity was discovered and where radium was discovered. Scientific discoveries of the past, like art of the past, has shaped life in the 21st century. From this travel guide, a tourist will learn what other guides leave out.

Measurement and evaluation of alpha radioactivity using ionized air transport technology

International Nuclear Information System (INIS)

Maekawa, Tatsuyuki; Yamaguchi, Hiromi

2009-01-01

A novel alpha radioactivity monitor using ionized air transport technology has been developed for future constitution of 'clearance level' for uranium and TRU radioactive waste. This technology will bring paradigm shift on alpha-ray measurement, such as converting 'closely contacting and scanning measurement' to 'remotely contacting measurement in the block', and drastically improve the efficiency of measurement operation. In this article, the origin and chronicle of this technology were simply explained and our newest accomplishment was described. Furthermore, using measurement data obtained in our development process, measurement and evaluation examples of alpha radioactivity were shown for practical operations as informative guides. We hope that this technology will be widely endorsed as a practical method for alpha clearance measurement in the near future. (author)

Site selection experience for a new low-level radioactive waste storage/disposal facility at the Savannah River Plant

International Nuclear Information System (INIS)

Towler, O.A.; Cook, J.R.; Helton, B.D.

1985-10-01

Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identified at SRP. The potential site were ranked based on how well they met a set of characteristics considered important in site selection for a low-level radioactive waste disposal facility. The characteristics were given a weighting factor representing its relative importance in meeting site performance criteria. A candidate site was selected and will be the subject of a site characterization program

Resolution no. 15/2012 Safety Guide for the practice of nuclear meters

International Nuclear Information System (INIS)

2012-01-01

1. This guide is Intended to complement the requirements for practice Nuclear meters out in September: • Joint Resolution CITMA-MINSAP Regulation Basic Standards Radiation safety of November 30, 2001, hereinafter NBS. • CITMA Resolution 121/2000, Regulations for the Safe Transport Radioactive Materials; hereinafter transport regulations. • Resolution 35/2003 of CITMA Regulation for the safe management of Radioactive waste of March 7, 2003, hereinafter Regulation waste. • Joint Resolution CITMA-MINSAP Regulations for the Selection, Training Authorization and Associated Personnel performing Employment Practices of Ionizing Radiation of December 19, 2003, hereinafter Staff Rules. 2. The requirements of this guide are applicable to entities and performing practice-related activities Nuclear Meters throughout the national territory.

Drush User's Guide

CERN Document Server

Requena, Juan Pablo Novillo

2012-01-01

A practical guide full of examples and step-by-step instructions to start using Drush right from chapter 1. Drupal developers or themers who understand Drupal administration's basic concepts. Drush can make building any kind of website quicker and easier, no matter if it is a development environment, beta, a simple blog or a complex system.

Bottom loaded filter for radioactive liquids

International Nuclear Information System (INIS)

Wendland, W.G.

1980-01-01

A bottom loaded filter assembly for filtering radioactive liquids through a replaceable cartridge filter is disclosed. The filter assembly includes a lead-filled jacket enveloping a housing having a chamber therein for the filter cartridge. A track arrangement carries a hatch for sealing the chamber. A spacer plug supports the cartridge within guide means associated with the inlet conduit in the chamber. The plug and cartridge drop out of the chamber when the hatch is unbolted and move laterally of the chamber. During cartridge replacement, a new plug and cartridge are supported in the guide means by a spacer bar inserted across the track means under the chamber. The hatch is then slid under the chamber and bolted to the vessel, engaging an o-ring to seal the chamber

Dangerous quantities of radioactive material (D-values)

International Nuclear Information System (INIS)

2010-01-01

Radioactive material is widely used in industry, medicine, education and agriculture. In addition, it occurs naturally. The health risk posed by these materials vary widely depending on many factors, the most important of which are the amount of the material involved and its physical and chemical form. Therefore, there is a need to identify the quantity and type of radioactive material for which emergency preparedness and other arrangements (e.g. security) are warrant due to the health risk they pose. The aim of this publication is to provide practical guidance for Member States on that quantity of radioactive material that may be considered dangerous. A dangerous quantity is that, which if uncontrolled, could be involved in a reasonable scenario resulting in the death of an exposed individual or a permanent injury, which decreases that person's quality of life. This publication is published as part of the IAEA Emergency Preparedness and Response Series. It supports several publications including: the IAEA Safety Requirements 'Preparedness and Response for a Nuclear or Radiological Emergency', IAEA Safety Standards Series No. GS-R-2. IAEA, Vienna (2002). IAEA Safety Guide 'Categorization of Radioactive Sources', IAEA Safety Standards Series No RS-G-1.9, IAEA, Vienna (2005) and IAEA Safety Guide 'Arrangements for Preparedness for a Nuclear or Radiological Emergency' IAEA Safety Standards Series No. GS-G-2.1, IAEA, Vienna (2006). The procedures and data in this publication have been prepared with due attention to accuracy. However, as part of the review process, they undergo ongoing quality assurance checks. Comments are welcome and, following a period that will allow for a more extensive review, the IAEA may revise this publication as part of the process of continuous improvement. The publication uses a number of exposure scenarios, risk models and dosimetric data, which could be used during the response to nuclear or radiological emergency or other purposes

Determination of standards for transportation of radioactive material by aircrafts

International Nuclear Information System (INIS)

1978-01-01

These provisions are established on the basis of the Enforcement Regulation for the Law on Aviation. Terms are explained, such as exclusive loading and containers. Spontaneously ignitable liquid radioactive materials and the radioactive substances required to be contained in special vessels and others particularly operated during the transport, are excluded from the radioactive materials permissible for transport. The radioactive substances required to be transported as radioactive loadings don't include empty vessels used to contain radioactive materials and other things contaminated by such materials, when they conform to the prescriptions. The technical standards on radioactive loadings are defined, such as maximum radiation dose rate of 0.5 millirem per hour on the surface of L type loadings, 200 millirem per hour for A, and 1000 millirem per hour at the distance of 1 m for BM and BU types, respectively. Confirmation of the safeness of radioactive loadings may be made through the written documents prepared by the competent persons acknowledged by the Minister of Transport. The requisite of fissile loadings is that such loadings shall not reach critical state during the transport in the specified cases. Radioactive loadings or the containers with such loadings shall be loaded so that the safeness of such loadings is not injured by movement, overturn and fall during the transport. The maximum radiation dose rate of the containers with radioactive loadings shall not be more than 200 millirem per hour on the surface. The written documents describing the handling method and other matters for attention and the measures to be taken on accidents shall be carried with for the transport of radioactive loadings. (Okada, K.)

Dumping of solid packaged radioactivity in the deep oceans

International Nuclear Information System (INIS)

Forster, Wm. O.; Van As, D.

1980-01-01

With the increasing use of nuclear energy, the quantity of radioactive wastes which are generated is also increasing. Their treatment and disposal is causing a concern in further development of nuclear energy. World's oceans are considered as a possible location for these wastes. A convention on the prevention of marine pollution caused by dumping of wastes and other matter into oceans was adopted at the Intergovernmental Conference held at London in November 1972. The convention prohibits dumping of high-level radioactive wastes in the oceans and has entrusted the IAEA the tasks of defining the high level radioactive wastes and providing recommendations for the issue of special permits for dumping of the radioactive materials which do not fall into the category of high-level wastes. A provisional definition and recommendations formulated by the IAEA and adopted by contractin.o. parties in 1976 are outlined. On the basis of an oceanographic model developed by Shepherd (1976) and considered to be the best available, a revised definition and revised recommendations were formulated. Their salient features are mentioned. The key parameters for specific site assessments are mentioned. The Nuclear Energy Agency also formulated guidelines on sea-disposal packages for radioactive wastes in 1974 and revised them in 1978. Finally it is noted that criteria have not been established for dumping of non-radioactive wastes in the ocean, though such criteria are contained in the IAEA recommendations in case of radioactive wastes. (M.G.B.)

Method of removing radioactive waste from oil

International Nuclear Information System (INIS)

Belanger, R.L.

1986-01-01

This patent describes a method of removing particulates, radioactive contaminants, and moisture from oil, which consists of: straining out the particulates by passing the oil through a coarse filter screen to a receiving vessel; forming an upper stratum of oil and a lower stratum of sludge, consisting of mud, oil, particulates, and moisture, by heating the upper two-thirds of the receiving vessel; skimming off the stratum of oil from the receiving vessel; transferring the sludge from the receiving vessel to a container; transferring additional separated oil to the receiving vessel; conveying the oil skimmed from the receiving vessel to a mixing vessel; adding an effective amount of Calcium Hypochlorite crystals containing 65% free Chlorine to the mixing vessel to initiate salt formation with the radioactive contaminants; mixing the contents of the mixing vessel for at least ten minutes; transferring the mixture from the mixing vessel to a circulating heater; outputting the mixture from the circulating heater to a second mixing vessel; removing moisture from the oil; and filtering from the oil, the solid radioactive contaminant-salts and residual particulate matter

Manual on self-contained gamma irradiators (categories 1 and 3). Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of panoramic gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of panoramic gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. and which is common to all documents in the series. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

Radiological Risk Assessment and Survey of Radioactive Contamination for Foodstuffs

International Nuclear Information System (INIS)

Lee, W.R.; Lee, C.W.; Choi, K.S.

2007-11-01

After the Chernobyl nuclear accident in 1986, a radiological dose assessment and a survey of a radioactive contamination for foodstuffs have been investigated by many countries such as EU, Japan, USA. In the case of Japan which is similar to our country for the imported regions of foodstuffs, there were some instances of the excess for regulation on the maximum permitted levels of radioactive contamination among some imported foodstuffs. Concerns about the radioactive contamination of foodstuffs are increased because of the recently special situation (Nuclear test of North Korea). The purpose of this study is a radiological dose assessment and a survey of a radioactive contamination for foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Analytical results of the collected samples are below MDA. In this project, the model of radiological dose assessment via the food chain was also developed and radiological dose assessment was conducted based on surveys results of a radioactive contamination for foodstuffs in the Korean open markets since 2002. The results of radiological dose assessment are far below international reference level. It shows that public radiation exposure via food chain is well controlled within the international guide level. However, the radioactive contamination research of imported foodstuffs should be continuous considering the special situation(nuclear test of North Korea). These results are used to manage the radioactive contamination of the imported foodstuffs and also amend the regulation on the maximum permitted levels of radioactive contamination of foodstuffs

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.

Global marine radioactivity database (GLOMARD)

International Nuclear Information System (INIS)

Povinec, P.P.; Gayol, J.; Togawa, O.

1999-01-01

In response to the request of Member States and under the IAEA's mandate, the IAEA Marine Environment Laboratory (MEL) in Monaco has established and maintains a Global Marine Radioactivity Database (GLOMARD). It is a vast project compiling radionuclide measurements taken in the marine environment. It consists of systematic input of all radionuclide concentration data available for sea water, sediment, biota and suspended matter. The GLOMARD is therefore a powerful tool for the researchers of MEL as it integrates the results of analyses in most of the areas of the marine environment which have been investigated

The regulatory actions in the management of disuse radioactive sources

International Nuclear Information System (INIS)

Truppa, W.A.; Cordoba, M.F.; Poletti, M.; Calabria, M.A.; Pirez, C.

2010-01-01

During the last years, different incidents related to the discovery of inadvertent radioactive material have been reported through the international information systems available. From the analysis of the information received it can be concluded that those situations are derived from the inadequate application of concepts such as 'safety culture' and 'risk perception' or inadequate physical safety measures towards radioactive sources by the licensee. Among the activities that the regulators perform during the use of radioactive material, the most important are the ones related to avoiding the existence of disused radioactive sources. In this regard, the Nuclear Regulatory Authority (NRA) has implemented, through its Standards, regulatory mechanisms to adequately control and dispose of radioactive material. Concerning this matter, actions were taken in Argentina with the aim of disposing or keeping the custody in an authorized long term storage of every radioactive source used to measure thickness, humidity, level, weight, etc. that remained within the facilities without use and/or a suitable program to be reutilized within a period larger than six months. The objective of the present piece of work is to present the analysis and results of the actions fulfilled between 2002 and 2009, giving details about the regulatory activities performed in relation to the disposal and withdrawal of radioactive sources and the physical safety measures taken. (authors) [es

Ocean disposal of radioactive waste: Status report

International Nuclear Information System (INIS)

Calmet, D.P.

1989-01-01

For hundreds of years, the seas have been used as a place to dispose of wastes resulting from human activities and although no high level radioactive waste (HLW) has been disposed of into the sea, variable amounts of packaged low level radioactive waste (LLW) have been dumped at more than 50 sites in the northern part of the Atlantic and Pacific oceans. So far, samples of sea water, sediments and deep sea organisms collected on the various sites have not shown any excess in the levels of radionuclides above those due to nuclear weapons fallout except on certain occasions where caesium and plutonium were detected at higher levels in samples taken close to packages at the dumping site. Since 1957, the date of its first meeting to design methodologies to assess the safety of ''radioactive waste disposal into the sea'', the IAEA has provided guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. Since the Convention for the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (referred to as the London Dumping Convention) came into force in 1975, the dumping of waste has been regulated on a global scale. The London Dumping Convention entrusted IAEA with specific responsibilities for the definition of high level radioactive wastes unsuitable for dumping at sea, and for making recommendations to national authorities for issuing special permits for ocean dumping of low level radioactive wastes. This paper presents a status report of immersion operations of low-level radioactive waste and the current studies the IAEA is undertaking on behalf of the LDC

Forensic microanalysis of Manhattan Project legacy radioactive wastes in St. Louis, MO.

Science.gov (United States)

Kaltofen, Marco; Alvarez, Robert; Hixson, Lucas W

2018-06-01

Radioactive particulate matter (RPM) in St Louis, MO, area surface soils, house dusts and sediments was examined by scanning electron microscopy with energy dispersive X-ray analysis. Analyses found RPM containing 238 U and decay products (up to 46 wt%), and a distinct second form of RPM containing 230 Th and decay products (up to 15.6 wt%). The SEM-EDS analyses found similar RPM in Manhattan Project-era radioactive wastes and indoor dusts in surrounding homes. Copyright © 2018 Elsevier Ltd. All rights reserved.

Croatian-Hungarian cooperation on the Danube river radioactivity measurements

International Nuclear Information System (INIS)

Lulic, S.; Vancsura, P.

2003-01-01

Danube river radioactivity measurements on the border profile Mohac-Batina have been performed since the beginning of 1978 with varying frequency of sampling. Thus, in the period before nuclear power plant Paks started to work joint croatian-hungarian sampling at the border profile was taking place four times a year; the obtained results of measured radioactivity levels were used to assess radioactivity background data. From the start of nuclear power plant Paks running until Chernobyl reactor accident (April 1986) sampling was performed six times a year. After the Chernobyl accident, samples have been taken every month. Since decreased Chernobyl reactor accident influence was estimated until present samples have been taken six times a year. On the Danube river border profile the concentration activity of gamma radionuclides has been determined in water samples (filtered water and suspended matter), and in fish, sediment and Danube river algae samples. (authors)

Guide for International Peer Reviews of Decommissioning Cost Studies for Nuclear Facilities

International Nuclear Information System (INIS)

LaGuardia, Thomas S.; Pescatore, Claudio; )

2014-01-01

Peer reviews are a standard co-operative OECD working tool that offer member countries a framework to compare experiences and examine best practices in a host of areas. The OECD Nuclear Energy Agency (NEA) has developed a proven methodology for conducting peer reviews in radioactive waste management and nuclear R and D. Using this methodology, the NEA Radioactive Waste Management Committee's Working Party on Decommissioning and Dismantling (WPDD) developed the present guide as a framework for decommissioning cost reviewers and reviewees to prepare for and conduct international peer reviews of decommissioning cost estimate studies for nuclear facilities. It includes checklists that will help national programmes or relevant organisations to assess and improve decommissioning cost estimate practices in the future. This guide will act as the NEA reference for conducting such international peer reviews. The remainder of this guide is divided into eight chapters. Chapter 2 describes gathering the cost estimate study and underpinning documents, reviewing the study and writing a final report. Chapter 3 provides a detailed checklist approach for the review of the cost study report. Chapter 4 provides checklists to assist in reviewing benchmarked information. Chapter 5 provides comments on the approach and recommendations for use of this guide. Chapters 6 and 7 provide the background material used in developing this guide and Chapter 8 provides a list of the abbreviations and acronyms used in this guide

Evaluation of indigenously developed plastic scintillator sheet detector for surface radioactive contamination monitoring application

International Nuclear Information System (INIS)

Sahani, R.M.; Chaudhary, H.S.; Mahala, V.K.; Senwar, K.R.; Meena, J.P.

2018-01-01

Radioactive contamination may be caused by release of radioactivity in the environment due to accident at nuclear plant/reactor or spillage of loose radioactive materials in a laboratory. The protection of workers from potentially hazardous radiations emitted by the contaminants is a matter of prime concern. The detection of such radiations requires a monitoring system capable of measuring the level of radioactivity at the contaminated site. Plastic scintillators are widely used for large area radiation monitoring due to the ease of preparation in different shape and sizes. These detectors are sensitive to beta and gamma radiation therefore can be used for monitoring of beta and gamma contamination. In this paper, performance results of indigenously developed plastic scintillator sheet of area 800 cm 2 are reported

Industrial Radiography Instructor's Guide.

Science.gov (United States)

Richardson, Harry D.

The curriculum guide was developed for teacher use in an 80-hour course for industrial radiographers. The units include: (1) The Structure of Matter and Radiation, (2) Nuclear Reactions and Radioisotopes, (3) The Nature and Consequences of Radiation Exposure, (4) Radiation Attenuation, (5) Absorption of Radiation, (6) Radiation Detection and…

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

INES scale: French application to radioactive material transport

International Nuclear Information System (INIS)

Sowinski, S.; Strawa, S.; Aguilar, J.

2004-01-01

After getting the control of radioactive material transport in June 1997, the French safety Authority (ASN) decided to apply the INES scale to transport events. DGSNR (Directorate General for Nuclear Safety and Radioprotection) requests that radioactive material package consignors declare any event occurring during transportation, and has introduced the use of the INES scale adapted to classify transport events in order to inform the public and to have feedback. This paper deals with DGSNR's feedback during the past seven years concerning the french application of the INES scale. Significant events that occurred during transportation are presented. The French experience was used by IAEA to develop a draft guide in 2002 and IAEA asked countries to use a new draft for a trial period in July 2004

Science, Society, and America's Nuclear Waste: Ionizing Radiation, Unit 2. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 2 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to convey factual information relevant to radioactivity and radiation and relate that information both to the personal lives of students…

Lepton flavor violation induced by dark matter

Science.gov (United States)

Arcadi, Giorgio; Ferreira, C. P.; Goertz, Florian; Guzzo, M. M.; Queiroz, Farinaldo S.; Santos, A. C. O.

2018-04-01

Guided by gauge principles we discuss a predictive and falsifiable UV complete model where the Dirac fermion that accounts for the cold dark matter abundance in our Universe induces the lepton flavor violation (LFV) decays μ →e γ and μ →e e e as well as μ -e conversion. We explore the interplay between direct dark matter detection, relic density, collider probes and lepton flavor violation to conclusively show that one may have a viable dark matter candidate yielding flavor violation signatures that can be probed in the upcoming experiments. In fact, keeping the dark matter mass at the TeV scale, a sizable LFV signal is possible, while reproducing the correct dark matter relic density and meeting limits from direct-detection experiments.

Progress towards a convention on the safe management of radioactive waste

International Nuclear Information System (INIS)

Webb, G.A.M.; Jankowitsch, O.

1996-01-01

The Convention on Nuclear Safety was prepared during the period 1992 to 1994 and after consideration by a diplomatic conference in June 1994 was opened for signature at the general conference of the IAEA in September 1994. The matter of the safety of radioactive waste was discussed many times during the development of the convention but it was eventually decided to restrict the coverage to matters concerned with nuclear safety of land-based civil nuclear power plants and those aspects of radioactive waste management directly connected with and carried out on the same site as the power plant. In the preamble to the convention, however, item (ix) affirms 'the need to begin promptly the development of an international convention on the safety of radioactive waste management as soon as the ongoing process to develop waste management safety fundamentals has resulted in broad international agreement'. In September 1994, the general conference of the IAEA also passed a resolution inviting the board of governors and the director general to commence preparations for a convention on the safety of radioactive waste management. The director general therefore organized a preparatory meeting of experts from member states to discuss the basic concepts and the possible scope of such a convention and to examine working methods and the procedures for its preparation. This meeting which took place in February 1995 prepared a paper entitled 'Inventory of Issues Raised' and proposed that the appropriate mechanism would be the setting up of an open-ended group of legal and technical experts to prepare the convention. The Safety Series document at the fundamentals level on the principles of radioactive waste management was approved by the Board of Governors in March 1995 and all the initial preconditions for starting work on the convention were then fulfilled. (author)

The radioactive waste management in France

International Nuclear Information System (INIS)

Lacoste, A.C.; Bodenez, Ph.; Jacq, F.; Grevoz, A.; Bataille, Ch.; Birraux, C.; Vicent, C.; Locufier, A.; Bodenez, Ph.; Dupraz, B.; Leroy, D.; Granger, S.; Taniguchi, T.; Louvat, D.; Sene, M.; Sene, R.; Bonnemains, J.

2005-01-01

The actors involved in research will report on fourteen years work in their respective fields: ANDRA on its research on deep geological formation repositories and the Cea on its research into partitioning and transmutation, and packaging and long term storage, will submit their preliminary reports in June 2005. The debate surrounding high-level long-lived waste must not draw a veil over the existence of the other types of radioactive waste whose levels are much lower but representing volumes which are much greater. It is the reason why A.S.N. oversees the drafting of the National Plan for Radioactive Waste Management and recoverable Materials initiated two years ago by the Ministry for ecology and sustainable development following a request from O.P.E.C.S.T. (Parliament Office for Scientific and Technology Choices Assessment). The parliament has to decide on the matter within the deadline of 2006. (N.C.)

Radiation Safety in Industrial Radiography. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

A users guide to the radioactive waste inventory program 'DATABASE'

International Nuclear Information System (INIS)

Prince, G.A.; Tymons, B.J.

1984-09-01

The program computes an inventory of radioactive waste accumulation in a form such that a variety of interrogation, collation and summary functions can be used to access the stored information. Database is designed to be used online, that is the user will communicate with it at a computer terminal, and the program will display the result of each enquiry. It has the potential to automate much of the searching and adding up which was involved in compiling and using waste inventories in the past. (author)

Radiation protection and safety guide no. GRPB-G-4: inspection

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

The use of ionizing radiation and radiation sources in Ghana is on the increase due to national developmental efforts in Health Care, Food and Agriculture, Industry, Science and Technology. This regulatory Guide has been developed to assist both the Regulatory Body (Radiation Protection Board) and operating organizations to perform systematic inspections commensurate with the level of hazard associated with the application of radiation sources and radioactive materials. The present Guide applies to the Radiation Protection and Safety inspection and/or audit conducted by the Radiation Protection Board or Radiation Safety Officer. The present Guide is applicable in Ghana and to foreign suppliers of radiation sources. The present Guide applies to notifying person, licensee, or registrant and unauthorized practice

Some of the bases of the IAEA definition and recommendations concerning high-level radioactive waste unsuitable for dumping at sea and some of the Japanese findings of deep sea survey in the Pacific

International Nuclear Information System (INIS)

Nishiwaki, Y.

1980-01-01

The Provisional Definition and Recommendations Concerning Radioactive Wastes and Other Radioactive Matter referred to in Annexes I and II to the London Convention of 1972 on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter have been reviewed and revised by the IAEA during 1975-1978. The Revised Definition and Recommendations and of the Annex thereto for the purposes of the Convention emphasize that the definition and recommendations set forth by the IAEA should not be interpreted as precluding the adoption of more restrictive requirements by any Party to the Convention or appropriate national authorities, and that nothing in the document shall be construed as encouraging the dumping at sea of radioactive waste or other radioactive matter. With these reservations, the Definition of High-Level Radioacive Wastes or Other High-Level Radioactive Matter Unsuitable for Dumping at Sea is given, distinguishing between α-emitters, β/γ-emitters with half-lives of at least 0.5 years and of unknown half-lives; and tritium and β/γ-emitters with half-lives of less than 0.5 years. Bases of the IAEA definition and recommendations concerning high level radioactive waste unsuitable for dumping at sea and reservations attached to the given concentration limits are discussed. (orig.) [de

Regulatory framework for the management of radioactive wastes in Argentina

International Nuclear Information System (INIS)

D'Amato, E.; Siraky, G.; Petraitis, E.; Novo, R.

2000-01-01

The legal and regulatory framework within which the radioactive waste management is carried out in Argentina are exposed. The activities of the Nuclear Regulatory Authority (ARN) in relation to facility inspections, safety assessments and collaboration with international agencies in the matter are also presented. Further, the regulatory criteria applied to waste management are reported. (author)

Guide for effluent radiological measurements at DOE installations

International Nuclear Information System (INIS)

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

1983-07-01

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

Bottom loaded filter for radioactive liquid

International Nuclear Information System (INIS)

Wendland, W.G.

1980-01-01

A specification is given for a bottom loaded filter assembly for filtering radioactive liquids through a replaceable cartridge filter, which includes a lead-filled jacket enveloping a housing having a chamber therein for the filter cartridge. A track arrangement carries a hatch for sealing the chamber. A spacer plug supports the cartridge within guide means associated with the inlet conduit in the chamber. The plug and cartridge drop out of the chamber when the hatch is unbolted and moved laterally of the chamber along the track. During cartridge replacement a new plug and cartridge are supported in the guide means by a spacer bar inserted across the track means under the chamber. The hatch is then slid under the chamber and bolted to a flange on the housing, engaging an O-ring to seal the chamber. (author)

Supporting the initiative. Cooperation in radioactive waste management with the Russian Federation

International Nuclear Information System (INIS)

Bonne, A.; Semenov, B.

2000-01-01

An important objective of the IAEA activities is to facilitate and strengthen international co-operation for the sound and safe management of radioactive waste and spent nuclear fuel. The Russian Federation has been facing a number of complicated environmental problems in this field. This article gives a brief overview of the activities of the Contact Expert Group (CEG) which was established in 1996 with the objectives to promote international co-operative efforts aimed at resolving radioactive waste management issues, including radiation safety, environmental, technical, legal, organizational and financial matters

Legal Aspects of Radioactive Waste Management: Relevant International Legal Instruments

International Nuclear Information System (INIS)

Wetherall, Anthony; Robin, Isabelle

2014-01-01

The responsible use of nuclear technology requires the safe and environmentally sound management of radioactive waste, for which countries need to have stringent technical, administrative and legal measures in place. The legal aspects of radioactive waste management can be found in a wide variety of legally binding and non-binding international instruments. This overview focuses on the most relevant ones, in particular those on nuclear safety, security, safeguards and civil liability for nuclear damage. It also identifies relevant regional instruments concerning environmental matters, in particular, with regard to strategic environmental assessments (SEAs), environmental impact assessments (EIAs), public access to information and participation in decision-making, as well as access to justice

Filters for radioactive liquid wastes

International Nuclear Information System (INIS)

Koshiba, Yukihiko; Kawashima, Akio

1980-01-01

In the crud generated in the reactor cooling water for nuclear power plants, iron oxides (hematite and magnetite) are contained as the main components, and also Co, Mn, Fe, Cr exist as radioactive nuclides. A new filter to separate these cruds, nuclepore membrane filter (NPMF), was investigated for its adaptability, and has been adopted as a practical filter for radioactive liquid wastes. The NPMF has such features as the possibility of complete automation of operation, no generation of secondary wastes, and easy maintenance, because the NPMF has uniform circular holes in poly-carbonate thin films, and shows the properties of stable filtering of particulates, capability of back washing, and others. The elements mounted in a practical system have such construction that the membrane is cut in the form of doughnut, and sandwiched with 100 mesh polyester nets (spacer); the obtained unit filter (cassette) is mounted on the stackable plate of the same size; and 80 pieces of this cassette are formed in a filter of 4 m 2 filtering area. The performance varies with the properties of suspended matters and the turbidity of wastes. For example, the filtered liquid of 0.1 ppm or less can be obtained when the 1 μm filter material is used to treat the liquid waste containing 1 to 100 ppm suspended matters. Usually back washed water is produced by about 1/100 of treated liquid wastes. The lifetime of the membrane is expected to be 1 or 2 years if crud is the main component. (Wakatsuki, Y.)

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

International Nuclear Information System (INIS)

2004-01-01

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

Packaging of radioactive wastes for sea disposal

International Nuclear Information System (INIS)

1981-02-01

The Convention on the Prevention of Marine Pollution by the Dumping of Wastes and Other Matter, known as the London Dumping Convention was adopted by an inter-governmental conference in London in 1972 and came into force in 1975. In 1977, the IAEA Board of Governors agreed that there is a continuing responsibility for the IAEA to contribute to the effectiveness of the London Dumping Conventions by providing guidance relevant to the various aspects of dumping radioactive wastes at sea. In the light of the above responsibilities, the IAEA organized a Technical Committee Meeting from 3 to 7 December 1979 to assess the current situation concerning the requirements and the practices of packaging radioactive wastes for dumping at sea with a view to providing further guidance on this subject. The present report summarizes the results of this meeting

The IAEA inventory databases related to radioactive material entering the marine environment

International Nuclear Information System (INIS)

Rastogi, R.C.; Sjoeblom, K.L.

1999-01-01

Contracting Parties to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter (LC 1972) have requested the IAEA to develop an inventory of radioactive material entering the marine environment from all sources. The rationale for developing and maintaining the inventory is related to its use as an information base with which the impact of radionuclides entering the marine environment from different sources can be assessed and compared. Five anthropogenic sources of radionuclides entering the marine environment can be identified. These sources are: radioactive waste disposal at sea; accidents and losses at sea involving radioactive material; discharge of low level liquid effluents from land-based nuclear facilities; the fallout from nuclear weapons testing; and accidental releases from land-based nuclear facilities. The first two of these sources are most closely related to the objective of the LC 1972 and its request to the IAEA. This paper deals with the Agency's work on developing a database on radioactive material entering the marine environment from these two sources. The database has the acronym RAMEM (RAdioactive Material Entering the Marine Environment). It includes two modules: inventory of radioactive waste disposal at sea and inventory of accidents and losses at sea involving radioactive material

Development of a technical guide for the identification of radiological sources of potential exposure and/or contamination

International Nuclear Information System (INIS)

Reyes, R.; Scott, A.; Falo, G.; Collins, J.; Szrom, F.; Collins, D.

1999-01-01

Radiological assessment of sites with radioactive residues starts with the identification of potential sources. The US Army Center for Health Promotion and Preventive Medicine (USACHPPM) has developed a technical guide that summarizes sources of potential radiological exposures of both civilian and military origin. These sources include those found in the natural environment, in the nuclear fuel cycle, in medical and industrial settings, in the transportation of radioactive materials, in US Army commodities and foreign materiel, and in the use and storage of nuclear weapons. This technical guide is intended to foster awareness of radiological hazards and to provide the reader with the knowledge necessary to take the first step in radiological health risk assessment: recognition of the hazard. Furthermore, this guide can be used in conjunction with other technical guides for performing radiological surveys and field dose assessments in war or peacetime operations. (author)

Application of the management system for facilities and activities. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This Safety Guide supports the Safety Requirements publication on The Management System for Facilities and Activities. It provides generic guidance to aid in establishing, implementing, assessing and continually improving a management system that complies with the requirements established. In addition to this Safety Guide, there are a number of Safety Guides for specific technical areas. Together these provide all the guidance necessary for implementing these requirements. This publication supersedes Safety Series No. 50-SG-Q1-Q7 (1996). The guidance provided here may be used by organizations in the following ways: - To assist in the development of the management systems of organizations directly responsible for operating facilities and activities and providing services for: Nuclear facilities; Activities using sources of ionizing radiation; Radioactive waste management; The transport of radioactive material; Radiation protection activities; Any other practices or circumstances in which people may be exposed to radiation from naturally occurring or artificial sources; The regulation of such facilities and activities; - To assist in the development of the management systems of the relevant regulatory bodies; - By the operator, to specify to a supplier, via contractual documentation, any guidance of this Safety Guide that should be included in the supplier's management system for the supply and delivery of products

Preliminary results of the TMI-2 radioactive iodine mass balance study

International Nuclear Information System (INIS)

Pelletier, C.A.; Cox, T.E.; Reeder, D.L.; Vollique, P.G.; Thomas, C.D.

1982-01-01

Analysis of samples taken from the Three Mile Island Unit 2 (TMI-2) reactor building following the 1979 accident indicates the fraction of the radioactive iodine (radioiodine) inventory in the core released to the uilding atmosphere is smaller tan assumed in Regulatory Guide 1.4. This summary presents analytical results supporting this conclusion

Construction and commissioning of workrooms for handling of unsealed radioactive materials

International Nuclear Information System (INIS)

Weinhold, G.; Jost, E.; Koenig, W.

1976-03-01

The requirements prescribed for planning, design and construction of type II and III workrooms for handling of unsealed sources are outlined. The 'Guide Concerning Construction and Equipment of Rooms for Handling of Radioactive Materials' is explained and supplemented in part. Furthermore, problems of radiation protection organization and measuring techniques are discussed. (author)

The total amounts of radioactively contaminated materials in forests in Fukushima, Japan

Science.gov (United States)

Hashimoto, Shoji; Ugawa, Shin; Nanko, Kazuki; Shichi, Koji

2012-01-01

There has been leakage of radioactive materials from the Fukushima Daiichi Nuclear Power Plant. A heavily contaminated area (≥ 134, 137Cs 1000 kBq m−2) has been identified in the area northwest of the plant. The majority of the land in the contaminated area is forest. Here we report the amounts of biomass, litter (small organic matter on the surface of the soil), coarse woody litter, and soil in the contaminated forest area. The estimated overall volume and weight were 33 Mm3 (branches, leaves, litter, and coarse woody litter are not included) and 21 Tg (dry matter), respectively. Our results suggest that removing litter is an efficient method of decontamination. However, litter is being continuously decomposed, and contaminated leaves will continue to fall on the soil surface for several years; hence, the litter should be removed promptly but continuously before more radioactive elements are transferred into the soil. PMID:22639724

International symposium on restoration of environments with radioactive residues. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

After the use of radioactive materials or the utilization of nuclear energy, some radioactive residues may remain in the environment and give rise to the exposure of persons living or working in that environment. Most commonly, these residues are the result of human activities that have been carried out in the past without proper regard to the internationally accepted radiation protection requirements for practices, or at that time when those requirements were less stringent than today. Of course unforeseen events such as accidents of concentrations of naturally occurring radioactive material can also lead to higher levels of radioactive residues in theenvironment. The purpose of this Symposium is to foster an information exchange on the restoration of environments with radioactive residues. This includes the principles and criteria for guiding decision making and the methodologies for assessing the radiological situation and developing remediation plans for the human habitats affected. The overall aim is to promote an international consensus on the relevant issues in these areas. This document contains 51 presentations delivered during oral and poster sessions. Each of the presentations was separately indexed and provided with an abstract.

International symposium on restoration of environments with radioactive residues. Contributed papers

International Nuclear Information System (INIS)

1999-01-01

After the use of radioactive materials or the utilization of nuclear energy, some radioactive residues may remain in the environment and give rise to the exposure of persons living or working in that environment. Most commonly, these residues are the result of human activities that have been carried out in the past without proper regard to the internationally accepted radiation protection requirements for practices, or at that time when those requirements were less stringent than today. Of course unforeseen events such as accidents of concentrations of naturally occurring radioactive material can also lead to higher levels of radioactive residues in the environment. The purpose of this Symposium is to foster an information exchange on the restoration of environments with radioactive residues. This includes the principles and criteria for guiding decision making and the methodologies for assessing the radiological situation and developing remediation plans for the human habitats affected. The overall aim is to promote an international consensus on the relevant issues in these areas. This document contains 51 presentations delivered during oral and poster sessions. Each of the presentations was separately indexed and provided with an abstract

Radioactivity in the ocean: laws and biological effects

Energy Technology Data Exchange (ETDEWEB)

Hunsaker, C.T.

1985-01-01

This paper summarizes the literature on US laws and international agreements, experimental and monitoring data, and ongoing studies to provide background information for environmental assessment and regulatory compliance activities for ocean dumping of low-level radioactive waste. The Marine Protection, Research, and Sanctuaries Act is the major US legislation governing ocean disposal of radioactive waste. The major international agreement on ocean dumping is the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The United States ended its ocean dumping of radioactive wastes in 1970, but other countries have continued ocean dumping under international supervision in the northeast Atlantic. Monitoring of former US disposal sites has neither revealed significant effects on marine biota nor indicated a hazard to human health. Also, no effects on marine organisms have been found that could be attributed to routine discharges into the Irish Sea from the Windscale reprocessing plant. We must improve our ability to predict the oceanic carrying capacity and the fate and effects of ionizing radiation in the marine environment.

Radioactivity in the ocean: laws and biological effects

International Nuclear Information System (INIS)

Hunsaker, C.T.

1985-01-01

This paper summarizes the literature on US laws and international agreements, experimental and monitoring data, and ongoing studies to provide background information for environmental assessment and regulatory compliance activities for ocean dumping of low-level radioactive waste. The Marine Protection, Research, and Sanctuaries Act is the major US legislation governing ocean disposal of radioactive waste. The major international agreement on ocean dumping is the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter. The United States ended its ocean dumping of radioactive wastes in 1970, but other countries have continued ocean dumping under international supervision in the northeast Atlantic. Monitoring of former US disposal sites has neither revealed significant effects on marine biota nor indicated a hazard to human health. Also, no effects on marine organisms have been found that could be attributed to routine discharges into the Irish Sea from the Windscale reprocessing plant. We must improve our ability to predict the oceanic carrying capacity and the fate and effects of ionizing radiation in the marine environment

Consumer Citizenship Curriculum Guides for Social Studies, English, Science, Mathematics.

Science.gov (United States)

MacKenzie, Louise; Smith, Alice

These four consumer citizenship curriculum guides for social studies, English, science, and mathematics incorporate consumer education into these subject matter areas in grades 8-12. Each guide is organized around 10 main component/goals. They are basic economics in the marketplace, credit, consumer law/protection, banking skills, comparison…

Forsmark site investigation. Bedrock geology - overview and excursion guide

Energy Technology Data Exchange (ETDEWEB)

Stephens, Michael B. (Geological Survey of Sweden, Uppsala (Sweden))

2010-09-15

Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark (this guide) and Laxemar-Simpevarp areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel in Finland. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at ten representative outcrops or outcrop areas at the ground surface in the site investigation area at Forsmark. All localities are located within or immediately adjacent to the proposed repository volume selected by SKB

Oskarshamn site investigation. Bedrock geology - overview and excursion guide

Energy Technology Data Exchange (ETDEWEB)

Wahlgren, Carl-Henric (Geological Survey of Sweden, Uppsala (Sweden))

2010-09-15

Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark and Laxemar-Simpevarp (this guide) areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at eight representative outcrops or outcrop areas at the ground surface in the site investigation area at Laxemar-Simpevarp and at one locality north of this area, i.e. at a total of nine localities

Oskarshamn site investigation. Bedrock geology - overview and excursion guide

International Nuclear Information System (INIS)

Wahlgren, Carl-Henric

2010-09-01

Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark and Laxemar-Simpevarp (this guide) areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at eight representative outcrops or outcrop areas at the ground surface in the site investigation area at Laxemar-Simpevarp and at one locality north of this area, i.e. at a total of nine localities

Forsmark site investigation. Bedrock geology - overview and excursion guide

International Nuclear Information System (INIS)

Stephens, Michael B.

2010-09-01

Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark (this guide) and Laxemar-Simpevarp areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel in Finland. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at ten representative outcrops or outcrop areas at the ground surface in the site investigation area at Forsmark. All localities are located within or immediately adjacent to the proposed repository volume selected by SKB

Radioactive waste disposal via electric propulsion

Science.gov (United States)

Burns, R. E.

1975-01-01

It is shown that space transportation is a feasible method of removal of radioactive wastes from the biosphere. The high decay heat of the isotopes powers a thermionic generator which provides electrical power for ion thrust engines. The massive shields (used to protect ground and flight personnel) are removed in orbit for subsequent reuse; the metallic fuel provides a shield for the avionics that guides the orbital stage to solar system escape. Performance calculations indicate that 4000 kg. of actinides may be removed per Shuttle flight. Subsidiary problems - such as cooling during ascent - are discussed.

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

Method of processing radioactive wastes

International Nuclear Information System (INIS)

Matagi, Yoshihiko; Takahara, Akira; Ootsuka, Katsuyuki.

1984-01-01

Purpose: To avoid the reduction in the atmospheric insulation by preventing the generation of CO 2 , H 2 O, etc. upon irradiation of microwave heat. Method: Radioactive wastes are charged into a hopper, supplied on a conveyor, fed each by a predetermined amount to a microwave furnace and heated by microwaves applied from a microwave guide. Simultaneously, inert gases are supplied from a supply line. The Radioactive wastes to be treated are shielded by the inert gases to prevent the combustion of decomposed gases produced from the wastes upon irradiation of microwave heat to thereby prevent the generation of CO 2 , H 2 , etc., as well as the generated decomposed gases are diluted with the inert gases to decrease the dissociation of the decomposed gases to prevent the reduction in the atmospheric insulation. Since the spent inert gases can be recovered for reuse, the amount of gaseous wastes released to the atmosphere can be decreased and the working life of the high performance air filters can be extended. (Sekiya, K.)

Low-level radioactive waste management in France: two decades of experience

International Nuclear Information System (INIS)

Marque, Y.

1993-01-01

Human activities generate wastes and these wastes have potential impacts on our environment and important implications for the twilight years of the twentieth century. Radioactive wastes, in particular, is a matter of considerable concern to the public, with emotional debate often clouding the legitimate need of the public for information for the subject. In France, the development of the nuclear power program and the widespread use of radioisotopes by the medical profession, industry and the research community called for a radioactive waste management program. In 1979, the French Government created ANDRA, the National Radioactive Waste Management Agency, which has the complete responsibility for radioactive waste disposal, including design, siting, construction and operation of waste disposal facilities. In 1991, the Waste Law reaffirmed ANDRA's principle functions and created the National Waste Observatory within ANDRA, whose the mission is to establish and maintain a current inventory of all radioactive waste storage and disposal sites on French territory. The present paper describes the generation of short-lived waste in France, the french policy on short-lived waste disposal, operation and cancellation of Manche plant, design and construction of Aube plant

Effects of radioactivity in the sea

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-04-15

The Agency's regulatory work has proved even more important than was originally expected. It is clear that these activities must be continued for several years, as there are several fields not yet covered, and several which must be followed through by incorporation into international conventions or other administrative frameworks. Research in this field is to be conducted under a trilateral agreement between the International atomic Energy Agency, the Government of the Principality of Monaco and the Institute of Oceanography in Monaco. The program will have three major objectives. Firstly, it will be aimed at acquiring knowledge about the movement of water and marine organisms and the deposition of organic and inorganic matter. Secondly, there will be a special study of the distribution in marine organisms of radioactive materials already existing or that may be introduced into various locations. And thirdly, there will be a study of the effects of radioactive materials at various concentration levels on the marine ecology.

Quality assurance for safety in the radioactive waste management: a quality assurance system in Novi Han radioactive waste repository

International Nuclear Information System (INIS)

Petrova, A.; Kolev, I.

2000-01-01

Novi Han Radioactive Waste Repository (RWR) is still the only place in Bulgaria for storage of low and intermediate level radioactive waste. It is necessary to establish and maintain a Quality Assurance (QA) system to ensure that the RWR can be operated safely with regard to the health and safety of the general public and site personnel. A QA system has to establish the basic requirements for quality assurance in order to enhance nuclear safety by continuously improving the methods employed to achieve quality. It is envisaged that the QA system for the Novi Han RWR will cover the operation and maintenance of the radioactive waste disposal facilities, the radiation protection and monitoring of the site, as well as the scientific and technology development aspects. The functions of the Novi Han RWR presume the availability of an environmental management system. It is appropriate to establish a QA system based on the requirements of the ISO Standards 9001 and 14000, using the recommendations of the IAEA (Quality assurance for safety in NPPs and other nuclear installations, code and safety guides Q1-Q14). (authors)

Standard Guide for Radiation Protection Program for Decommissioning Operations

CERN Document Server

American Society for Testing and Materials. Philadelphia

1987-01-01

1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of...

L-037: EPR-First Responders: Action Guides commander of incident response

International Nuclear Information System (INIS)

2011-01-01

This conference is about the main action guides responses implemented by the incident commander in a radiological emergency. The public exposure, the contamination, the radioactive sources and suspicious material are important aspects to be considered by the first responders

Procedures for picking up and receiving packages of radioactive material

International Nuclear Information System (INIS)

1975-05-01

This regulatory guide describes a method acceptable to the NRC staff for licensees to comply with the provisions in 10 CFR Part 20, section 20.205, with respect to arrangements for receipt, pickup, and monitoring of packages containing radioactive material and with respect to reporting of packages which, on receipt, show evidence of leakage or excessive radiation levels. (U.S.)

The philosophy behind the federal radiation council guides

Energy Technology Data Exchange (ETDEWEB)

Tompkins, P C [Federal Radiation Council (United States)

1969-07-01

The basic philosophy of the FRC in making recommendations for the control of radioactivity associated with normal peacetime operations is given in FRC report. Radiation Protection Guides for application to activities such as Plowshare would be derived on the basis of this philosophy. Considerations involve a balance of benefit versus risk for each Plowshare activity that is proposed for industrial application using potential exposures small in comparison to the basic guide of 0.17 rem per year as the primary reference condition. Alternate approaches to achieving an appropriate balance have been suggested. These include allocation of a fraction of the 0.17 rem per capita per year to each relevant activity; setting a universally applicable MPC for each nuclide of interest, and the concept of the dose commitment. Data to show the benefit in terms of the national need for the resource in question (e.g., gas production) and the risk as indicated by the amount of residual radioactivity is a prerequisite to setting guidance for using Plowshare techniques in conjunction with consumer products available to the general public. (author)

The philosophy behind the federal radiation council guides

International Nuclear Information System (INIS)

Tompkins, P.C.

1969-01-01

The basic philosophy of the FRC in making recommendations for the control of radioactivity associated with normal peacetime operations is given in FRC report. Radiation Protection Guides for application to activities such as Plowshare would be derived on the basis of this philosophy. Considerations involve a balance of benefit versus risk for each Plowshare activity that is proposed for industrial application using potential exposures small in comparison to the basic guide of 0.17 rem per year as the primary reference condition. Alternate approaches to achieving an appropriate balance have been suggested. These include allocation of a fraction of the 0.17 rem per capita per year to each relevant activity; setting a universally applicable MPC for each nuclide of interest, and the concept of the dose commitment. Data to show the benefit in terms of the national need for the resource in question (e.g., gas production) and the risk as indicated by the amount of residual radioactivity is a prerequisite to setting guidance for using Plowshare techniques in conjunction with consumer products available to the general public. (author)

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

Performance assessment review guide for DOE low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Dodge, R.L.; Hansen, W.R.; Kennedy, W.E. Jr.; Layton, D.W.; Lee, D.W.; Maheras, S.T.; Neuder, S.M.; Wilhite, E.L.; Curl, R.U.; Grahn, K.F.; Heath, B.A.; Turner, K.H.

1991-10-01

This report was prepared under the direction of the Performance Assessment Peer Review Panel. The intent is to help Department of Energy sites prepare performance assessments that meet the Panel's expectations in terms of detail, quality, content, and consistency. Information on the Panel review process and philosophy are provided, as well as important technical issues that will be focused on during a review. This guidance is not intended to provide a detailed review plan as in NUREG-1200, Standard Review Plan for Review of a License Application for a Low-Level Radioactive Waste Disposal Facility (January 1988). The focus and intent of the Panel's reviews differ significantly from a regulatory review. The review of a performance assessment by the Panel uses the collective professional judgment of the members to ascertain that the approach taken the methodology used, the assumptions made, etc., are technically sound and adequately justified. The results of the Panel's review will be used by Department of Energy Headquarters in determining compliance with the requirements of DOE Order 5820.2A, ''Radioactive Waste Management.''

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

Standard guide for making quality nondestructive assay measurements

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This guide is a compendium of Quality Measurement Practices for performing measurements of radioactive material using nondestructive assay (NDA) instruments. The primary purpose of the guide is to assist users in arriving at quality NDA results, that is, results that satisfy the end user’s needs. This is accomplished by providing an acceptable and uniform basis for the collection, analysis, comparison, and application of data. The recommendations are not compulsory or prerequisites to achieving quality NDA measurements, but are considered contributory in most areas. 1.2 This guide applies to the use of NDA instrumentation for the measurement of nuclear materials by the observation of spontaneous or stimulated nuclear radiations, including photons, neutrons, or the flow of heat. Recommended calibration, operating, and assurance methods represent guiding principles based on current NDA technology. The diversity of industry-wide nuclear materials measurement applications and instrumentation precludes disc...

Guide to the safe handling of radioactive wastes at nuclear power plants

International Nuclear Information System (INIS)

1980-01-01

This guide discusses the responsibilities of the regulatory authorities, the design considerations of waste management systems and the source and characteristics of waste. Present techniques for treating, conditioning, storing and disposing of gaseous, liquid and solid wastes on and from the site are summarized, and a consensus of good practice in waste management based on current knowledge and experience is given. The guide also contains brief chapters on transport of wastes, monitoring systems, safety analyses and a review of future trends in waste management

Guide to the safety design examination about light water reactor facilities for power generation

International Nuclear Information System (INIS)

Anon.

1977-01-01

This guide was compiled to evaluate the validity of the design policy when the safety design is examined at the time of the application for approval of the installation of nuclear reactors. About 7 years has elapsed since the existing guide was established, and the more appropriate guide to evaluate the safety should be made on the basis of the knowledge and experience accumulated thereafter. The range of application of this guide is limited to the above described evaluation, and it is not intended as the general standard for the design of nuclear reactors. First, the definition of the words used in this guide is given. Then, the guide to the safety examination is described about the general matters of reactor facilities, nuclear reactors and the measuring and controlling system, reactor-stopping system, reactivity-controlling system and safety protection system, reactor-cooling system, reactor containment vessels, fuel handling and waste treatment system. Several matters which require attention in the application of this guide or the clarification of the significance and interpretation of the guide itself were found, therefore the explanation about them was added at the end of this guide. (Kako, I.)

The radioactive waste management videoconference training series for an international audience

International Nuclear Information System (INIS)

Callan, C.; Hylko, J.M.

1996-01-01

A proven cost-effective method for delivering new educational opportunities to employees in different locations simultaneously is by using the live videoconference format. Also, the videotapes produced from this format allows employees to participate who are not routinely available for traditional classroom training. However, the primary challenge is to design a distance learning series that meets the requirements of a diverse audience. The National Environmental Technology Network (NETN), a program associated with the College of Engineering at the University of New Mexico, has a proven track record in developing and producing effective videoconference and distance learning programs for industry, government, national laboratories, and universities. Specifically, The Radioactive Waste Management Videoconference Training Series is comprised of eight individual programs: (1) Introduction to Radioactive Waste Management, (2) Interactions Between Radiation and Matter; (3) Decommissioning and Decontamination; (4) Transportation; (5) Low-Level Radioactive Waste; (6) High-Level Radioactive Waste; (7) Transuranic Waste; and (8) New and Other Technologies for Radioactive Waste Management. Each program consists of a tiered approach featuring an introduction, case studies, legal and regulatory issues, radioactive waste characteristics, disposal Options, and transfer of technology. The participants receive a packet containing a full outline of the course, including charts and illustrations used by the presenters. At the conclusion of each program, the interactive question/answer period allows viewers to ask pertinent questions and to participate as a group

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.

Regulatory control of radiation sources. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

Resource Letter HCMP-1: History of Condensed Matter Physics

Science.gov (United States)

Martin, Joseph D.

2017-02-01

This Resource Letter provides a guide to the literature on the history of condensed matter physics, including discussions of the development of the field and strategies for approaching its complicated historical trajectory. Following the presentation of general resources, journal articles and books are cited for the following topics: conceptual development; institutional and community structure; social, cultural, and political history; and connections between condensed matter physics and technology.

The transport of radioactive matters. Situation of transport events occurred in France from 1999 to 2007

International Nuclear Information System (INIS)

2008-01-01

This report presents transport events involving radioactive material, occurred on French territory from 1999 to 2007, listed in the I.R.S.N. database. 901 events have been recorded. For each of them, about 70 parameters have been collected from the analysis of the notifications and reports of the events (type of event, type of package, level on the INES scale). This synthesis informs about the annual evolution of transport events involving radioactive material and about their seriousness level. It also presents a short description of the incidents with radiological aspect and of the main events occurred in 2007. Then, an analysis of the most frequent types of events from 1999 to 2007 and of their evolution tendencies is presented. It gives a view of the elements that could be deduced from this feedback, in order to improve the safety of the radioactive material transports. (authors)

Global marine radioactivity database (GLOMARD)

International Nuclear Information System (INIS)

2000-06-01

The GLOMARD stores all available data on marine radioactivity in seawater, suspended matter, sediments and biota. The database provides critical input to the evaluation of the environmental radionuclide levels in regional seas and the world's oceans. It can be used as a basis for the assessment of the radiation doses to local, regional and global human populations and to marine biota. It also provides information on temporal trends of radionuclide levels in the marine environment and identifies gaps in available information. The database contains information on the sources of the data; the laboratories performing radionuclide analysis; the type of samples (seawater, sediment, biota) and associated details (such as volume and weight); the sample treatment, analytical methods, and measuring instruments; and the analysed results (such as radionuclide concentrations, uncertainties, temperature, salinity, etc.). The current version of the GLOMARD allows the input, maintenance and extraction of data for the production of various kinds of maps using external computer programs. Extracted data are processed by these programs to produce contour maps representing radionuclide distributions in studied areas. To date, development work has concentrated on the Barents and Kara Seas in the Arctic and the Sea of Japan in the northwest Pacific Ocean, in connection with the investigation of radioactive waste dumping sites, as well as on marine radioactivity assessment of the Mururoa and Fangataufa nuclear weapons tests sites in French Polynesia. Further data inputs and evaluations are being carried out for the Black and Mediterranean Seas. In the framework of the project on Worldwide Marine Radioactivity Studies, background levels of 3 H, 90 Sr, 137 Cs and 239,240 Pu in water, sediment and biota of the world's oceans and seas will be established

Declaration and authorization forms for the fabrication, distribution or use of radioactive sources or electric generators of ionizing radiation

International Nuclear Information System (INIS)

2010-01-01

This document gathers all the forms to be completed when declaring or when asking for an authorization for the fabrication, retailing or use of radioactive sources or electric equipment generating ionizing radiation. These forms can concern all domains (use of sealed radioactive sources, possession and use of a particle accelerator or of radionuclides, import or export of radionuclides or of products containing radionuclides), or the use of such materials or equipment in the medical sector, or the fabrication and use in industry or research, or in user's guides for radioactive sources

Advisory material for the IAEA regulations for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

Since the first edition in 1961, the Regulations for the Safe Transport of Radioactive Material of the IAEA (IAEA Regulations) have served as the basis of safety for the transport of radioactive material worldwide. In the discussions leading to the first edition of the IAEA Regulations, it was realized that there was need for a publication to supplement the Regulations which could give information of individual provisions as to their purpose, their scientific background and how to apply them in practice. In response, the Agency published Safety Series No. 7, entitled, in its first edition in 1961, 'Notes on Certain Aspects of the Regulations'. An additional source of information on the Regulations, providing advice on 'how' the user should comply with them which could be augmented from time to time in the light of latest experience, was provided by the Agency, initially in relation to the 1973 edition of the Regulations. This was entitled 'Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material' and designated Safety Series No. 37. This document is the result of combining the two Safety Series in a single publication. Thus the primary purpose of this publication is to provide guidance to users on proven and acceptable ways of complying with the Regulations. This Advisory Material is not a stand-alone text and it only has significance when used as a companion to the IAEA Safety Standards Series No. ST-1, Regulations for the Safe Transport of Radioactive Material (1996 edition)

Preliminary study of radioactive limonite localities in Colorado, Utah, and Wyoming

Science.gov (United States)

Lovering, T.G.; Beroni, E.P.

1956-01-01

Nine radioactive limonite localities of different types were sampled during the spring and fall of 1953 in an effort to establish criteria for differentiating limonite outcrops associated with uranium or thorium deposits from limonite outcrops not associated with such deposits. The samples were analyzed for uranium and thorium by standard chemical methods, for equivalent uranium by the radiometric method, and for a number of common metals by semiquantitative geochemical methods. Correlation coefficients were then calculated for each of the metals with respect to equivalent uranium, and to uranium where present, for all of the samples from each locality. The correlation coefficients may indicate a significant association between uranium or thorium and certain metals. Occurrences of specific that are interpreted as significant very considerably for different uranium localities but are more consistent for the thorium localities. Samples taken from radioactive outcrops in the vicinity of uranium or thorium deposits can be quickly analyzed by geochemical methods for various elements. Correlation coefficients can then be determined for the various elements with respect to uranium or thorium; if any significant correlations are obtained, the elements showing such correlation may be indicators of uranium or thorium. Soil samples of covered areas in the vicinity of the radioactive outcrop may then be analyzed for the indicator elements and any resulting anomalies used as a guide for prospecting where the depth of overburden is too great to allow the use of radiation-detecting instruments. Correlation coefficients of the associated indicator elements, used in conjunction with petrographic evidence, may also be useful in interpreting the origin and paragenesis of radioactive deposits. Changes in color of limonite stains on the outcrop may also be a useful guide to ore in some areas.

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.)

The exposures to natural radioactivity as a result of human activities

International Nuclear Information System (INIS)

Rannou, A.; Dupuis, M.; Bottollier-Depois, J.F.; Leprieur, F.; Pasquier, J.L.; Doremus, P.; Pierre, J.P.; Bernhard, S.; Delporte, V.; Servent, J.P.; Marchand, D.; Dupuis, M.; Bottollier-Depois, J.F.; Leprieur, F.; Pasquier, J.L.; Doremus, P.; Pierre, J.P.; Surbeck, H.; Degrange, J.P.

2005-01-01

The new regulation in matter of radiation protection, coming from the transposition of the European directive 96/29/EURATOM modifies the code of the public health and the labour code. The exposures to natural radioactivity by the very fact of human activities are the object of specific dispositions. These new dispositions apply to professional areas that were, until now, little concerned by the regulation relative to ionizing radiations. The S.F.R.P., in relationship with the Minister in charge of labour, and the A.F.T.I.M. (French organisation of safety technicians and engineers and labour physicians) organizes two days of information and exchange on the subject. This meeting concerns industry and research departments but also inspectors and labour physicians and other actors having a look on the risk management in societies. After some reminder on radioactivity and its effects, the regulation and the global risk management on working place, several actual examples are presented, covering the different known situations of exposure to the natural radioactivity ( radon, cosmic rays, use of radioactive material in an industrial process, production of radioactive waste). The days finish by a round table conference on the stakes and practical entailment of the new regulation. (N.C.)

Public acceptance in radioactive waste management

International Nuclear Information System (INIS)

Diaconu, Stela; Covreag, Ilinca

2008-01-01

Radioactive waste, unavoidable by-products of economically developed societies, arises from the production of energy by nuclear fission reactors as well as from medical, research and industrial applications of radioactive materials. The main objective of radioactive waste management is the safety as well the protection of public health and the environment. The first approach for the disposal of radioactive waste was based on the traditional 'decide, announce and defend' model, focused almost exclusively on technical content. In spite of the significant technical progress that would ensure long-term safety, the rate of progress towards implementing such solutions has been slower than expected, partly attributable to an earlier technical optimism and to an underestimation of the societal and political dimensions. It is now broadly recognized that radioactive waste management involves both technical and societal dimensions which cannot be dissociated. Because of changes in society's decision-making environment and heightened public sensitivity to all matters connected with environmental protection, nuclear power, radioactivity, and especially radioactive waste, any decision regarding whether, when and how to implement waste management solutions will typically require thorough public examination and the involvement of many relevant stakeholders. The building of a long-term relationship with the local communities and the waste management facility is one of the most important contributors to sustainable radioactive waste management solutions. A new approach in now in place at international level, based on 'engage, interact and co-operate', for which both technical and societal issues are to be reconciled. That means that the involvement of all interested parties in the decision-making process is a condition for a successful and publicly acceptable implementation of such a project. A central role in the public acceptance of nuclear technologies play the management and

Medical response guide for the initial phase of a radiological emergency

International Nuclear Information System (INIS)

Vazquez, Marina A.; Perez, Maria del R.

2007-01-01

In case of a sanitary emergency, the local community and its health care system are the first aid providers. Therefore, preparedness through education and training programs would allow emergency systems to provide an appropriate first medical response. The main objective of this guide is to give basic guidelines for the medical response management after situations involving radioactive materials, in an easy and simple way. The information contained in this guide is addressed to health care personnel of any local assistance center. (author) [es

Evaluation of physicochemical properties of radioactive cesium in municipal solid waste incineration fly ash by particle size classification and leaching tests.

Science.gov (United States)

Fujii, Kengo; Ochi, Kotaro; Ohbuchi, Atsushi; Koike, Yuya

2018-07-01

After the Fukushima Daiichi-Nuclear Power Plant accident, environmental recovery was a major issue because a considerable amount of municipal solid waste incineration (MSWI) fly ash was highly contaminated with radioactive cesium. To the best of our knowledge, only a few studies have evaluated the detailed physicochemical properties of radioactive cesium in MSWI fly ash to propose an effective method for the solidification and reuse of MSWI fly ash. In this study, MSWI fly ash was sampled in Fukushima Prefecture. The physicochemical properties of radioactive cesium in MSWI fly ash were evaluated by particle size classification (less than 25, 25-45, 45-100, 100-300, 300-500, and greater than 500 μm) and the Japanese leaching test No. 13 called "JLT-13". These results obtained from the classification of fly ash indicated that the activity concentration of radioactive cesium and the content of the coexisting matter (i.e., chloride and potassium) temporarily change in response to the particle size of fly ash. X-ray diffraction results indicated that water-soluble radioactive cesium exists as CsCl because of the cooling process and that insoluble cesium is bound to the inner sphere of amorphous matter. These results indicated that the distribution of radioactive cesium depends on the characteristics of MSWI fly ash. Copyright © 2018 Elsevier Ltd. All rights reserved.

Long term industrial management of radioactive wastes in France

International Nuclear Information System (INIS)

Lavie, J.

1981-01-01

All human activities including energy generation entail the wastes. This definitely applies also to nuclear power generation. Currently the nuclear power program is very extensive, and the plans of fuel reprocessing proceed along this line. In consequence, the Government has decided on tackling the problem of industrial radioactive waste management in earnest. For the purpose, the National Radioactive Waste Management Agency (ANDRA) was created in November, 1979, within the French Atomic Energy Commission (CEA). Its main functions are the design, siting and construction of waste disposal centers and their management, the establishment of waste treatment and disposal standards, and the research and development. The following matters are described: the need for comprehensive industrial approach, the concept of industrial management, ANDRA business program, the industrial policy on waste disposal, and ANDRA financing. (J.P.N.)

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in … shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Management and storage of radioactive waste

International Nuclear Information System (INIS)

Faussat, A.

1995-01-01

Management of radioactive waste is a matter of public concern. Such management, however, is today handled industrially in France, and when these techniques are well applied, its is possible to create storage centres. Waste having a short half-life is now stored in the Centre de l'Aube, which replaces the one begun in 1969 in the Department de la Manche. For waste with a long half-life, following the law passed in 1991, ANDRA is pursuing its programme of site prospecting to establish two underground laboratories for studying geological storage. (author). 2 figs., 1 tab

Declaration and authorization forms for the fabrication, distribution or use of radioactive sources or electric generators of ionizing radiation; Formulaires de declaration et d'autorisation de fabrication, de distribution ou d'utilisation de sources radioactives ou de generateurs electriques de rayonnements ionisants

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This document gathers all the forms to be completed when declaring or when asking for an authorization for the fabrication, retailing or use of radioactive sources or electric equipment generating ionizing radiation. These forms can concern all domains (use of sealed radioactive sources, possession and use of a particle accelerator or of radionuclides, import or export of radionuclides or of products containing radionuclides), or the use of such materials or equipment in the medical sector, or the fabrication and use in industry or research, or in user's guides for radioactive sources

Decommissioning of nuclear fuel cycle facilities. Safety guide

International Nuclear Information System (INIS)

2001-01-01

The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

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

Toward improvements of the education concerning radiation, radioactivity, and nuclear energy in high schools in Japan

International Nuclear Information System (INIS)

Matsuura, Tatsuo

1996-01-01

Despite the high scientific and technical level of research and practical applications of radiation, radioactivity, and nuclear energy in Japan, the level of education concerning these matters at primary school and junior and high schools seems to be considerably behind the world, according to a recent comparative survey among six European countries and Japan. It has also been found that the description of these matters in current textbooks of science and social studies in senior high schools in Japan is generally not satisfactory, both in scope and in correctness. There are many reasons for this observation. One is the fact that many Japanese people including writers of textbooks have an excessive fear for radiation and radioactivity, and consequently are critical of the use of nuclear energy. Another is that Japanese teachers also have similar feeling and tend to avoid teaching about such controversial subject. This comes from the educational policy of Monbusho, Ministry of Education, Science and Culture; the nuclear-related matters are not being given an appropriate educational position, despite their importance in the national energy policy determined by the Atomic Energy Commission of Japan. In addition, there are several unfortunate educational circumstances. These include, limitations of hours of teaching allotted to the subject of science, the system of choosing curricula among several menus in the subject, the shortage of experimental instruments available in classroom, the severe safety regulation in handling even a very small amount of radioactivity, extraordinary fear for radiation and radioactivity by students, teachers, and their supervisors, the rare appearance of these topics in the problems at the entrance examination of universities. This paper discusses various ways to correct the situation and reports on our recent activities for improving means of education such as textbooks and the official guidelines. (J.P.N.)

Procedures for picking up and receiving packages of radioactive material - May 1975

International Nuclear Information System (INIS)

Anon.

1976-01-01

This regulatory guide describes a method acceptable to the NRC staff for licensees to comply with the provisions in 10 CFR Part 20, Section 20.205, with respect to arrangements for receipt, pickup, and monitoring of packages containing radioactive material and with respect to reporting of packages which, on receipt, show evidence of leakage or excessive radiation levels

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.)

Development of very low-level radioactive waste sequestration process criteria

Energy Technology Data Exchange (ETDEWEB)

Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2015-12-15

Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

HBR guide to persuasive presentations inspire action, engage the audience, sell your ideas

CERN Document Server

Duarte, Nancy

2012-01-01

Terrified of speaking in front of a group? Or simply looking to polish your skills? No matter where you are on the spectrum, this guide will give you the confidence and the tools you need to get results. Written by presentation expert Nancy Duarte, the "HBR Guide to Persuasive Presentations" will help you: (1) Win over tough crowds, (2) Organize a coherent narrative, (3) Create powerful messages and visuals, (4) Connect with and engage your audience, (5) Show people why your ideas matter to them, and (6) Strike the right tone, in any situation.

Taking into account the dissemination risk of radioactive materials in the French fuel cycle factories; La prise en compte du risque de dissemination des matieres radioactives dans les usines du cycle du combustible en France

Energy Technology Data Exchange (ETDEWEB)

Ruiz, J

1994-12-31

In this text the conception principles retained for treating the dissemination risk of radioactive matters in the French fuel cycle factories are presented. For taking into account this risk successives containment systems are used with respects to the ventilation regulations and fire protection.

Establishment and utilization of radiological protection programs for the transport of radioactive material

International Nuclear Information System (INIS)

Lopez V, J.; Capadona, N.

2006-01-01

The present work has by objective to indicate rules for the establishment and the use of the Radiological Protection Programs (PPR) that are of application to the transport of radioactive materials according to that required by the Transport Regulation of the International Atomic Energy Agency (IAEA). The PPR are established and applied in systematic form for remittent, transport and addressees, to consider the measures of radiological protection and its appropriately control during the transport stages of radioactive material. In particular, in the work it is analyzed the PPR applied to the operative stage, in the one that can be considered as one of the more important documents to use since it summarizes the evaluations and the necessary controls of radiological protection. Also it is analyzed the importance that this document gets ready on the base that it converges in the the analyses, evaluations and data that have been kept in mind during the previous stages of design of bundles and production of packings, the types and quantities of involved bundles, as well as of considering the quantities of expeditions and its frequencies, the ways of transport, etc. It is included a brief description of the parts that the PPR conforms on the base of that suggested in the advanced draft of the TS-G-1.5 Guide 'Radiation Protection Programmes for Transport of Radioactive Material', of October, 2005, of the IAEA: objectives. necessity, scope, basic elements of a PPR in function of the occupational dose. assignment of functions and responsibilities for the establishment of a PPR, evaluation and dose optimization, surface contamination, segregation and other protection measures, responses in emergencies. training and administration systems for baled and transport of radioactive material. Next an example of PPR for the transport of bundles of the A Type by lorry with content of radiopharmaceuticals that are the bundles more used worldwide in the expeditions of radioactive

DarkSide search for dark matter

Energy Technology Data Exchange (ETDEWEB)

Alexander, T.; Alton, D.; Arisaka, K.; Back, H. O.; Beltrame, P.; Benziger, J.; Bonfini, G.; Brigatti, A.; Brodsky, J.; Bussino, S.; Cadonati, L.; Calaprice, F.; Candela, A.; Cao, H.; Cavalcante, P.; Chepurnov, A.; Chidzik, S.; Cocco, A. G.; Condon, C.; D' Angelo, D.; Davini, S.; Vincenzi, M. De; Haas, E. De; Derbin, A.; Pietro, G. Di; Dratchnev, I.; Durben, D.; Empl, A.; Etenko, A.; Fan, A.; Fiorillo, G.; Franco, D.; Fomenko, K.; Forster, G.; Gabriele, F.; Galbiati, C.; Gazzana, S.; Ghiano, C.; Goretti, A.; Grandi, L.; Gromov, M.; Guan, M.; Guo, C.; Guray, G.; Hungerford, E. V.; Ianni, Al; Ianni, An; Joliet, C.; Kayunov, A.; Keeter, K.; Kendziora, C.; Kidner, S.; Klemmer, R.; Kobychev, V.; Koh, G.; Komor, M.; Korablev, D.; Korga, G.; Li, P.; Loer, B.; Lombardi, P.; Love, C.; Ludhova, L.; Luitz, S.; Lukyanchenko, L.; Lund, A.; Lung, K.; Ma, Y.; Machulin, I.; Mari, S.; Maricic, J.; Martoff, C. J.; Meregaglia, A.; Meroni, E.; Meyers, P.; Mohayai, T.; Montanari, D.; Montuschi, M.; Monzani, M. E.; Mosteiro, P.; Mount, B.; Muratova, V.; Nelson, A.; Nemtzow, A.; Nurakhov, N.; Orsini, M.; Ortica, F.; Pallavicini, M.; Pantic, E.; Parmeggiano, S.; Parsells, R.; Pelliccia, N.; Perasso, L.; Perasso, S.; Perfetto, F.; Pinsky, L.; Pocar, A.; Pordes, S.; Randle, K.; Ranucci, G.; Razeto, A.; Romani, A.; Rossi, B.; Rossi, N.; Rountree, S. D.; Saggese, P.; Saldanha, R.; Salvo, C.; Sands, W.; Seigar, M.; Semenov, D.; Shields, E.; Skorokhvatov, M.; Smirnov, O.; Sotnikov, A.; Sukhotin, S.; Suvarov, Y.; Tartaglia, R.; Tatarowicz, J.; Testera, G.; Thompson, J.; Tonazzo, A.; Unzhakov, E.; Vogelaar, R. B.; Wang, H.; Westerdale, S.; Wojcik, M.; Wright, A.; Xu, J.; Yang, C.; Zavatarelli, S.; Zehfus, M.; Zhong, W.; Zuzel, G.

2013-11-22

The DarkSide staged program utilizes a two-phase time projection chamber (TPC) with liquid argon as the target material for the scattering of dark matter particles. Efficient background reduction is achieved using low radioactivity underground argon as well as several experimental handles such as pulse shape, ratio of ionization over scintillation signal, 3D event reconstruction, and active neutron and muon vetos. The DarkSide-10 prototype detector has proven high scintillation light yield, which is a particularly important parameter as it sets the energy threshold for the pulse shape discrimination technique. The DarkSide-50 detector system, currently in commissioning phase at the Gran Sasso Underground Laboratory, will reach a sensitivity to dark matter spin-independent scattering cross section of 10^-45 cm² within 3 years of operation.

Radiological control guide for decommissioning of the TRIGA mark-2, 3

International Nuclear Information System (INIS)

Lee, Bong Jae

2000-08-01

The purpose of radiological control for TRIGA mark-2, 3 research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, is in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. In order to accomplish these goal, the radiological control guide will be prepared during the decommissioning activities. Therefore, it is expected that this technical report can be used in preparing radiological control guide for safety decommissioning of the TRIGA mark-2, 3

Holifield Radioactive Ion Beam Facility Development and Status

CERN Document Server

Tatum, Alan

2005-01-01

The Holifield Radioactive Ion Beam Facility (HRIBF) is a national user facility dedicated to nuclear structure, reactions, and nuclear astrophysics research with radioactive ion beams (RIBs) using the isotope separator on-line (ISOL) technique. An integrated strategic plan for physics, experimental systems, and RIB production facilities have been developed and implementation of the plan is under way. Specific research objectives are defined for studying the nature of nucleonic matter, the origin of elements, solar physics, and synthesis of heavy elements. Experimental systems upgrade plans include new detector arrays and beam lines, and expansion and upgrade of existing devices. A multifaceted facility expansion plan includes a $4.75M High Power Target Laboratory (HPTL), presently under construction, to provide a facility for testing new target materials, target geometries, ion sources, and beam preparation techniques. Additional planned upgrades include a second RIB production system (IRIS2), an external axi...

Preclosure Safety Analysis Guide

International Nuclear Information System (INIS)

D.D. Orvis

2003-01-01

A preclosure safety analysis (PSA) is a required element of the License Application (LA) for the high- level radioactive waste repository at Yucca Mountain. This guide provides analysts and other Yucca Mountain Repository Project (the Project) personnel with standardized methods for developing and documenting the PSA. The definition of the PSA is provided in 10 CFR 63.2, while more specific requirements for the PSA are provided in 10 CFR 63.112, as described in Sections 1.2 and 2. The PSA requirements described in 10 CFR Part 63 were developed as risk-informed performance-based regulations. These requirements must be met for the LA. The PSA addresses the safety of the Geologic Repository Operations Area (GROA) for the preclosure period (the time up to permanent closure) in accordance with the radiological performance objectives of 10 CFR 63.111. Performance objectives for the repository after permanent closure (described in 10 CFR 63.113) are not mentioned in the requirements for the PSA and they are not considered in this guide. The LA will be comprised of two phases: the LA for construction authorization (CA) and the LA amendment to receive and possess (R and P) high-level radioactive waste (HLW). PSA methods must support the safety analyses that will be based on the differing degrees of design detail in the two phases. The methods described herein combine elements of probabilistic risk assessment (PRA) and deterministic analyses that comprise a risk-informed performance-based safety analysis. This revision to the PSA guide was prepared for the following objectives: (1) To correct factual and typographical errors. (2) To provide additional material suggested from reviews by the Project, the U.S. Department of Energy (DOE), and U.S. Nuclear Regulatory Commission (NRC) Staffs. (3) To update material in accordance with approaches and/or strategies adopted by the Project. In addition, a principal objective for the planned revision was to ensure that the methods and

Installation of a radioactive waste disposal facility. The necessity of building up durable links between the general public and radioactive waste. Feedback from experience in France

International Nuclear Information System (INIS)

Comte, Annabelle; Farin, Sebastien

2015-01-01

2013 has been a banner year for Andra with widespread discussions on the question of long-term management of radioactive waste: a nationwide public discussion about the planned Cigeo deep disposal facility has been organized and national discussions on the energy source transition had inevitably brought up the question of what to do with future radioactive waste to be produced under the various scenarios put forward. In spite of an open institutional framework, with numerous legal provisions for citizen participation, 2013 showed that creation of a radioactive waste disposal facility is not, and cannot be, a question dealt with like breaking news, within a given temporal or spatial perimeter. Any attempts to bring up the subject under the spotlight of public scrutiny inevitably shift the discussions away from their central theme and abandon the underlying question - what should be done with the existing radioactive waste and the waste that is bound to be produced? - to move on to the other major question: ''Should we stop using nuclear power or not?'', which takes us away from our responsibilities towards future generations. Daring to face the question, anchor it in citizen discussions, and create awareness of our duties towards coming generations: this is the challenge that Andra had already set itself several years ago. Our position is a strong one; rather than seeking to mask the problem of radioactive waste, we must face up to our responsibilities: the waste is already there, and we have to do something with it. It will take time to be successful here. Long-term management of radioactive waste is clearly a really long-term matter. All the experience in the field has shown that it involves patience and careful listening, and requires building up a basis for solid trust among the potential neighboring population, who are the most directly concerned. Durable proximity human investment is one of the key factors of success. For over 20 years now

Installation of a radioactive waste disposal facility. The necessity of building up durable links between the general public and radioactive waste. Feedback from experience in France

Energy Technology Data Exchange (ETDEWEB)

Comte, Annabelle; Farin, Sebastien [Andra, Chatenay-Malabry (France)

2015-07-01

2013 has been a banner year for Andra with widespread discussions on the question of long-term management of radioactive waste: a nationwide public discussion about the planned Cigeo deep disposal facility has been organized and national discussions on the energy source transition had inevitably brought up the question of what to do with future radioactive waste to be produced under the various scenarios put forward. In spite of an open institutional framework, with numerous legal provisions for citizen participation, 2013 showed that creation of a radioactive waste disposal facility is not, and cannot be, a question dealt with like breaking news, within a given temporal or spatial perimeter. Any attempts to bring up the subject under the spotlight of public scrutiny inevitably shift the discussions away from their central theme and abandon the underlying question - what should be done with the existing radioactive waste and the waste that is bound to be produced? - to move on to the other major question: ''Should we stop using nuclear power or not?'', which takes us away from our responsibilities towards future generations. Daring to face the question, anchor it in citizen discussions, and create awareness of our duties towards coming generations: this is the challenge that Andra had already set itself several years ago. Our position is a strong one; rather than seeking to mask the problem of radioactive waste, we must face up to our responsibilities: the waste is already there, and we have to do something with it. It will take time to be successful here. Long-term management of radioactive waste is clearly a really long-term matter. All the experience in the field has shown that it involves patience and careful listening, and requires building up a basis for solid trust among the potential neighboring population, who are the most directly concerned. Durable proximity human investment is one of the key factors of success. For over 20 years now

CP violation and the matter-antimatter asymmetry of the Universe

International Nuclear Information System (INIS)

Hambye, T.

2012-01-01

In our everyday environment one observes only matter. That is quite a fortunate situation... Any sizeable presence of antimatter on Earth, from the enormous energy it would release through annihilation with matter, would prevent us talking about it. For the physicist this fact, at first sight obvious, is nevertheless a kind of surprise: antimatter, which is observed in cosmic rays, in radioactive decays of nuclei, which has been copiously produced and extensively studied in accelerators and which is nowadays currently used in hospitals, turns out to have pretty much the same properties as matter. Moreover, the fact that matter dominates appears to be a general property of our Universe: no evidence of large quantities of antimatter has been observed at any distance from us. Why would matter have taken the advantage on antimatter? In this short review we explain how, through a limited number of basic elements, one can find answers to this question. Matter and antimatter have, in fact, not exactly the same properties: from laboratory experiments CP conservation is known not to be a fundamental law of nature. (author)

The ORPHEUS dark matter experiment

International Nuclear Information System (INIS)

Abplanalp, M.; Konter, J.A.; Mango, S.; Perret-Gallix, D.; Kainer, K.U.; Knoop, K.M.

1996-01-01

A progress report of the ORPHEUS dark matter experiment in the Bern Underground Laboratory is presented. A description of the ORPHEUS detector and its sensitivity to WIMPs is given. The detector will consist of 1 to 2 kg Sn granules operating in a magnetic field of approximately 320 G and at a temperature of 50 mK. In the first phase, the detector will be read out by conventional pickup coils, followed by a second phase with SQUID loops. Preliminary results on background and radioactivity measurements are shown. (orig.)

Radioactive wastes in Oklo; Desechos radiactivos en Oklo

Energy Technology Data Exchange (ETDEWEB)

Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2006-07-01

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

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.)

NRC perspective on extended on-site storage of low-level radioactive waste after 1993

International Nuclear Information System (INIS)

Remick, Forrest J.

1992-01-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires that each State, which has not provided for disposal capacity by January 1, 1993, must take title and possession of the low-level radioactive wastes generated in the State. If the states do not take title and possession of the wastes, the rebates to which the states would have been entitled to would be returned to the waste generators. in considering the matter, the Commission solicited comments from States) low-level radioactive waste compacts, local governments, and the general public so that the public's views could be factored into the Commission's deliberations on this issue. This paper addresses the current status of NRC positions on the adequacy of the NRC's existing regulatory framework associated with the title transfer provisions of the LLRWPAA and the Commission's views on extended on-site storage of low-level radioactive wastes after the 1993 and 1996 milestones. (author)

A two-zone cosmic ray propagation model and its implication of the surviving fraction of radioactive cosmic ray isotopes

International Nuclear Information System (INIS)

Simon, M.; Scherzer, R.; Enge, W.

1977-01-01

In cosmic ray propagation calculations one can usually assume a homogeneous distribution of interstellar matter. The crucial astrophysical parameters in these models are: The path length distribution, the age of the cosmic ray particles and the interstellar matter density. These values are interrelated. The surviving fraction of radioactive cosmic ray isotopes is often used to determine a mean matter density of that region, where the cosmic ray particles may mainly reside. Using a Monte Carlo Propagation Program we calculated the change in the surviving fraction quantitatively assuming a region around the sources with higher matter density. (author)

Radioactive Materials in Medical Institutions as a Potential Threat

International Nuclear Information System (INIS)

Radalj, Z.

2007-01-01

In numerous health institutions ionizing sources are used in everyday practice. Most of these sources are Roentgen machines and accelerators which produce radiation only when in use. However, there are many institutions, e.g., Nuclear medicine units, where radioactive materials are used for diagnostic and therapeutic purposes. This institutions store a significant amount of radioactive materials in form of open and closed sources of radiation. Overall activity of open radiation sources can reach over a few hundred GBq. Open sources of radiation are usually so called short-living isotopes. Since they are used on daily basis, a need for a continuous supply of the radioactive materials exists (on weekly basis). Transportation phase is probably the most sensitive phase because of possible accidents or sabotage. Radiological terrorism is a new term. Legislation in the area of radiological safety is considered complete and well defined, and based on the present regulatory mechanism, work safety with radiation sources is considered relatively high. However, from time to time smaller accidents do happen due to mishandling, loose of material (possible stealing), etc. Lately, the safety issue of ionizing sources is becoming more important. In this matter we can expect activities in two directions, one which is going towards stealing and 'smuggling' of radioactive materials, and the other which would work or provoke accidents at the location where the radiation sources are.(author)

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.

A guide to archival collections relating to radioactive fallout from nuclear weapon testing

International Nuclear Information System (INIS)

1989-10-01

This guide has been prepared by professional historians who have a working knowledge of many of the record collections, included in the following pages. In describing materials, they have tried to include enough information so that persons unfamiliar with the complexities of large record systems will be able to determine the nature of the information in, and the quality of, each record collection. The guide is organized alphabetically by the means of the record repositories, not by the organizations which have custody of the records. It should be noted that arrangement by location does not reveal at a single glance all of the materials that may have originated in a specific laboratory, research center, or government agency. For example, records originated in one of the Atomic Energy Commission's national laboratories may, in some cases, be listed under the Federal Records Centers to which they have been retired. Thus, this guide includes an index of agencies originating documents and pages listing those agencies

Prediction of Radioactive Material Proliferation in Abukuma Basin using USLE

Science.gov (United States)

Yi, C. J.

2014-12-01

Due to the nuclear-power plant accident after the 2011 Great East Japan Earthquake and Tsunami, the residents who had resided within 20 km from the Daiichi Fukushima Nuclear Power Plant had forced to leave their hometown. The impacts by the radioactive contamination extended to numerous social elements, such as food, economy, civil engineering, community rebuilding, etc. Japanese government agencies have measured the level of radioactive contamination in urban, agricultural area, forest, riverine and ocean. The research found that the concentration level of cesium-137 (137Cs) is higher in the forest than an open area such as paddy field or rural town. Litter layers and surface layers, especially, are found to be significantly contaminated. The study calculated the estimation of contaminated soil erosion using the USLE which the idea is based on scenario that addresses a question, what if 137Cs would carry out from the forest after intensive rainfall. Predicting radioactively contaminated areas after intense rainfall is a critical matter for the future watershed risk management.

Stakeholder involvement techniques. A short guide and annotated bibliography

International Nuclear Information System (INIS)

2005-01-01

The Forum on Stakeholder Confidence (FSC) was created under a mandate from the Radioactive Waste Management Committee (RWMC) of the OECD Nuclear Energy Agency (NEA) to facilitate the sharing of international experience in addressing the societal dimension of radioactive waste management. It explores means of ensuring an effective dialogue amongst all stakeholders, and considers ways to strengthen confidence in decision-making processes. FSC documents may be obtained online at www.nea.fr/html/rwrnifsc.html. OECD countries are increasingly implementing forms of participatory democracy that will require new or enhanced forms of dialogue amongst a broader range of concerned parties. The 4. regular FSC meeting held in Paris in May 2003 included a topical session on Stakeholder involvement tools: Criteria for choice and evaluation. The internal Minutes of the 4. meeting noted, in response to the discussions initiated by this topical session: 'Given that FSC members have one specific issue - radioactive waste management (RWM) - to deal with, a continuing relationship and dialogue among stakeholders seems important. What is desired is a well-informed citizen, because this is - in the end - an issue of democracy. Perhaps we have suffered in our field from a lack of recognition that RWM, like others, is an issue of democracy as well as a technical one'. At the close of the topical session, it was agreed that the FSC would prepare a short guide on stakeholder involvement techniques. The present guide approaches the topic from the point of view of radioactive waste management. However, because dialogue and deliberation techniques can be used in many fields, it will be of interest to a wide readership. It includes an annotated bibliography pointing to easily accessible handbooks and other resources. (author)

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

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The safe management of radioactive waste from mining and milling activities

International Nuclear Information System (INIS)

Reisenweaver, D.W.

2002-01-01

The IAEA is developing a Safety Guide for the management of radioactive waste from the mining and milling of uranium and thorium ores. This new Safety Guide will provide information that has been requested by Member States concerning the safe management of these wastes. The guide includes some new concepts, but they are intended to be reasonable and provide appropriate safety conditions for the workers, general public and the environment. The Regulatory Authorities of individual countries are responsible for establishing and implementing the regulatory framework through the development of appropriate rules, criteria and guidelines and establishing a licensing framework. The IAEA has issued a number of publications that provide requirements and guidance for the protection of workers, public and the environment. The overall objective and subsidiary principles developed explicitly for the management of radioactive waste should emphasize that the protection of the public from the beginning of operation to post-closure should be considered in its entity from the beginning of the design of the facility. The Safety Guide acknowledges that mining and milling wastes will contain non radiological hazards, in addition to the radiological hazards. The development of the waste management strategy is usually a complex process that aims to achieve a reasonable balance between the often conflicting goals - maximizing risk reduction versus minimizing financial expenditures. The evaluation criteria and procedures used to select the preferred option/and or development of the waste management strategy should be clearly defined and acceptable for the different parties interested in the project. This includes the public. A safety assessment should be performed to indicate how the design of the waste management facilities provides the optimum protection for the workers, public and environment using safety-type indicators. (author)

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

Concentration dynamics in lakes and reservoirs. Studies using radioactive tracers

International Nuclear Information System (INIS)

Gilath, Ch.

1983-01-01

The use of radioactive tracers for the investigation of concentration dynamics of inert soluble matter in lakes and reservoirs is reviewed. Shallow and deep stratified lakes are considered. The mechanism of mixing in lakes, flow pattern and input - output response are discussed. The methodology of the use of radioactive tracers for concentration dynamic studies is described. Examples of various investigations are reviewed. The dynamics of shallow lakes can be found and expressed in terms of transfer functions, axial dispersion models, residence time distributions and sometimes only semiquantitative information about the flow pattern. The dynamics of deep, stratified lakes is more complex and difficult to investigate with tracers. Flow pattern, horizontal and vertical eddy diffusivities, mass transfer between the hypolimnion and epilimnion are tools used for describing this dynamics. (author)

Argentina Nuclear Regulatory Authority and the final disposition gives to radioactive wastes

International Nuclear Information System (INIS)

Petraits, E.; Siraky, G.; Novo, R.

1998-01-01

This work describes the alignment legislative and regulator in which is carried out the final disposition the radioactive wastes in the Argentina Republic . Timbers the activities are presented the Authority Nuclear Regulator (RNA) and the applied focuses in connection with the inspections to the facilities, the evaluations security the associate systems and the collaboration with the international organizations in this matter

User's guide to the repository intrusion risk evaluation code INTRUDE

International Nuclear Information System (INIS)

Nancarrow, D.J.; Thorne, M.C.

1986-05-01

The report, commissioned by the Department of the Environment as part of its radioactive waste management research programme, constitutes the user's guide to the repository intrusion risk evaluation code INTRUDE. It provides an explanation of the mathematical basis of the code, the database used and the operation of the code. INTRUDE is designed to facilitate the estimation of individual risks arising from the possibility of intrusion into shallow land burial facilities for radioactive wastes. It considers a comprehensive inventory of up to 65 long-lived radionuclides and produces risk estimates for up to 20 modes of intrusion and up to 50 times of evaluation. (author)

Environmental education and digital resources as tools to raise awareness about radioactivity

International Nuclear Information System (INIS)

Araujo, Liderlanio de Almeida; Leite, Lucia Fernanda C. da Costa

2013-01-01

The objective of this study was to investigate the knowledge and awareness of students from the Liceu de Artes e Oficios localized in Recife-Pernambuco, about the theme radioactivity and environment in an interdisciplinary perspective. Thirty first-year high school students participated in this activity. Initially a questionnaire was applied to assess the students' prior knowledge on the topic. Following this stage, a lecture about radioactivity and its multiple uses for the benefit of society was presented to the students, together with a video about the story of radioactivity. A guided visit to the Museum of Radioactivity at the Universidade Federal de Pernambuco - UFPE, Brazil was also promoted. After these activities the questionnaire was reapplied to evaluate the development of students' knowledge. Research in textbooks and in the Internet was also carried out to evaluate the teaching resources used worldwide to study the nuclear issue. From this information a booklet, indicating the benefits of radioactivity was prepared by the students and later distributed to the community. After the activities there was evolution of knowledge on the subject radioactivity. Sixty seven percent of the students were able to make the calculations of half-life, 81% correctly explicated the definition of and αand β particles and γ radiation. Finally, 93% discussed about the contributions of Pierre and Marie Curie and Becquerel as well as their importance on the history of radioactivity. Dynamic activities should be encouraged so that students can learn to build knowledge with autonomy and, in turn, influence the construction of a new society. (author)

Environmental education and digital resources as tools to raise awareness about radioactivity

Energy Technology Data Exchange (ETDEWEB)

Araujo, Liderlanio de Almeida; Leite, Lucia Fernanda C. da Costa, E-mail: liderlanioalmeida@gmail.com, E-mail: lfernanda@unicap.br, E-mail: helena@unicap.br [Universidade Catolica de Pernambuco (UNICAP), Recife, PE (Brazil). Centro de Ciencias e Tecnologia. Curso de Licenciatura em Quimica; Aquino, Katia Aparecida da Silva, E-mail: aquino@ufpe.br [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Departamento de Energia Nuclear; Gazineu, Maria Helena Paranhos, E-mail: helenaparanhos@recife.ifpe.edu.br [Instituto Federal de Pernambuco (IFPE), Recife, PE (Brazil)

2013-07-01

The objective of this study was to investigate the knowledge and awareness of students from the Liceu de Artes e Oficios localized in Recife-Pernambuco, about the theme radioactivity and environment in an interdisciplinary perspective. Thirty first-year high school students participated in this activity. Initially a questionnaire was applied to assess the students' prior knowledge on the topic. Following this stage, a lecture about radioactivity and its multiple uses for the benefit of society was presented to the students, together with a video about the story of radioactivity. A guided visit to the Museum of Radioactivity at the Universidade Federal de Pernambuco - UFPE, Brazil was also promoted. After these activities the questionnaire was reapplied to evaluate the development of students' knowledge. Research in textbooks and in the Internet was also carried out to evaluate the teaching resources used worldwide to study the nuclear issue. From this information a booklet, indicating the benefits of radioactivity was prepared by the students and later distributed to the community. After the activities there was evolution of knowledge on the subject radioactivity. Sixty seven percent of the students were able to make the calculations of half-life, 81% correctly explicated the definition of and αand β particles and γ radiation. Finally, 93% discussed about the contributions of Pierre and Marie Curie and Becquerel as well as their importance on the history of radioactivity. Dynamic activities should be encouraged so that students can learn to build knowledge with autonomy and, in turn, influence the construction of a new society. (author)

Estimation of laid energy in a γ radioactive wastes barrel

International Nuclear Information System (INIS)

Mechitoua, B.

1999-01-01

The purpose is to reproduce the results of a study realised at the Cea Grenoble ((DTA/CEREM/DEM) with the MCNPP4B code and an internal DAM code. The calculations concern the estimation of the percentage of the energy transferred to the organic matters contained in gamma radioactive wastes casks. After the checking it is estimated with the calculations codes the percentages of energy laid in more realistic configurations. (N.C.)

Measurement of natural radioactivity in Chahbahar – Sistan and Blouchestan in Iran

Directory of Open Access Journals (Sweden)

Seyyed Abbas Hosseini

2014-05-01

Full Text Available Background: Natural radioactivity exposes radiation so that it goes whole body through different ways and causes diseases leading to death, if it is more than standard amount by ICRP. The aim of this study was to measure the amount of radioactivity in the soil, water and air of Chabahar city in Sistan and Baluchestan province, Iran. Material and Methods: A few locations of city were chosen as a sampling station. The study of drinking water radioactivity was performed in Bandargah and city square. Soil’ radioactivity tested in Tiss village and Shillat. Radioactivity measurement of air was performed in the above-mention places. The radioactivity of drinking water and soil were measured by using a coaxial detector Germanium with high purity. Results: Average concentrations of Ra-228, Th-222 and K-40 in soil and Ra-228 in piping drinking water and in consumed plant were 450±34.5 Bq/Kg, 28.5±2.5 Bq/Kg, 24.3±2.6 Bq/Kg and <2 Bq/L, respectively. The overall results demonstrated low levels of radioactivity (<2 mBq/L, and less levels of K-40, Ra-228 and Th-232 in soil. The Ra-228 concentrations measured in piping and underground water were generally below the detection limit. As there was lower radioactivity in comparison with international standards, there was not probably any disease. Absorbed dose in air was 485.5±20 nanoGy/h and effective dose was 596±24.5, 5 µSv. Conclusion: It is found that there is a significant difference in average of 228Ra, 40K and 232Th in the area relative to some points in the world that may be because of organic matter and microbial biomass. Different factors effect on radioactivity of samples. This region shows the least ionizing radiation.

Classification of Radioactive Waste. General Safety Guide (Russian Edition); Классификация радиоактивных отходов. Руководство по безопасности

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-02-15

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste.

Survey of environmental radiation in Kawamata-machi, Fukushima-ken (2). Radioactive cesium in wild mushroom

International Nuclear Information System (INIS)

Inagaki, Masayo; Yamanishi, Hirokuni; Wakabayashi, Genichiro; Hohara, Sin-ya; Itoh, Tetsuo; Shirasaka, Norifumi; Tanesaka, Eiji; Okumura, Hiroshi; Furukawa, Michio

2013-01-01

Large amount of radioactive cesium was emitted from the TEPCO Fukushima Dai-ichi nuclear power plant by the accident into atmospheric air, and a part of the radioactivity was brought to the ground by rain and snowfall. The Yamakiya district in Kawamata-machi, Fukushima is specified as the prepared evacuation zone. The authors collected wild mushrooms in this district as samples with gentle guide of local mushroom lovers in October, 2012. The kinds of mushroom were specified by the mushroom specialist. 16 kinds of mushrooms have been extracted. The extracted mushroom was brought back to the university. The concentration of radioactive cesium was measured by means of the hyperpure germanium semiconductor detector. The concentrations were ranged from 0.5 to 2600 Bq/g, and were different with points of sampling and kinds. The concentrations were compared with before washing and after washing by means of ultrasonic cleaning. The amount of radioactive cesium reduced to the range from 30% to 60% of the before washing. (author)

Studies of radioactivity of vegetables: determination of transfer factors 85Sr and 134Cs in some vegetables

International Nuclear Information System (INIS)

Oncsik, M.B.

1999-01-01

The radioisotope uptake of potato and culinary dry bean was studied in field experiments on meadow soil enriched with vermiculite and humanite by artificial soil contamination. The isotope uptake from the soil was characterized by a transfer factor (TF). Based on the results of the potato experiment it was found that the TF value characterizing the 134 Cs contamination of the crop, changed between 1.31 - 0.77*10 -4 m 2 (kg dry matter) -1 on high humus content soil (treated with humanite) and on soil treated with vermiculite, while it was 22-45 % higher in plants grown on the radioactive control plots. lt was 1.69*10 -4 m 2 (kg dry matter)2 -1 in average. The TF values of 85 Sr uptake of potato are several times higher than those of experiments treated by isotope 134 Cs. The TF values fluctuated between 5.30-7.33*10 -4 m 2 (kg dry matter) -1 in soils treated with the additives, while on the plots with radioactive contamination it was 8.42*10 -4 m 2 (kg dry matter) -1 . Based on the results of 134 Cs studies of edible part of dry bean, it could be stated that after the soil contamination the TF value was 0.99*10 -4 m 2 (kg dry matter) -1 in average. According to the activity results of the experiments there was significant difference between the contamination of the plant parts. Refs. 6 (author)

RadCat 3.0 user guide.

Energy Technology Data Exchange (ETDEWEB)

Hinojosa, Daniel; Penisten, Janelle J.; Dennis, Matthew L.; Osborn, Douglas M.; Weiner, Ruth F.; Heames, Terence John; Marincel, Michelle K.

2009-05-01

RADTRAN is an internationally accepted program and code for calculating the risks of transporting radioactive materials. The first versions of the program, RADTRAN I and II, were developed for NUREG-0170 (USNRC, 1977), the first environmental statement on transportation of radioactive materials. RADTRAN and its associated software have undergone a number of improvements and advances consistent with improvements in both available data and computer technology. The version of RADTRAN currently bundled with RadCat is RADTRAN 6.0. This document provides a detailed discussion and a guide for the use of the RadCat 3.0 Graphical User Interface input file generator for the RADTRAN code. RadCat 3.0 integrates the newest analysis capabilities of RADTRAN 6.0 which includes an economic model, updated loss-of-lead shielding model, and unit conversion. As of this writing, the RADTRAN version in use is RADTRAN 6.0.

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.)

Security in transport, storage and disposal of radioactive materials, providing to the department of nuclear medicine in hospitals Rafael Angel Calderon Guardia, San Juan de Dios and Mexico

International Nuclear Information System (INIS)

Elizondo Valle, Alejandro; Jimenez Mendez, Christian; Leiton Araya, Christopher; Villalobos Rodriguez, Geovanny; Leal Vega, Olga Maritza; Lopez Gatjens, Santiago

2010-01-01

The security is analysed for the transport and storage of radioactive sources and the management of radioactive waste product of practices and interventions in nuclear medicine services in hospitals Calderon Guardia, San Juan de Dios and Mexico. The objective is to assess the compliance with current regulations, the effectiveness and efficiency of the same. The security and compliance with current regulations were considered related to the transport of radioactive sources by the two private companies that provide this service, from the Juan Santamaria airport customs to three hospitals evaluated. Compliance with national and international rules on storage of radioactive sources and waste materials were analyzed. For this has been studied Costa Rican law and the recommendations of international organizations related to the subject matter, in the three nuclear medicine services valued. The national and international background related to radiological accidents occurred with radioactive sources during transport, storage and waste were revised, where highlights that in most cases, these accidents occurred for breach of the regulations established. Studies in Costa Rica on radioactive waste management were analysed, and the current status of nuclear medicine services in terms of radiation safety, which helped with the investigation. The compliance and regulations were analyzed by the result of observation and interviews during development, to finally make a series of findings and provide recommendations that are considered relevant. Various variants and indicators that are defined in the theoretical framework were used; also, the strategy of methodology is described. The purpose of the work has been to provide a scientific nature, and that methodology met the objectives, offering an approach from different angles and the actors involved, and a critical and objective analysis strictly in order to contribute to public health. The research is a valuable tool that provides

Research of high energy radioactivity identification detector

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Kyun; Lee, Yong Bum; Hwang, Jong Sun; Choi, Seok Ki

1998-07-01

{Delta} {Epsilon}-{Epsilon} telescope high radioactivity detector was designed, fabricated, and tested at the 35 MeV proton energy. We developed the computer code to calculate the energy loss of projectile ions in the matter. Using the code, we designed and fabricated a detector to measure 15-50 MeV protons. The detector was successfully tested to measure the energy of protons and deuterons and to identify the ions. In future, we would like to extend the present result to the development of a higher energy proton detector and a heavy ion detector. (author). 10 refs., 3 tabs., 14 figs

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.)

Production of adsorbent from palm shell for radioactive iodine scrubbing process

International Nuclear Information System (INIS)

Mohamad Azman Che Mat Isa; Ku Halim Ku Hamid; Muhd Noor Muhd Yunus; Mohamad Puad Abu; Abdul Halim Badaruddin; Mohammad Nizammudin Abd Aziz; Muhd Ridwan Abdul Rahim

2010-01-01

The biggest biomass source in Malaysia comes from oil palm industry. According to the statistic of year 2004, Malaysia produced 40 million tones per year of biomass which 30 million tones of biomass originated from the oil palm industries. Therefore, the biomass waste such as palm kernel shell can be used to produce granular adsorbent for radioactive materials. For that reason, a newly system, called Rocking Kiln - Fluidized Bed (RK - FB) was developed to utilize large amount of the biomass to produce high value added product. Charcoal or chemically produced activated carbon could be produced by using the kiln. Washing process was introduced to remove particles, minerals and volatile matters from charcoal produced and then would create more surface area in the adsorbent by creating more active sites. In this research, the adsorbent produced was used to scrub iodine 131. In nuclear power reactor, iodine isotope 131 is produced during nuclear fission, and this elementary radioactive iodine may pollute exhaust air streams that could cause thyroid cancer. For removal of radioactive iodine, normally a potassium iodide - impregnated activated carbon (KI - AC) is used. Thus, a process will be developed to produce KI - AC and this product will be used to calculate the efficiency to remove the radioactive iodine 131.The results obtain show that adsorbent produced has a high potential to be used in radioactive adsorbing and likely more economics. This paper will elaborate further the experimental set-up of in Kiln - Fluidized Bed (RK - FB), adsorbent quality and radioactive scrubbing process. (author)

Hanford tank clean up: A guide to understanding the technical issues

International Nuclear Information System (INIS)

Gephart, R.E.; Lundgren, R.E.

1995-01-01

One of the most difficult technical challenges in cleaning up the US Department of Energy's (DOE) Hanford Site in southeast Washington State will be to process the radioactive and chemically complex waste found in the Site's 177 underground storage tanks. Solid, liquid, and sludge-like wastes are contained in 149 single- and 28 double-shelled steel tanks. These wastes contain about one half of the curies of radioactivity and mass of hazardous chemicals found on the Hanford Site. Therefore, Hanford cleanup means tank cleanup. Safely removing the waste from the tanks, separating radioactive elements from inert chemicals, and creating a final waste form for disposal will require the use of our nation's best available technology coupled with scientific advances, and an extraordinary commitment by all involved. The purpose of this guide is to inform the reader about critical issues facing tank cleanup. It is written as an information resource for the general reader as well as the technically trained person wanting to gain a basic understanding about the waste in Hanford's tanks -- how the waste was created, what is in the waste, how it is stored, and what are the key technical issues facing tank cleanup. Access to information is key to better understanding the issues and more knowledgeably participating in cleanup decisions. This guide provides such information without promoting a given cleanup approach or technology use

Hanford tank clean up: A guide to understanding the technical issues

Energy Technology Data Exchange (ETDEWEB)

Gephart, R.E.; Lundgren, R.E.

1995-12-31

One of the most difficult technical challenges in cleaning up the US Department of Energy`s (DOE) Hanford Site in southeast Washington State will be to process the radioactive and chemically complex waste found in the Site`s 177 underground storage tanks. Solid, liquid, and sludge-like wastes are contained in 149 single- and 28 double-shelled steel tanks. These wastes contain about one half of the curies of radioactivity and mass of hazardous chemicals found on the Hanford Site. Therefore, Hanford cleanup means tank cleanup. Safely removing the waste from the tanks, separating radioactive elements from inert chemicals, and creating a final waste form for disposal will require the use of our nation`s best available technology coupled with scientific advances, and an extraordinary commitment by all involved. The purpose of this guide is to inform the reader about critical issues facing tank cleanup. It is written as an information resource for the general reader as well as the technically trained person wanting to gain a basic understanding about the waste in Hanford`s tanks -- how the waste was created, what is in the waste, how it is stored, and what are the key technical issues facing tank cleanup. Access to information is key to better understanding the issues and more knowledgeably participating in cleanup decisions. This guide provides such information without promoting a given cleanup approach or technology use.

Development of radiometric methods for radioactive waste characterization

International Nuclear Information System (INIS)

Tessaro, Ana Paula Gimenes

2015-01-01

The admission of radioactive waste in a final repository depends among other things on the knowledge of the radioisotopic inventory of the waste. To obtain this information it is necessary make the primary characterization of the waste so that it is composition is known, to guide the next steps of radioactive waste management. Filter cartridges that are used in the water polishing system of IEA-R1 research reactor is one of these wastes. The IEA-R1 is a pool-type research reactor, operating between 2 and 5 MW that uses water as coolant, moderator and biological shield. Besides research, it is used for production of radioisotopes and irradiation of samples with neutron and gamma beams. It is located in the Nuclear and Energy Research Institute at the University of Sao Paulo campus. The filter cartridges are used to retain particles that are suspended in the cooling water. When filters become saturated and are unable to maintain the flow within the established limits, they are replaced and disposed of as radioactive waste. After a period of decay, they are sent to the Radioactive Waste Management Department. The aim of this work is to present the studies to determine the activity of gamma emitters present in the cartridge filters. The activities were calculated using the dose rates measured with hand held detectors, after the ratios of the emission rates of photons were evaluated by gamma spectrometry, by the Point Kernel method, which correlates the activity of a source with dose rates at various distances. The method described can be used to determine routinely the radioactive inventory of these filters, avoiding the necessity of destructive radiochemical analysis, or the necessity of calibrating the geometry of measurement. (author)

Stepwise Decision Making for Long-Term Radioactive Waste Management

International Nuclear Information System (INIS)

Pescatore, Claudio; Vari, Anna

2003-01-01

Consideration is increasingly being given, in radioactive waste management (RWM), to concepts such as 'stepwise decision making' and 'adaptive staging' in which the public, and especially the local communities, are also meaningfully involved in the review and planning of developments. The key feature of these concepts is development by steps or stages that are reversible, within the limits of practicability and provided they meet the requirements of an acceptable safety case. Stepwise decisions are designed to provide reassurance that actions can be reversed if experience shows them to have adverse or unwanted effects. Stepwise decision making has thus come to the fore as being especially important for making progress for radioactive waste management in a manner which is acceptable to large sectors of society. Despite its early identification within the RWM community as an important means for reaching decision in which there is broad-based confidence, stepwise decision making has not been widely debated. Accepted guiding principles of any such process have not yet been formulated, its roots in empirical social science research have not been fully reviewed, nor the difficulties of its implementation analysed. This paper reviews the current developments regarding stepwise decision making in RWM with the aim to pinpoint where it stands, to highlight its societal dimension, to analyse its roots in social sciences, and to identify guiding principles and issues in implementation. It is observed that there is convergence between the approach taken by the practitioners of RWM and the indications received from field studies in social research, and that general guiding principles can be proposed at least as a basis for further discussion. A strong basis for dialogue across disciplines thus exists. General methodological issues are also identified. This paper was developed in the framework of the activities of the NEA Forum on Stakeholder Confidence, which is presented in a

Management system for regulating transport of radioactive material

International Nuclear Information System (INIS)

Lopez Vietri, Jorge; Capadona, Nancy; Barenghi, Leonardo

2008-01-01

Full text: The objective of this paper is to describe the main characteristics and fundamentals of the Nuclear regulatory Authority's (Autoridad Regulatoria Nuclear, ARN) management system applied to the regulation of transport of radioactive material, in Argentina. In the frame of ARN's quality policy, 'Protection against ionizing radiation on transport of radioactive materials' was selected as one of the regulatory processes, named TRM process from now on. ARN's quality management system is integrally based on ISO 9000 system addressed to help organizations in designing and implementing their quality management systems. TRM process was split into five sub processes in order to facilitate the implementation of quality system. Such sub processes were defined taking account of the main functions developed by ARN in the branch of safe transport of radioactive materials and are listed below: 1) Development and updating of standards and regulatory guides; 2) Licensing of packages, special radioactive materials and consignments of radioactive materials; 3) Compliance assurance during the transport of radioactive materials, and 4) Training, advising and communications. For each of these sub processes were specified their objectives, inputs, activities and outputs, the clients and stakeholders, responsibilities, supporting documents, control of documents and records, control of non-conformances, monitoring and measurements, audits, feedback and improvement. It was decided to develop a quality plan to organize and manage activities to meet quality requirements, to optimize the use of limited resources of the organization and to be used as a basis for monitoring and assessing compliance with the requirements, both internal and external. Supporting documents for sub processes were issued, validated, reviewed and improved as an essential point to implement continuous improving. Simultaneously, some indexes were defined to monitor and measure the sub processes as a way to show

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

Remote radioactive waste drum inspection with an autonomous mobile robot

International Nuclear Information System (INIS)

Heckendorn, F.M.; Ward, C.R.; Wagner, D.G.

1992-01-01

An autonomous mobile robot is being developed to perform remote surveillance and inspection task on large numbers of stored radioactive waste drums. The robot will be self guided through narrow storage aisles and record the visual image of each viewable drum for subsequent off line analysis and archiving. The system will remove the personnel from potential exposure to radiation, perform the require inspections, and improve the ability to assess the long term trends in drum conditions

Organization and staffing of the regulatory body for nuclear facilities. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this safety guide is to provide recommendations for national authorities on the appropriate management system, organization and staffing for the regulatory body responsible for the regulation of nuclear facilities in order to achieve compliance with the applicable safety requirements. This safety guide covers the organization and staffing in relation to nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And radioactive waste management facilities such as treatment, storage and disposal facilities. This safety guide also covers issues related to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation

Regulatory requirements for the use of consumer products containing radioactive substances

International Nuclear Information System (INIS)

Mason, G.C.; Paynter, R.A.; Schmitt-Hannig, A.; Sztanyik, L.B.

1996-01-01

In almost 100 years since the discovery of radioactivity, the properties of radioactive materials have been exploited in products such as clocks and watches incorporating luminous paint which are freely available to members of the public. Over time, regulatory authorities have felt it necessary to apply some degree of control to the supply and use of such products in order to protect public health. In many areas of radiation protection, national authorities take note of international recommendations when developing national standards, but the existing detailed guidance of the International Atomic Energy Agency (IAEA) for consumer products is incomplete and out of date. Recently, a thorough revision of the International Basic Safety Standards (BSS) has occurred, which has prompted a review and revision of the related guidance published by the IAEA. A draft Guide on Regulatory Requirements for the Use of Consumer Products Containing Radioactive Substances has now been completed and is currently under review within the IAEA's system for development of documents in its Safety Series of publications. (author)

NAIR: handbook on the national arrangements for incidents involving radioactivity

International Nuclear Information System (INIS)

1987-01-01

A revised handbook on the national arrangements for incidents involving radioactivity (NAIR) has been published. Following brief introductory sections on the administrative aspects and operational aspects, the main part of the handbook is devoted to operational and call-out lists including an index of police forces served by NAIR, an index of establishments providing assistance under NAIR, sources of stage 1 and stage 2 assistance for each police constabulary, hospitals prepared to accept contaminated casualties and to assist with decontamination of personnel, and hospitals prepared to advise on the treatment and admission of casualties exposed to large doses of radiation. Technical appendices are also given on radiological protection in NAIR incidents, instruments and equipment, radionuclide data and a guide to suitable detectors, package and source identification and disposal of radioactive materials involved in NAIR accidents. (U.K.)

Canada's Intelligent Transportation Systems (ITS) : deployment and integration plan : applicant's guide

Science.gov (United States)

2000-02-01

This document is the applicant's guide for proposing intelligent transportation systems projects to Transport Canada and details such matters as eligibility, Transport Canada's program objectives and assessment of projects

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.

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)

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

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

Radioactive Waste Management Fellowship Program: Summary of program activities for calendar year 1986

International Nuclear Information System (INIS)

1987-01-01

This document describes a graduate fellowship program designed to guide future scientists and engineers toward a career in high level radioactive waste management. Oak Ridge Associated Universities administers this program on behalf of 17 participating universities. The report summarizes the background and qualifications of the last year's applicants and awardees and provides examples of the distributed literature describing the program. 8 figs

Physical chemistry characterization of soils of the Storage Center of Radioactive Wastes; Caracterizacion fisico-quimica de suelos del Centro de Almacenamiento de Desechos Radioactivos

Energy Technology Data Exchange (ETDEWEB)

Hernandez T, U. O.; Fernandez R, E. [Instituto Tecnologico de Toluca, Av. Tecnologico s/n, 52140 Metepec, Estado de Mexico (Mexico); Monroy G, F.; Anguiano A, J., E-mail: uohtrejo@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (MX)

2011-11-15

Any type of waste should be confined so that it does not causes damage to the human health neither the environment and for the storage of the radioactive wastes these actions are the main priority. In the Storage Center of Radioactive Wastes the radioactive wastes generated in Mexico by non energy applications are storage of temporary way. The present study is focused in determining the physical chemistry properties of the lands of the Storage Center of Radioactive Wastes like they are: real density, ph, conductivity percentage of organic matter and percentage of humidity. With what is sought to make a characterization to verify the reaction capacity of the soils in case of a possible flight of radioactive material. The results show that there are different density variations, ph and conductivity in all the soil samples; the ph and conductivity vary with regard to the contact time between the soil and their saturation point in water, for the case of the density due to the characteristics of the same soil; for what is not possible to establish a general profile, but is necessary to know the properties of each soil type more amply. Contrary case is the content of organic matter and humidity since both are in minor proportions. (Author)

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.)

Non-radioactive waste management in a Nuclear Energy Research Institution

Energy Technology Data Exchange (ETDEWEB)

Furusawa, Helio A.; Martins, Elaine A.J.; Cotrim, Marycel E.B.; Pires, Maria A. F., E-mail: helioaf@ipen.br, E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEM-SP), Sao Paulo, SP (Brazil). Centro de Quimica e Meio Ambiente

2013-07-01

For more than 50 years, non-radioactive materials have been used in processes at IPEN to support the nuclear fuel development and all related activities. Reagents, raw materials, products and by-products have been stored. Many of these are hazardous highly toxic or reactants materials. Some years ago actions sent part of these non-radioactive waste materials to proper disposal (technical incineration) resulting in an Institutional Non-Radioactive Waste Management Program. In 2005, an internal set of procedures and information entitled - Guia de Procedimentos para Armazenamento, Tratamento e Descarte de Residuos de Laboratorio Quimico - (Guide of Procedures for Storage, Treatment, and Disposal of Chemistry Laboratory Wastes) - was published to be used at the IPEN's facilities. A data base managed by software was created in order to allow the Units to input data and information about the routinely generated wastes and those already existing. Even after disposing so huge amount of wastes, a latent demand still exists. Several goals were achieved notably a well-organized and roomy space; safer storage places; local, state, and nationwide laws enforcement (for radioactive and non-radioactive materials); and improvement in chemicals control as hazardous and aged materials are more frequently disposed. A special stress was conducted to know and follow laws, regulations, and technical norms as the entire process is very detailed and this is not a day-by-day routine for the IPEN's technical personnel. The immediate consequence is that the safer the workplace the safer the nuclear related activities are done. (author)

Non-radioactive waste management in a Nuclear Energy Research Institution

International Nuclear Information System (INIS)

Furusawa, Helio A.; Martins, Elaine A.J.; Cotrim, Marycel E.B.; Pires, Maria A. F.

2013-01-01

For more than 50 years, non-radioactive materials have been used in processes at IPEN to support the nuclear fuel development and all related activities. Reagents, raw materials, products and by-products have been stored. Many of these are hazardous highly toxic or reactants materials. Some years ago actions sent part of these non-radioactive waste materials to proper disposal (technical incineration) resulting in an Institutional Non-Radioactive Waste Management Program. In 2005, an internal set of procedures and information entitled - Guia de Procedimentos para Armazenamento, Tratamento e Descarte de Residuos de Laboratorio Quimico - (Guide of Procedures for Storage, Treatment, and Disposal of Chemistry Laboratory Wastes) - was published to be used at the IPEN's facilities. A data base managed by software was created in order to allow the Units to input data and information about the routinely generated wastes and those already existing. Even after disposing so huge amount of wastes, a latent demand still exists. Several goals were achieved notably a well-organized and roomy space; safer storage places; local, state, and nationwide laws enforcement (for radioactive and non-radioactive materials); and improvement in chemicals control as hazardous and aged materials are more frequently disposed. A special stress was conducted to know and follow laws, regulations, and technical norms as the entire process is very detailed and this is not a day-by-day routine for the IPEN's technical personnel. The immediate consequence is that the safer the workplace the safer the nuclear related activities are done. (author)

Method and apparatus for the purification of a liquid contaminated with radioactive substances

International Nuclear Information System (INIS)

Mende, H.

1976-01-01

A method of and apparatus for the purification of a liquid contaminated with radioactive substances is described, wherein the liquid is infed to an evaporator in or with which there is connected a column having a multiplicity of superposed plates or floors. The vapor generated in the evaporator is guided through a washing or scrubbing liquid uniformly distributed at the floors and flowing in crosswise counterflow with regard to the vapor. The washing liquid at the floors is deflected a number of times in such a manner that the washing liquid itself together with the droplets entrained by the vapor are uniformly admixed and the washing liquid subjected to a constant intake of the radioactive substance

External Events Excluding Earthquakes in the Design of Nuclear Power Plants. Safety Guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide provides recommendations and guidance on design for the protection of nuclear power plants from the effects of external events (excluding earthquakes), i.e. events that originate either off the site or within the boundaries of the site but from sources that are not directly involved in the operational states of the nuclear power plant units. In addition, it provides recommendations on engineering related matters in order to comply with the safety objectives and requirements established in the IAEA Safety Requirements publication, Safety of Nuclear Power Plants: Design. It is also applicable to the design and safety assessment of items important to the safety of land based stationary nuclear power plants with water cooled reactors. Contents: 1. Introduction; 2. Application of safety criteria to the design; 3. Design basis for external events; 4. Aircraft crash; 5. External fire; 6. Explosions; 7. Asphyxiant and toxic gases; 8. Corrosive and radioactive gases and liquids; 9. Electromagnetic interference; 10. Floods; 11. Extreme winds; 12. Extreme meteorological conditions; 13. Biological phenomena; 14. Volcanism; 15. Collisions of floating bodies with water intakes and UHS components; Annex I: Aircraft crashes; Annex II: Detonation and deflagration; Annex III: Toxicity limits.

New Monitoring System to Detect a Radioactive Material in Motion

International Nuclear Information System (INIS)

Boudergui, Karim; Kondrasovs, Vladimir; Coulon, Romain; Corre, Gwenole; Normand, Stephane

2013-06-01

Illegal radioactive material transportation detection, by terrorist for example, is problematic in urban public transportation. Academics and industrials systems include Radiation Portal Monitor (RPM) to detect radioactive matters transported in vehicles or carried by pedestrians. However, today's RPMs are not able to efficiently detect a radioactive material in movement. Due to count statistic and gamma background, false alarms may be triggered or at the contrary a radioactive material not detected. The statistical false alarm rate has to be as low as possible in order to limit useless intervention especially in urban mass transportation. The real-time approach depicted in this paper consists in using a time correlated detection technique in association with a sensor network. It is based on several low-cost and large area plastic scintillators and a digital signal processing designed for signal reconstruction from the sensor network. The number of sensors used in the network can be adapted to fit with applications requirements or cost. The reconstructed signal is improved by comparing other approaches. This allows us to increase the device speed that has to be scanned while decreasing the risk of false alarm. In the framework of a project called SECUR-ED Secured Urban Transportation - European Demonstration, this prototype system will be used during an experiment in the Milan urban mass transportation. (authors)

Mind Over Matter: The Brain's Response to Drugs. Teacher's Guide.

Science.gov (United States)

National Inst. on Drug Abuse (DHHS/PHS), Rockville, MD.

This teacher's guide aims to develop an understanding among students grades 5 through 9 of the physical reality of drug use. Contents include: (1) "Brain Anatomy"; (2) "Nerve Cells and Neurotransmission"; (3) "Effects of Drugs on the Brain"; (4) "Marijuana"; (5) "Opiates"; (6) "Inhalants"; (7) "Hallucinogens"; (8) "Steroids"; (9) "Stimulants";…

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

A guide to ventilation requirements for uranium mines and mills. Regulatory guide G-221

International Nuclear Information System (INIS)

2003-06-01

The purpose of G-221 is to help persons address the requirements for the submission of ventilation-related information when applying for a Canadian Nuclear Safety Commission (CNSC) licence to site and construct, operate or decommission a uranium mine or mill. This guide is also intended to help applicants for a uranium mine or mill licence understand their operational and maintenance obligations with respect to ventilation systems, and to help CNSC staff evaluate the adequacy of applications for uranium mine and mill licences. This guide is relevant to any application for a CNSC licence to prepare a site for and construct, operate or decommission a uranium mine or mill. In addition to summarizing the ventilation-related obligations or uranium mine and mill licensee, the guide describes and discusses the ventilation-related information that licence applicants should typically submit to meet regulatory requirements. The guide pertains to any ventilation of uranium mines and mills for the purpose of assuring the radiation safety of workers and on-site personnel. This ventilation may be associated with any underground or surface area or premise that is licensable by the CNSC as part of a uranium mine or mill. These areas and premises typically include mine workings, mill buildings, and other areas or premises involving or potentially affected by radiation or radioactive materials. Some examples of the latter include offices, effluent treatment plants, cafeterias, lunch rooms and personnel change-rooms. (author)

The ActionScript 30 Quick Reference Guide

CERN Document Server

Stiller, David; deHaan, Jen; Richardson, Darren

2008-01-01

"No matter what your background, the pages that follow will provide you with some excellent knowledge, insight, and even a little bit of wisdom in the realm of Flash and ActionScript. Happy learning!"-- Branden Hall, from the ForewordWritten by Flash insiders with extensive knowledge of the technology, this guide is designed specifically to help Flash designers and developers make the leap from ActionScript 2.0 to the new object-oriented ActionScript 3.0 quickly and painlessly. Formatted so you can find any topic easily, ActionScript 3.0 Quick Reference Guide explains:Object-oriented programmi

Natural radioactivity of Loire river sediments: relations with the lithology

International Nuclear Information System (INIS)

Patryl, L.

2000-01-01

This study has been carried out on request of the Loire-Bretagne water agency by the Laboratory of geology of Tours univ. (EA2100 GeEAC) in collaboration with CEA-Le Ripault. The main objective was the study of the nature and distribution of natural radioactivity in the Loire river alluvial deposits, its origin in the rocks of the surrounding basins and its links with the alluvial petrography. The radioactive flux linked with the sediments of the bottom of the river has been also determined. The Loire river and its main affluents have been the object of radiological and petrographic analyses (grain size, sands and clays mineralogy, organic matter content). The average radioactivities of 40 K, 238 U and 228 Ac in the alluvial deposits are 934.3 ± 164.7 Bq.kg -1 , 50.6 ± 30.8 Bq.kg -1 and 28.8 ± 18.1 Bq.kg -1 , respectively. The average radioactivity of 238 U, 228 Ac and their daughter products is statistically higher in Loire superieure (Massif Central mounts) than in Loire moyenne (Paris basin). The activities of 238 U and 228 Ac are mainly influenced by the grain size of the alluvial deposits and by the mineralogical composition of the sand fraction. The alluvial deposits are mainly sandy and the coarse fraction is the most abundant. The primary radioactivity is carried by the few zircons of the sediments. The activity of the uranium and thorium families increase with the feldspars content. The fixation of radioactivity seems to be linked with the presence of clay minerals inside the weathered feldspar grains which are abundant in the sands. The radioactivity of the Loire river alluvial deposits shows no important changes with respect to the substratums because of a smoothing due to the predominance of longitudinal fluxes with respect to the lateral ones. The impact of an old uranium mine on the alluvial deposits of the Besbre river is detectable along about a tenth of km s downstream only. Because of the strong variations of radioactivity with granularity, a

A report on the environmental safety evaluation in sea disposal of radioactive wastes

International Nuclear Information System (INIS)

1976-01-01

In October 1976, the Atomic Energy Commission of Japan decided its policy regarding radioactive wastes. It is stated that the sea disposal of low-level solid wastes as test will be made from about 1978, and after the confirmation of the safety, full-scale sea disposal will then follow. In this field, studies have long been made in Japan and international organizations. Based on these results, the present report describes on the following matters: the amount of radioactive wastes and the activities for disposal, the safety of disposal packages, the state of prospective sites for sea disposal, the models of the sea, the estimation of radionuclide concentrations in the ocean, and the exposure doses of general people. (Mori, K.)

Radioactive contamination in the Netherlands caused by the nuclear reactor accident at Chernobyl

International Nuclear Information System (INIS)

1986-10-01

In this report of the Dutch Coordination Commission for Measurements of Radioactivity and Xenobiotic matters (CCRX) a detailed survey is presented of the spread of radioactive material over Europe as a consequence of the reactor accident in Chernobyl and of measurements of the contamination of the physical environment, food and human people in the Netherlands. The radiation burden for the Dutch people and the effects upon public health are estimated and a measuring program is introduced for monitoring the effects of the reactor accident upon the Dutch people. Finally a number of requirements are discussed on the base of the acquired experiments, to which future watching programs should satisfy. 24 refs.; 32 figs.; 16 tabs

Standard format and content for a license application to store spent fuel and high-level radioactive waste

International Nuclear Information System (INIS)

1989-09-01

Subpart B, ''License Application, Form, and Contents,'' of 10 CFR Part 72, ''Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste,'' specifies the information to be covered in an application for a license to store spent fuel in an independent spent fuel storage installation (ISFSI) or to store spent fuel and high-level radioactive waste in a monitored retrievable storage facility (MRS). However, Part 72 does not specify the format to be followed in the license application. This regulatory guide suggests a format acceptable to the NRC staff for submitting the information specified in Part 72 for license application to store spent fuel in an ISFSI or to store spent fuel and high-level radioactive waste in an MRS

When Nothing Matters Anymore: A Survival Guide for Depressed Teens.

Science.gov (United States)

Cobain, Bev

This guide provides adolescents with information on depression. An introduction discusses symptoms of depression and lists famous people who were known to be depressed. Part 1, "What's Wrong," explores how it feels to be depressed, the causes and types of depression, and the connections between depression, suicide, and drug and alcohol abuse. A…

Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities