WorldWideScience

Sample records for simulated radioactive materials

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  2. The ability to use FLEXPART in simulation of the long-range radioactive materials dispersed from nuclear power plants near Vietnam border

    International Nuclear Information System (INIS)

    Pham Kim Long; Pham Duy Hien; Nguyen Hao Quang; Do Xuan Anh; Duong Duc Thang; Doan Quang Tuyen

    2016-01-01

    FLEXPART is a Lagrangian transport and dispersion model suitable for the simulation of a large range of atmospheric transport processes. FLEXPART has been researched and applied in simulation of the long-range dispersion of radioactive materials. It can be applicable to the problem of radioactive materials released from the nuclear power plants impact on Vietnam. This report presents simulation of radioactive dispersion from the accident assumed Fangchenggang and Changjiang nuclear power plants in China with the FLEXPART, using meteorological data from the National Centers for Environmental Prediction (NCEP). The results of simulations and analyzing showed good applicability of FLEXPART for a long-range radioactive materials dispersion. The preliminary simulation results show that the impact of the radioactive material dispersion in Vietnam varies by the well-known characteristics of the monsoon of our country. Winter is the time when the dominant northeast winds up radioactive dispersion most towards our country, its sphere of influence extends from the Northeast (Quang Ninh) to North Central (Da Nang). (author)

  3. Monte Carlo simulation of radiation streaming from a radioactive material shipping cask

    International Nuclear Information System (INIS)

    Liu, Y.Y.; Schwarz, R.A.; Tang, J.S.

    1996-01-01

    Simulated detection of gamma radiation streaming from a radioactive material shipping cask have been performed with the Monte Carlo codes MCNP4A and MORSE-SGC/S. Despite inherent difficulties in simulating deep penetration of radiation and streaming, the simulations have yielded results that agree within one order of magnitude with the radiation survey data, with reasonable statistics. These simulations have also provided insight into modeling radiation detection, notably on location and orientation of the radiation detector with respect to photon streaming paths, and on techniques used to reduce variance in the Monte Carlo calculations. 13 refs., 4 figs., 2 tabs

  4. Experimental determination of the shipboard fire environment for simulated radioactive material packages

    International Nuclear Information System (INIS)

    Koski, J.A.; Bobbe, J.G.; Arviso, M.

    1997-03-01

    A series of eight fire tests with simulated radioactive material shipping containers aboard the test ship Mayo Lykes, a break-bulk freighter, is described. The tests simulate three basic types of fires: engine room fires, cargo fires and open pool fires. Detailed results from the tests include temperatures, heat fluxes and air flows measured during the fires. The first examination of the results indicates that shipboard fires are not significantly different from fires encountered in land transport. 13 refs., 15 figs., 11 tabs

  5. Monte Carlo simulations of radioactive waste encapsulated by bisphenol-A polycarbonate and effect of bismuth-III oxide filler material

    International Nuclear Information System (INIS)

    Özdemir, Tonguç

    2017-01-01

    Radioactive waste generated from the nuclear industry and non-power applications should carefully be treated, conditioned and disposed according to the regulations set by the competent authority(ies). Bisphenol-a polycarbonate (BPA-PC), a very widely used polymer, might be considered as a potential candidate material for low level radioactive waste encapsulation. In this work, the dose rate distribution in the radioactive waste drum (containing radioactive waste and the BPA-PC polymer matrix) was determined using Monte Carlo simulations. Moreover, the change of mechanical properties of BPA-PC was estimated and their variation within the waste drum was determined for the periods of 15, 30 and 300 years after disposal to the final disposal site. The change of the dose rate within the waste drum with different contents of bismuth-III oxide were also simulated. It was concluded that addition of bismuth-III oxide filler decreases the dose delivered to the polymeric matrix due to photoelectric effect. - Highlights: • Bisphenol-a polycarbonate (BPA-PC) is a widely used polymeric material and have a considerable gamma radiation stability. • BPA-PC could have a potential candidate material for radioactive waste embedding. • Activity of the radioactive waste that could be embedded into the BPA-PC matrix was simulated. • Effect of bismuth-III-oxide filler to the BPA-PC matrix was determined.

  6. Simulation of the dynamic response of radioactive material shipping package - railcar systems during coupling operations

    International Nuclear Information System (INIS)

    Fields, S.R.

    1981-12-01

    The basic equations of the computer model CARDS (Cask-Railcar Dynamic Simulator), developed for the U.S. Nuclear Regulatory Commission to simulate the dynamic behavior of radioactive material shipping package - railcar systems, are presented. A companion model, CARRS (Casks Railcar Response Spectrum Generator), that generates system response as frequency response spectra is also presented in terms of its basic equations

  7. Simulation of the dynamic response of radioactive material shipping package-railcar systems during coupling operations

    International Nuclear Information System (INIS)

    Fields, S.R.

    1983-10-01

    The basic equations of the computer model CARDS (Cask-Railcar Dynamic Simulator), developed for the US Nuclear Regulatory Commission to simulate the dynamic behavior of radioactive material shipping package - railcar systems, are presented. A companion model, CARRS (Cask Railcar Response Spectrum Generator), that generates system response as frequency response spectra is also presented in terms of its basic equations. 1 reference, 18 figures

  8. Determination of Fire Enviroment in Stacked Cargo Containers with Radioactive Materials Packages

    Energy Technology Data Exchange (ETDEWEB)

    Arviso, M.; Bobbe, J.G.; Dukart, R.D.; Koski, J.A.

    1999-05-01

    Results from a Fire Test with a three-by-three stack of standard 6 m long International Standards Organization shipping containers containing combustible fuels and empty radioactive materials packages are reported and discussed. The stack is intended to simulate fire conditions that could occur during on-deck stowage on container cargo ships. The fire is initated by locating the container stack adjacent to a 9.8 x 6 m pool fire. Temperatures of both cargoes (empty and simulated radioactive materials packages) and containers are recorded and reported. Observations on the duration, intensity and spread of the fire are discussed. Based on the results, models for simulation of fire exposure of radioactive materials packages in such fires are suggested.

  9. Transport of radioactive materials

    International Nuclear Information System (INIS)

    2013-01-01

    This ninth chapter presents de CNEN-NE--5.01 norm 'Transport of radioactive material'; the specifications of the radioactive materials for transport; the tests of the packages; the requests for controlling the transport and the responsibilities during the transport of radioactive material

  10. Computed tomography of radioactive objects and materials

    International Nuclear Information System (INIS)

    Sawicka, B.D.; Murphy, R.V.; Tosello, G.; Reynolds, P.W.; Romaniszyn, T.

    1990-01-01

    Computed tomography (CT) has been performed on a number of radioactive objects and materials. Several unique technical problems are associated with CT of radioactive specimens. These include general safety considerations, techniques to reduce background-radiation effects on CT images and selection criteria for the CT source to permit object penetration and to reveal accurate values of material density. In the present paper, three groups of experiments will be described, for objects with low, medium and high levels of radioactivity. CT studies on radioactive specimens will be presented. They include the following: (1) examination of individual ceramic reactor-fuel (uranium dioxide) pellets, (2) examination of fuel samples from the Three Mile Island reactor, (3) examination of a CANDU (CANada Deuterium Uranium: registered trademark) nuclear-fuel bundle which underwent a simulated loss-of-coolant accident resulting in high-temperature damage and (4) examination of a PWR nuclear-reactor fuel assembly. (orig.)

  11. Atmospheric dispersion of radioactive materials

    International Nuclear Information System (INIS)

    Chino, Masamichi

    1988-01-01

    The report describes currently available techniques for predicting the dispersion of accidentally released radioactive materials and techniques for visualization using computer graphics. A simulation study is also made on the dispersion of radioactive materials released from the Chernobyl plant. The simplest models include the Gauss plume model and the puff model, which cannot serve to analyze the effects of the topography, vertical wind shear, temperature inversion layer, etc. Numerical analysis methods using advection and dispersion equations are widely adopted for detailed evaluation of dispersion in an emergency. An objective analysis model or a hydrodynamical model is often used to calculate the air currents which are required to determine the advection. A small system based on the puff model is widely adopted in Europe, where the topography is considered to have only simple effects. A more sophisticated large-sized system is required in nuclear facilities located in an area with more complex topographic features. An emergency system for dispersion calculation should be equipped with a graphic display to serve for quick understanding of the radioactivity distribution. (Nogami, K.)

  12. Dossier: transport of radioactive materials

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  13. Radioactive Plumes Monitoring Simulator

    International Nuclear Information System (INIS)

    Kapelushnik, I.; Sheinfeld, M.; Avida, R.; Kadmon, Y.; Ellenbogen, M.; Tirosh, D.

    1999-01-01

    The Airborne Radiation Monitoring System (ARMS) monitors air or ground radioactive contamination. The contamination source can be a radioactive plume or an area contaminated with radionuclides. The system is based on two major parts, an airborne unit carried by a helicopter and a ground station carried by a truck. The system enables real time measurement and analysis of radioactive plumes as well as post flight processing. The Radioactive Plumes Monitoring Simulator purpose is to create a virtual space where the trained operators experience full radiation field conditions, without real radiation hazard. The ARMS is based on a flying platform and hence the simulator allows a significant reduction of flight time costs

  14. The safe transport of radioactive materials

    CERN Document Server

    Gibson, R

    1966-01-01

    The Safe Transport of Radioactive Materials is a handbook that details the safety guidelines in transporting radioactive materials. The title covers the various regulations and policies, along with the safety measures and procedures of radioactive material transport. The text first details the 1963 version of the IAEA regulation for the safe transport of radioactive materials; the regulation covers the classification of radionuclides for transport purposes and the control of external radiation hazards during the transport of radioactive materials. The next chapter deals with concerns in the im

  15. Transport of radioactive materials

    International Nuclear Information System (INIS)

    1988-07-01

    The norm which establishes the requirements of radiation protection and safety related to the transport of radioactive materials, aiming to keep a suitable control level of eventual exposure of personnels, materials and environment of ionizing radiation, including: specifications on radioactive materials for transport, selection of package type; specification of requirements of the design and assays of acceptance of packages; disposal related to the transport; and liability and administrative requirements, are presented. This norm is applied to: truckage, water carriage and air service; design, fabrication, assays and mantenaince of packages; preparation, despatching, handling, loading storage in transition and reception in the ultimate storage of packages; and transport of void packages which have been contained radioactive materials. (M.C.K.) [pt

  16. Storage depot for radioactive material

    International Nuclear Information System (INIS)

    Szulinski, M.J.

    1983-01-01

    Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-01

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

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  19. Experimental measurement of a shipboard fire environment with simulated radioactive materials packages

    International Nuclear Information System (INIS)

    Koski, J.A.; Wix, S.D.

    1996-01-01

    Results from a series of eight test fires ranging in size from 2.2 to 18.8 MW conducted aboard the Coast Guard fire test ship Mayo Lykes at Mobile, Alabama are presented and discussed. Tests aboard the break-bulk type cargo ship consisted of heptane spray fires simulating engine room and galley fires, wood crib fires simulating cargo hold fires, and pool fires staged for comparison to land-based regulatory fire results. Primary instrumentation for the tests consisted of two pipe calorimeters that simulated a typical package shape for radioactive materials packages. The calorimeters were both located adjacent to the fires and on the opposite side of the cargo hold bulkhead nearest the fire. The calorimeters were constructed from 1.5 m length sections of nominal 2 foot diameter schedule 60 steel pipe. Type K thermocouples were attached at 12 locations on the circumference and ends of the calorimeter. Fire heat fluxes to the calorimeter surfaces were estimated with the use of the Sandia SODDIT inverse heat conduction code. Experimental results from all types of tests are discussed, and some comparisons are made between the environments found on the ship and those found in land-based pool fire tests

  20. Consumer Products Containing Radioactive Materials

    Science.gov (United States)

    Fact Sheet Adopted: February 2010 Health Physics Society Specialists in Radiation Safety Consumer Products Containing Radioactive Materials Everything we encounter in our daily lives contains some radioactive material, ...

  1. Transport of Radioactive Materials

    International Nuclear Information System (INIS)

    2001-01-01

    This address overviews the following aspects: concepts on transport of radioactive materials, quantities used to limit the transport, packages, types of packages, labeling, index transport calculation, tags, labeling, vehicle's requirements and documents required to authorize transportation. These requirements are considered in the regulation of transport of radioactive material that is in drafting step

  2. Accidents during transport of radioactive material

    International Nuclear Information System (INIS)

    Agarwal, S.P.

    2008-01-01

    Radioactive materials are a part of modern technology and life. They are used in medicine, industry, agriculture, research and electrical power generation. Tens of millions of packages containing radioactive materials are consigned for transport each year throughout the world. In India, about 80000 packages containing radioactive material are transported every year. The amount of radioactive material in these packages varies from negligible amounts used in consumer products to very large amounts in shipment of irradiator sources and spent nuclear fuel

  3. Radioactive materials transport

    International Nuclear Information System (INIS)

    Talbi, B.

    1996-01-01

    The development of peaceful applications of nuclear energy results in the increase of transport operations of radioactive materials. Therefore strong regulations on transport of radioactive materials turns out to be a necessity in Tunisia. This report presents the different axes of regulations which include the means of transport involved, the radiation protection of the carriers, the technical criteria of security in transport, the emergency measures in case of accidents and penalties in case of infringement. (TEC). 12 refs., 1 fig

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  5. Radioactive waste material melter apparatus

    Science.gov (United States)

    Newman, D.F.; Ross, W.A.

    1990-04-24

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

  6. Radioactive waste material melter apparatus

    International Nuclear Information System (INIS)

    Newman, D.F.; Ross, W.A.

    1990-01-01

    An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs

  7. Radioactive Materials Packaging (RAMPAC) Radioactive Materials Incident Report (RMIR). RAMTEMP users manual

    International Nuclear Information System (INIS)

    Tyron-Hopko, A.K.; Driscoll, K.L.

    1985-10-01

    The purpose of this document is to familiarize the potential user with RadioActive Materials PACkaging (RAMPAC), Radioactive Materials Incident Report (RMIR), and RAMTEMP databases. RAMTEMP is a minor image of RAMPAC. This reference document will enable the user to access and obtain reports from databases while in an interactive mode. This manual will be revised as necessary to reflect enhancements made to the system

  8. Radioactive material package seal tests

    International Nuclear Information System (INIS)

    Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

    1990-01-01

    General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 x 10 -7 std cm 3 /s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab

  9. Radioactive material generator

    International Nuclear Information System (INIS)

    Czaplinski, T.V.; Bolter, B.J.; Heyer, R.E.; Bruno, G.A.

    1975-01-01

    A radioactive material generator includes radioactive material in a column, which column is connected to inlet and outlet conduits, the generator being embedded in a lead casing. The inlet and outlet conduits extend through the casing and are topped by pierceable closure caps. A fitting, containing means to connect an eluent supply and an eluate container, is adapted to pierce the closure caps. The lead casing and the fitting are compatibly contoured such that they will fit only if properly aligned with respect to each other

  10. Customs control of radioactive materials

    International Nuclear Information System (INIS)

    Causse, B.

    1998-01-01

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

  11. Computerized simulation of the mechanical behavior of wood-filled shock absorbers of radioactive materials transport casks

    International Nuclear Information System (INIS)

    Neumann, Martin; Wille, Frank

    2011-01-01

    In Germany the mechanical component inspection of transport containers for radioactive materials is performed by BAM (Bundesanstalt fuer Materialforschung und -pruefung) under consideration of national and international standards and guidelines. Experimental and calculative (analytical and numerical) techniques combined with material and/or component testing are the basis of assessment concepts according the state of the art. The authors describe the experiences of BAM concerning assessment and description of the mechanical behavior of shock absorbing components, including modeling strategies, material models, drop tests and experiment-calculation comparison. Energy absorbing components are used to reduce the impact forces at the container in case of a transport accident. In Germany wood filled thin-walled constructions are used. The deformation behavior of the wood is a main part of the calculative simulation procedures in comparison with experimental tests.

  12. Naturally Occurring Radioactive Materials (NORM)

    International Nuclear Information System (INIS)

    Gray, P.

    1997-01-01

    This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training)

  13. Naturally Occurring Radioactive Materials (NORM)

    Energy Technology Data Exchange (ETDEWEB)

    Gray, P. [ed.

    1997-02-01

    This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training).

  14. Radioactive waste material testing capabilities in Romania

    International Nuclear Information System (INIS)

    Vieru, G.

    1999-01-01

    Radioactive material including wastes, generated by Romanian nuclear facilities are packaged in accordance with national and IAEA's Regulation for a safe transport to the disposal center. The evaluation and certification of packages is accomplished by subjecting these packages to normal and simulated test conditions in order to prove the package to technical performances. The standards provide to package designers the possibility to use analysis, testing or a combination of these. The paper describes the experimental and simulating qualification tests for type A packages used for transport and storage of radioactive wastes (low level). Testing are used to substantiate assumptions used in analytical models and to demonstrate package structural response. There are also presented testing capabilities which are used to perform and simulate the required qualification tests. By direct comparison of analysis and experimental results, the degree of reliability of analytical methods and admissibility of assumptions taken in package designing and in demonstrating its safety under conditions of INR - Pitesti, within the contract between the INR - Pitesti and IAEA - Vienna, were determined. (author)

  15. Fixing of various simulated radioactive wastes in urea-formaldehyde resin

    International Nuclear Information System (INIS)

    Du Dahai; Wei Peng

    1986-01-01

    This paper outlines the results of the fixing of a variety of simulated radioactive wastes in the urea-formaldehyde resin. The radioactive waste materials fixed include spent ion exchange resin, concentrates of NaNO 3 -NaBO 2 as well as NaBO 2 and sludge. The performance of the fixed products has been improved by means of selecting the synthetic conditions of resin, a suitable hardener and an inorganic additive

  16. Experimental ship fire measurements with simulated radioactive cargo

    International Nuclear Information System (INIS)

    Koski, J.A.; Arviso, M.; Bobbe, J.G.; Wix, S.D.; Cole, J.K.; Hohnstreiter, G.F.; Beene, D.E. Jr.

    1997-10-01

    Results from a series of eight test fires ranging in size from 2.2 to 18.8 MW conducted aboard the Coast Guard fire test ship Mayo Lykes at Mobile, Alabama are presented and discussed. Tests aboard the break bulk type cargo ship consisted of heptane spray fires simulating engine room and galley fires, wood crib fires simulating cargo hold fires, and pool fires staged for comparison to land based regulatory fire results. Primary instrumentation for the tests consisted of two pipe calorimeters that simulated a typical package shape for radioactive materials packages

  17. Experimental ship fire measurements with simulated radioactive cargo

    International Nuclear Information System (INIS)

    Koski, J.A.; Arvisol, M.; Bobbe, J.G.; Wix, S.D.; Cole, J.K.; Hohnstreiter, G.F.; Wix, S.D.; Beene, D.E.; Keane, M.P.

    1998-01-01

    Results from a series of eight test fires ranging in size from 2.2 to 18.8 MW conducted aboard the Coast Guard fire test ship Mayo Lykes at Mobile, Alabama are presented and discussed. Tests aboard the break-bulk type cargo ship consisted of heptane spray fires simulating engine room and galley fires, wood crib fires simulating cargo hold fires, and pool fires staged for comparison to land-based regulatory fire results. Primary instrumentation for the tests consisted of two pipe calorimeters that simulated a typical package shape for radioactive materials packages. (authors)

  18. Radioactive material accidents in the transport

    International Nuclear Information System (INIS)

    Rodrigues, D.L.; Magalhaes, M.H.; Sanches, M.P.; Sordi, G.M.A.A.

    2008-01-01

    Transport is an important part of the worldwide nuclear industry and the safety record for nuclear transport across the world is excellent. The increase in the use of radioactive materials in our country requires that these materials be moved from production sites to the end user. Despite the number of packages transported, the number of incidents and accidents in which they are involved is low. In Brazil, do not be records of victims of the radiation as a result of the transport of radioactive materials and either due to the accidents happened during the transports. The absence of victims of the radiation as result of accidents during the transports is a highly significant fact, mainly to consider that annually approximately two hundred a thousand packages containing radioactive material are consigned for transport throughout the country, of which eighty a thousand are for a medical use. This is due to well-founded regulations developed by governmental and intergovernmental organizations and to the professionalism of those in the industry. In this paper, an overview is presented of the activities related to the transport of radioactive material in the state of Sao Paulo. The applicable legislation, the responsibilities and tasks of the competent authorities are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. It also presents the packages amounts of carried and the accidents occurred during the transport of radioactive materials, in the last five years. The main occurred events are argued, demonstrating that the demanded requirements of security for any transport of radioactive material are enough to guarantee the necessary control of ionizing radiation expositions to transport workers, members of general public and the environment. (author)

  19. Effects of non-radioactive material around radioactive material on PET image quality

    International Nuclear Information System (INIS)

    Toshimitsu, Shinya; Yamane, Azusa; Hirokawa, Yutaka; Kangai, Yoshiharu

    2015-01-01

    Subcutaneous fat is a non-radioactive material surrounding the radioactive material. We developed a phantom, and examined the effect of subcutaneous fat on PET image quality. We created a cylindrical non-radioactive mimic of subcutaneous fat, placed it around a cylindrical phantom in up to three layers with each layer having a thickness of 20 mm to reproduce the obesity caused by subcutaneous fat. In the cylindrical phantom, hot spheres and cold spheres were arranged. The radioactivity concentration ratio between the hot spheres and B.G. was 4:1. The radioactivity concentration of B.G. was changed as follows : 1.33, 2.65, 4.00, and 5.30 kBq/mL. 3D-PET image were collected during 10 minutes. When the thickness of the mimicked subcutaneous fat increased from 0 mm to 60 mm, noise equivalent count decreased by 58.9-60.9% at each radioactivity concentration. On the other hand, the percentage of background variability increased 2.2-5.2 times. Mimic subcutaneous fat did not decrease the percentage contrast of the hot spheres, and did not affect the cold spheres. Subcutaneous fat decreases the noise equivalent count and increases the percentage of background variability, which degrades PET image quality. (author)

  20. Transport of radioactive materials

    International Nuclear Information System (INIS)

    1991-07-01

    The purpose of this Norm is to establish, relating to the TRANSPORT OF RADIOACTIVE MATERIALS, safety and radiological protection requirements to ensure an adequate control level of the eventual exposure of persons, properties and environment to the ionizing radiation comprising: specifications on radioactive materials for transport; package type selection; specification of the package design and acceptance test requirements; arrangements relating to the transport itself; administrative requirements and responsibilities. (author)

  1. Electrodeless light source provided with radioactive material

    International Nuclear Information System (INIS)

    1979-01-01

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

  2. Method of treating radioactive waste material

    International Nuclear Information System (INIS)

    Allison, W.

    1980-01-01

    A method of treating radioactive waste material, particularly a radioactive sludge, is described comprising separating solid material from liquid material, compressing the solid material and encapsulating the solid material in a hardenable composition such as cement, bitumen or a synthetic resin. The separation and compaction stages are conveniently effected in a tube press. (author)

  3. Radioactive materials in recycled metals.

    Science.gov (United States)

    Lubenau, J O; Yusko, J G

    1995-04-01

    In recent years, the metal recycling industry has become increasingly aware of an unwanted component in metal scrap--radioactive material. Worldwide, there have been 35 instances where radioactive sources were unintentionally smelted in the course of recycling metal scrap. In some cases contaminated metal consumer products were distributed internationally. In at least one case, serious radiation exposures of workers and the public occurred. Radioactive material appearing in metal scrap includes sources subject to licensing under the Atomic Energy Act and also naturally occurring radioactive material. U.S. mills that have smelted a radioactive source face costs resulting from decontamination, waste disposal, and lost profits that range from 7 to 23 million U.S. dollars for each event. To solve the problem, industry and the government have jointly undertaken initiatives to increase awareness of the problem within the metal recycling industry. Radiation monitoring of recycled metal scrap is being performed increasingly by mills and, to a lesser extent, by scrap processors. The monitoring does not, however, provide 100% protection. Improvements in regulatory oversight by the government could stimulate improved accounting and control of licensed sources. However, additional government effort in this area must be reconciled with competing priorities in radiation safety and budgetary constraints. The threat of radioactive material in recycled metal scrap will continue for the foreseeable future and, thus, poses regulatory policy challenges for both developed and developing nations.

  4. Detection of radioactive materials at borders

    International Nuclear Information System (INIS)

    2003-08-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  5. Detection of radioactive materials at borders

    International Nuclear Information System (INIS)

    2004-05-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  6. Detection of radioactive materials at borders

    International Nuclear Information System (INIS)

    2002-09-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  7. Radioactive certified reference materials

    International Nuclear Information System (INIS)

    Watanabe, Kazuo

    2010-01-01

    Outline of radioactive certified reference materials (CRM) for the analysis of nuclear materials and radioactive nuclides were described. The nuclear fuel CRMs are supplied by the three institutes: NBL in the US, CETAMA in France and IRMM in Belgium. For the RI CRMs, the Japan Radioisotope Association is engaged in activities concerning supply. The natural-matrix CRMs for the analysis of trace levels of radio-nuclides are prepared and supplied by NIST in the US and the IAEA. (author)

  8. Transport regulation for radioactive materials

    International Nuclear Information System (INIS)

    Ha Vinh Phuong.

    1986-01-01

    Taking into account the specific dangers associated with the transport of radioactive materials (contamination, irradiation, heat, criticality), IAEA regulations concerning technical specifications and administrative procedures to ward off these dangers are presented. The international agreements related to the land transport, maritime transport and air transport of radioactive materials are also briefly reviewed

  9. Accountability of Radioactive Materials in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Noor Fadilla Ismail; Wan Saffiey Wan Abdullah; Khairuddin Mohamad Kontol; Azimawati Ahmad; Suzilawati Muhd Sarowi; Mohd Fazlie Abdul Rashid

    2016-01-01

    Radioactive materials possessed in Malaysian Nuclear Agency have many beneficial applications for research and development, calibration, tracer and irradiation. There are two types of radioactive materials which consist of sealed sourced and unsealed sourced shall be accounted for and secured at all the times by following the security aspect. The Health Physics Group in the Department of Radiation Safety and Health Division is responsible to manage the issues related to any accountability for all radioactive material purchased or received under the radioactive material protocol. The accountability of radioactive materials in Malaysian Nuclear Agency is very important to ensure the security and control the radioactive materials to not to be lost or fall into the hands of people who do not have permission to possess or use it. The accountability of radioactive materials considered as a mandatory to maintaining accountability by complying the requirements of the Atomic Energy Licensing Act 1984 (Act 304) and regulations made thereunder and the conditions of license LPTA / A / 724. In this report describes the important element of accountability of radioactive materials in order to enhances security standard by allowing tracking of the locations of sources and to reduce the risk of radioactive materials falling into the wrong hands. (author)

  10. Radioactive substances in the Danish building materials

    International Nuclear Information System (INIS)

    Ulbak, K.

    1986-01-01

    Building materials as any other materials of natural occurrence contain small concentrations of natural radioactive elements. This natural radioactivity affects people inside buildings. This publiccation refers measurements of the Danish building materials, and radiation doses originating from this source affecting the Danish population are related to the other components of background radioactivity. (EG)

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

    CERN Multimedia

    2004-01-01

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

  12. Estimation of global inventories of radioactive waste and other radioactive materials

    International Nuclear Information System (INIS)

    2008-06-01

    A variety of nuclear activities have been carried out in the second part of the twentieth century for different purposes. Initially the emphasis was on military applications, but with the passage of time the main focus of nuclear activities has shifted to peaceful uses of nuclear energy and to the use of radioactive material in industry, medicine and research. Regardless of the objectives, the nuclear activities generate radioactive waste. It was considered worthwhile to produce a set of worldwide data that could be assessed to evaluate the legacy of the nuclear activities performed up to the transition between the twentieth and the twenty first century. The assessment tries to cover the inventory of all the human produced radioactive material that can be considered to result from both military and civilian applications. This has caused remarkable difficulties since much of the data, particularly relating to military programmes, are not readily available. Consequently the data on the inventory of radioactive material should be considered as order-of-magnitude approximations. This report as a whole should be considered as a first iteration in a continuing process of updating and upgrading. The accumulations of radioactive materials can be considered a burden for human society, both at present and in the future, since they require continuing monitoring and control. Knowing the amounts and types of such radioactive inventories can help in the assessment of the relative burdens. Knowledge of the national or regional radioactive waste inventory is necessary for planning management operations, including the sizing and design of conditioning, storage and disposal facilities. A global inventory, either of radioactive waste or of other environmental accumulations of radioactive material, could be used to provide a perspective on the requirements and burdens associated with their management, by means of comparisons with the burdens caused by other types of waste or other

  13. Regulations for the safe transport of radioactive materials

    International Nuclear Information System (INIS)

    Kgogo, Obonye

    2016-04-01

    The report provides insight and investigates whether Transport Regulations in Botswana follow international standards for transport of radioactive material. Radioactive materials are very useful in most of our activities and are manufactured in different countries, therefore end up traversing from one country to another and being transported in national roads .The IAEA regulation for the Transport of radioactive material is used as the reference guideline in this study. The current Regulations for Transport of radioactive material in Botswana do not cover all factors which need to be considered when transporting radioactive although they refer to IAEA regulations. Basing on an inadequacy of the regulations and category of radioactive materials in the country recommendations were made concerning security, packaging and worker training's. The regulations for the Transport of radioactive material in Botswana need to be reviewed and updated so that they can relate to international standard. (au)

  14. Radioactive material package testing capabilities at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Uncapher, W.L.; Hohnstreiter, G.F.

    1995-01-01

    Evaluation and certification of radioactive and hazardous material transport packages can be accomplished by subjecting these packages to normal transport and hypothetical accident test conditions. The regulations allow package designers to certify packages using analysis, testing, or a combination of analysis and testing. Testing can be used to substantiate assumptions used in analytical models and to demonstrate package structural and thermal response. Regulatory test conditions include impact, puncture, crush, penetration, water spray, immersion, and thermal environments. Testing facilities are used to simulate the required test conditions and provide measurement response data. Over the past four decades, comprehensive testing facilities have been developed at Sandia National Laboratories to perform a broad range of verification and certification tests on hazardous and radioactive material packages or component sections. Sandia's facilities provide an experience base that has been established during the development and certification of many package designs. These unique facilities, along with innovative instrumentation data collection capabilities and techniques, simulate a broad range of testing environments. In certain package designs, package testing can be an economical alternative to complex analysis to resolve regulatory questions or concerns

  15. 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

  16. Development of simple and rapid radioactivity analysis for thorium series in the products containing naturally occurring radioactive materials (NORM)

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jae Ryong; Park, Se Young; Yoon, Seok Won; Ha, Wi Ho [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of); Lee, Jae Kook; Kim, Kwang Pyo [Kyung Hee University, Seoul (Korea, Republic of)

    2016-05-15

    It is necessary to analyze radioactivity of naturally occurring radioactive materials (NORM) in products to ensure radiological safety required by Natural Radiation Safety Management Act. The pretreatments for the existing analysis methods require high technology and time. Such destructive pretreatments including grinding and dissolution of samples make impossible to reuse products. We developed a rapid and simple procedure of radioactivity analysis for thorium series in the products containing NORM. The developed method requires non-destructive or minimized pretreatment. Radioactivity of the product without pretreatment is initially measured using gamma spectroscopy and then the measured radioactivity is adjusted by considering material composition, mass density, and geometrical shape of the product. The radioactivity adjustment can be made using scaling factors, which is derived by radiation transport Monte Carlo simulation. Necklace, bracelet, male health care product, and tile for health mat were selected as representative products for this study. The products are commonly used by the public and directly contacted with human body and thus resulting in high radiation exposure to the user. The scaling factors were derived using MCNPX code and the values ranged from 0.31 to 0.47. If radioactivity of the products is measured without pretreatment, the thorium series may be overestimated by up to 2.8 times. If scaling factors are applied, the difference in radioactivity estimates are reduced to 3-24%. The developed procedure in this study can be used for other products with various materials and shapes and thus ensuring radiological safety.

  17. Safe transport of radioactive material

    International Nuclear Information System (INIS)

    1994-01-01

    Delivering radioactive material to where it is needed is a vital service to industry and medicine. Millions of packages are shipped all over the world by all modes of transport. The shipments pass through public places and must meet stringent safety requirements. This video explains how radioactive material is safely transported and describes the rules that carriers and handlers must follow

  18. 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)

  19. Development of radioactive materials inspection system

    International Nuclear Information System (INIS)

    Yang Lu; Wang Guobao; Chen Yuhua; Li Latu; Zhang Sujing

    2005-01-01

    Radioactive materials inspection system which is applied to inspect the horror activities of radioactive materials and its illegal transfer. The detector sections are made of highly stable and credible material. It has high sensitivity to radioactive materials. The inspect lowest limit of inspection is the 2-3 times to the background, the energy range is 30 keV-2.5 MeV and the response time is 0.5 s. Inspection message can be transmitted through wired or wireless web to implement remote control. The structure of the system is small, light and convenient. It is ideal for protecting society and public from the harm of the radiation. (authors)

  20. Impact limiters for radioactive materials transport packagings: a methodology for assessment

    International Nuclear Information System (INIS)

    Mourao, Rogerio Pimenta

    2002-01-01

    This work aims at establishing a methodology for design assessment of a cellular material-filled impact limiter to be used as part of a radioactive material transport packaging. This methodology comprises the selection of the cellular material, its structural characterization by mechanical tests, the development of a case study in the nuclear field, preliminary determination of the best cellular material density for the case study, performance of the case and its numerical simulation using the finite element method. Among the several materials used as shock absorbers in packagings, the polyurethane foam was chosen, particularly the foam obtained from the castor oil plant (Ricinus communis), a non-polluting and renewable source. The case study carried out was the 9 m drop test of a package prototype containing radioactive wastes incorporated in a cement matrix, considered one of the most severe tests prescribed by the Brazilian and international transport standards. Prototypes with foam density pre-determined as ideal as well as prototypes using lighter and heavier foams were tested for comparison. The results obtained validate the methodology in that expectations regarding the ideal foam density were confirmed by the drop tests and the numerical simulation. (author)

  1. Recovering method for high level radioactive material

    International Nuclear Information System (INIS)

    Fukui, Toshiki

    1998-01-01

    Offgas filters such as of nuclear fuel reprocessing facilities and waste control facilities are burnt, and the burnt ash is melted by heating, and then the molten ashes are brought into contact with a molten metal having a low boiling point to transfer the high level radioactive materials in the molten ash to the molten metal. Then, only the molten metal is evaporated and solidified by drying, and residual high level radioactive materials are recovered. According to this method, the high level radioactive materials in the molten ashes are transferred to the molten metal and separated by the difference of the distribution rate of the molten ash and the molten metal. Subsequently, the molten metal to which the high level radioactive materials are transferred is heated to a temperature higher than the boiling point so that only the molten metal is evaporated and dried to be removed, and residual high level radioactive materials are recovered easily. On the other hand, the molten ash from which the high level radioactive material is removed can be discarded as ordinary industrial wastes as they are. (T.M.)

  2. Packaging and transportation of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    The presentations made at the Symposium on Packaging and Transportation of Radioactive Materials are included. The purpose of the meeting was for the interchange of information on the technology and politics of radioactive material transportation. Separate abstracts were prepared for individual items. (DC)

  3. Packaging and transportation of radioactive materials

    International Nuclear Information System (INIS)

    1978-01-01

    The presentations made at the Symposium on Packaging and Transportation of Radioactive Materials are included. The purpose of the meeting was for the interchange of information on the technology and politics of radioactive material transportation. Separate abstracts were prepared for individual items

  4. International conventions for measuring radioactivity of building materials

    International Nuclear Information System (INIS)

    Tan Chenglong

    2004-01-01

    In buildings, whether civil or industrial, natural radioactivity always occurs at different degrees in the materials (main building materials, decorative materials). Concerns on radioactivity from building materials is unavoidable for human living and developing. As a member of WTO, China's measuring method of radioactivity for building materials, including radionuclides limitation for building materials, hazard evaluation system etc, should keep accordance with the international rules and conventions. (author)

  5. Airborne concentrations of radioactive materials in severe accidents

    International Nuclear Information System (INIS)

    Ross, D.F. Jr.; Denning, R.S.

    1989-01-01

    Radioactive materials would be released to the containment building of a commercial nuclear reactor during each of the stages of a severe accident. Results of analyses of two accident sequences are used to illustrate the magnitudes of these sources of radioactive materials, the resulting airborne mass concentrations, the characteristics of the airborne aerosols, the potential for vapor forms of radioactive materials, the effectiveness of engineered safety features in reducing airborne concentrations, and the release of radioactive materials to the environment. Ability to predict transport and deposition of radioactive materials is important to assessing the performance of containment safety features in severe accidents and in the development of accident management procedures to reduce the consequences of severe accidents

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  7. Working safely with radioactive materials

    International Nuclear Information System (INIS)

    Davies, Wynne

    1993-01-01

    In common with exposure to many other laboratory chemicals, exposure to ionising radiations and to radioactive materials carries a small risk of causing harm. Because of this, there are legal limits to the amount of exposure to ionising radiations at work and special rules for working with radioactive materials. Although radiation protection is a complex subject it is possible to simplify to 10 basic things you should do -the Golden Rules. They are: 1) understand the nature of the hazard and get practical training; 2) plan ahead to minimise time spent handling radioactivity; 3) distance yourself appropriately from sources of radiation; 4) use appropriate shielding for the radiation; 5) contain radioactive materials in defined work areas; 6) wear appropriate protective clothing and dosimeters; 7) monitor the work area frequently for contamination control; 8) follow the local rules and safe ways of working; 9) minimise accumulation of waste and dispose of it by appropriate routes, and 10) after completion of work, monitor, wash, and monitor yourself again. These rules are expanded in this article. (author)

  8. Decontamination method for radioactively contaminated material

    International Nuclear Information System (INIS)

    Shoji, Yuichi; Mizuguchi, Hiroshi; Sakai, Hitoshi; Komatsubara, Masaru

    1998-01-01

    Radioactively contaminated materials having surfaces contaminated by radioactive materials are dissolved in molten salts by the effect of chlorine gas. The molten salts are brought into contact with a low melting point metal to reduce only radioactive materials by substitution reaction and recover them into the low melting point metal. Then, a low melting point metal phase and a molten salt phase are separated. The low melting point metal phase is evaporated to separate the radioactive materials from molten metals. On the other hand, other metal ions dissolved in the molten salts are reduced into metals by electrolysis at an anode and separated from the molten salts and served for regeneration. The low melting point metals are reutilized together with contaminated lead, after subjected to decontamination, generated from facilities such as nuclear power plant or lead for disposal. Since almost all materials including the molten salts and the molten metals can be enclosed, the amount of wastes can be reduced. In addition, radiation exposure of operators who handle them can be reduced. (T.M.)

  9. Radioactive material packaging performance testing

    International Nuclear Information System (INIS)

    Romano, T.; Cruse, J.M.

    1991-02-01

    To provide uniform packaging of hazardous materials on an international level, the United Nations has developed packaging recommendations that have been implemented worldwide. The United Nations packaging recommendations are performance oriented, allowing for a wide variety of package materials and systems. As a result of this international standard, efforts in the United States are being directed toward use of performance-oriented packaging and elimination of specification (designed) packaging. This presentation will focus on trends, design evaluation, and performance testing of radioactive material packaging. The impacts of US Department of Transportation Dockets HM-181 and HM-169A on specification and low-specific activity radioactive material packaging requirements are briefly discussed. The US Department of Energy's program for evaluating radioactive material packings per US Department of Transportation Specification 7A Type A requirements, is used as the basis for discussing low-activity packaging performance test requirements. High-activity package testing requirements are presented with examples of testing performed at the Hanford Site that is operated by Westinghouse Hanford Company for the US Department of Energy. 5 refs., 2 tabs

  10. Safe transport of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-31

    The film shows the widespread use of radioactive materials in industry, medicine and research and explains the need for transporting nuclear material from producer to user. It shows the way in which packages containing radioactive materials are handled during transport and explains the most important provisions of the IAEA transport regulations, safety series no. 6, such as packaging design criteria and testing requirements, illustrated by various tests carried out, specimen packages and package and freight container labelling. Also illustrated are practical measures to be taken in case of an accident

  11. Transporting radioactive materials: Q ampersand A to your questions

    International Nuclear Information System (INIS)

    1993-04-01

    Over 2 million packages of radioactive materials are shipped each year in the United States. These shipments are carried by trucks, trains, ships, and airplanes every day just like other commodities. Compliance with Federal regulations ensures that radioactive materials are transported safely. Proper packaging is the key to safe shipment. Package designs for radioactive materials must protect the public and the environment even in case of an accident. As the level of radioactivity increases, packaging design requirements become more stringent. Radioactive materials have been shipped in this country for more than 40 years. As with other commodities, vehicles carrying these materials have been involved in accidents. However, no deaths or serious injuries have resulted from exposure to the radioactive contents of these shipments. People are concerned about how radioactive shipments might affect them and the environment. This booklet briefly answers some of the commonly asked questions about the transport of radioactive materials. More detailed information is available from the sources listed at the end of this booklet

  12. Institutional storage and disposal of radioactive materials

    International Nuclear Information System (INIS)

    St Germain, J.

    1986-01-01

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

  13. Transport of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    The increasing use of radioactive substances, not only in reactor operations but also in medicine, industry and other fields, is making the movement of these materials progressively wider, more frequent and larger in volume. Although regulations for the safe transport of radioactive materials have been in existence for many years, it has now become necessary to modify or supplement the existing provisions on an international basis. It is essential that the regulations should be applied uniformly by all countries. It is also desirable that the basic regulations should be uniform for all modes of transport so as to simplify the procedures to be complied with by shippers and carriers

  14. Radioactive material packaging performance testing

    International Nuclear Information System (INIS)

    Romano, T.

    1992-06-01

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

  15. Simulation of fire in a deposit of radioactive waste and the radiological risk associated to this scenario

    International Nuclear Information System (INIS)

    Domingos, Érica Nascimento; Lima, Zelmo Rodrigues de; Aguiar, Laís Alencar de

    2017-01-01

    A fire at radioactive waste deposit can result in significant damage as well as serious risks to the environment and the health of the general public. The CNEN (National Commission of Nuclear Energy) norms have fire protection regulations criteria and requirements to prevent the occurrence, neutralize the action and minimize the effects of the fire on the radioactive material present on the plant. These norms it is for to avoid or limit to the lowest possible levels the effects of ionizing radiation or toxic substances on humans and the environment. Before a possible fire containing radioactive material is necessary information that can estimate the dose in which the population will be submitted. In this work the proposal is to simulate a fire scenario containing radioactive material using Hotspot Health Physics simulation code and to identify the radiological risk of cancer in the respiratory system associated with this scenario using the BEIR V model. (author)

  16. Simulation of fire in a deposit of radioactive waste and the radiological risk associated to this scenario

    Energy Technology Data Exchange (ETDEWEB)

    Domingos, Érica Nascimento; Lima, Zelmo Rodrigues de, E-mail: erica.ndomingos@gmail.com, E-mail: zrlima@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Aguiar, Laís Alencar de, E-mail: laguiars@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    A fire at radioactive waste deposit can result in significant damage as well as serious risks to the environment and the health of the general public. The CNEN (National Commission of Nuclear Energy) norms have fire protection regulations criteria and requirements to prevent the occurrence, neutralize the action and minimize the effects of the fire on the radioactive material present on the plant. These norms it is for to avoid or limit to the lowest possible levels the effects of ionizing radiation or toxic substances on humans and the environment. Before a possible fire containing radioactive material is necessary information that can estimate the dose in which the population will be submitted. In this work the proposal is to simulate a fire scenario containing radioactive material using Hotspot Health Physics simulation code and to identify the radiological risk of cancer in the respiratory system associated with this scenario using the BEIR V model. (author)

  17. U.S. port commerce in radioactive materials

    International Nuclear Information System (INIS)

    Marti, B.E.

    1987-01-01

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

  18. Transport of radioactive materials by post

    International Nuclear Information System (INIS)

    1984-11-01

    The objective of the Seminar was to encourage safe and efficient carriage of radioactive material by post. Adequate, up-to-date regulations for international and domestic shipment of radioactive material by all modes of transport, including by mail, have been published by the IAEA. UPU, ICAO, IATA and other international organizations as well as a majority of the countries of the world have adopted most sections of the Agency's Regulations for the Safe Transport of Radioactive Material. Although there is an apparent need for shipping radioactive material by mail, some countries allow only domestic shipments and the postal regulations applied in these countries often differs from the international regulations. Only about 25 countries are known to allow international (as well as domestic) shipments. From the discussions and comments at the Seminar, it appears that the option of shipment by post would be advantageous to enhance both the safety and economy of transporting, as well as to increase availability of, radioactive materials. The Agency's Regulations for transport by post as adopted by the UPU and ICAO are considered to provide a high level of safety and ensure a negligible element of risk. A more uniform application of these regulations within UPU Member States should be encouraged. The competent authority for implementation of the other parts of the Agency's Regulations in each of the Member States should be invited to advise the Postal Administrators and assist in applying the requirements to national as well as international postal shipments

  19. A feasibility study for the design of a simulated radioactive waste repository facility

    International Nuclear Information System (INIS)

    1986-10-01

    The paper contains the text and references of a feasibility study for the design of a simulated radioactive waste repository facility (final report). The work was commissioned by the Department of the Environment, United Kingdom, as part of its radioactive waste management research programme. The nature of the candidate buffer materials, the factors defining their behaviour, and the nature of a buffer material selection and testing programme, are examined. A description is given of the properties and modelling of host materials. The complex interactions between host materials, and between buffer and host materials, are discussed, along with the instrumentation requirements for measuring the interactions. Finally, the temperature field around a waste package, and modelling a host continuum with a segmental block, are both investigated. (U.K.)

  20. Very low level radioactive material

    International Nuclear Information System (INIS)

    Schaller, K.H.; Linsley, G.; Elert, M.

    1993-01-01

    Man's environment contains naturally occurring radionuclides and doses from exposures to these radionuclides mostly cannot be avoided. Consequently, almost everything may be considered as very low level radioactive material. In practical terms, management and the selection of different routes for low level material is confined to material which was subject to industrial processing or which is under a system of radiological control. Natural radionuclides with concentrations reaching reporting or notification levels will be discussed below; nevertheless, the main body of this paper will be devoted to material, mainly of artificial origin, which is in the system involving notification, registration and licensing of practices and sources. It includes material managed in the nuclear sector and sources containing artificially produced radionuclides used in hospitals, and in industry. Radioactive materials emit ionising radiations which are harmful to man and his environment. National and international regulations provide the frame for the system of radiation protection. Nevertheless, concentrations, quantities or types of radionuclide may be such, that the material presents a very low hazard, and may therefore be removed from regulatory control, as it would be a waste of time and effort to continue supervision. These materials are said to be exempted from regulatory control. Material exempted in a particular country is no longer distinguishable from ''ordinary'' material and may be moved from country to country. Unfortunately, criteria for exempting radioactive materials differ strongly between countries and free trade. Therefore there is a necessity for an international approach to be developed for exemption levels

  1. Response to Illicit Trafficking of Radioactive Materials

    International Nuclear Information System (INIS)

    2010-01-01

    Two response paths are discussed in the presentation. Reactive response follows when an alarm of a border monitor goes off or a notification is received about an incident involving or suspected to involve radioactive materials. The response can also be the result of the finding of a discrepancy between a customs declaration form and the corresponding actual shipment. Proactive response is undertaken upon receipt of intelligence information suggesting the illicit trafficking of radioactive materials, notification about the discovery of non-compliance with transport regulations or if discrepancies are found in an inventory of radioactive materials.

  2. 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

  3. A method for prevention of radioactive material release

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  4. Background radioactivity in environmental materials

    International Nuclear Information System (INIS)

    Maul, P.R.; O'Hara, J.P.

    1989-01-01

    This paper presents the results of a literature search to identify information on concentrations of 'background' radioactivity in foodstuffs and other commonly available environmental materials. The review has concentrated on naturally occurring radioactivity in foods and on UK data, although results from other countries have also been considered where appropriate. The data are compared with established definitions of a 'radioactive' substance and radionuclides which do not appear to be adequately covered in the literature are noted. (author)

  5. Radioactive material inventory control at a waste characterization facility

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  6. 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

  7. The safe transport of radioactive materials

    International Nuclear Information System (INIS)

    Swindell, G.E.

    1975-01-01

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

  8. Spreadsheet application to classify radioactive material for shipment

    International Nuclear Information System (INIS)

    Brown, A.N.

    1997-12-01

    A spreadsheet application has been developed at the Idaho National Engineering and Environmental Laboratory to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by this spreadsheet are used to confirm the proper US Department of Transportation (DOT) classification when offering radioactive material packages for transport. The user must input to the spreadsheet the mass of the material being classified, the physical form (liquid or not), and the activity of each regulated nuclide. The spreadsheet uses these inputs to calculate two general values: (1) the specific activity of the material, and (2) a summation calculation of the nuclide content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive material (Yes or No). If the material is calculated to be radioactive, the specific activity is also used to determine if the material meets the activity requirement for one of the three Low Specific Activity designations (LSA-I, LSA-II, LSA-III, or Not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity)

  9. Development of an expert system for radioactive material transportation

    International Nuclear Information System (INIS)

    Tamanoi, K.; Ishitobi, M.; Shinohara, Y.

    1990-01-01

    An expert system to deal with radioactive material transportation was developed. This expert system is based on 'Regulations for the Safe Transport of Radioactive Material' by IAEA issued 1985. IAEA published the regulations under such environments that safety transportation has become increasingly being focused as uses of radioactive materials are more pervasive, not only in nuclear field but also in non-nuclear purposes. Attentions are payed for operators and environment to establish safety in handling radioactive materials. In the 1985 regulations, detailed categorization of radioactive materials and, correspondingly, new classification of packages are introduced. This categorization is more complicated than old regulations, leading us to develop an expert system to evaluate easily the packages categorization. (author)

  10. The management of radioactive materials spills

    International Nuclear Information System (INIS)

    Ryan, M.T.; Ebenhack, D.G.

    1985-01-01

    The management and handling of a radioactive materials spill must be swift and effective to reduce or mitigate any adverse impacts on public health and safety. Spills within nuclear facilities generally pose less of a public health impact than spills in areas of public access. The essential elements of spill management include prior planning by agencies which may be required to respond to a spill. Any plan for the management of radioactive materials spills must be flexible enough to be applied in a variety of situations. The major elements of a radioactive materials spill plan, however, apply in every case. It is essential that communications be clear and effective, that the management of a spill be directed by a responsible party whose authority is recognized by everyone involved and that the actions, according to the principles discussed above, be taken to assure the safety of any injured personnel, containment and stabilization and clean up the spill and to verify through radiological surveys and sample analyses that the clean up is complete. Any spill of radioactive materials, minor or major, should be assessed so that similar spills or accidents can be prevented

  11. Engineering materials for high level radioactive waste repository

    International Nuclear Information System (INIS)

    Wen Zhijian

    2009-01-01

    Radioactive wastes can arise from a wide range of human activities and have different physical and chemical forms with various radioactivity. The high level radioactive wastes (HLW)are characterized by nuclides of very high initial radioactivity, large thermal emissivity and the long life-term. The HLW disposal is highly concerned by the scientists and the public in the world. At present, the deep geological disposal is regarded as the most reasonable and effective way to safely dispose high-level radioactive wastes in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineering barrier system(EBS). The engineering materials in EBS include the vitrified HLW, canister, overpack, buffer materials and backfill materials. Referring to progress in the world, this paper presents the function, the requirement for material selection and design, and main scientific projects of R and D of engineering materials in HLW repository. (authors)

  12. Transport of radioactive material in Sudan practice and regulations

    International Nuclear Information System (INIS)

    Abdalla, M. K. E.

    2010-12-01

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

  13. Transport of radioactive material in Bangladesh: a regulatory perspective

    International Nuclear Information System (INIS)

    Mollah, A.S.

    2004-01-01

    Radioactive material is transported in Bangladesh in various types of packages and by different modes of transport. The transport of radioactive materials involves a risk both for the workers and members of the public. The safe transport of radioactive material is ensured in Bangladesh by compliance with Nuclear Safety and Radiation Control (NSRC) Act-93 and NSRC Rules-97. The Bangladesh Atomic Energy Commission (BAEC) is the competent authority for the enforcement of the NSRC act and rules. The competent authority has established regulatory control at each stage to ensure radiation safety to transport workers, members of general public and the environment. An overview is presented of the activities related to the transport of radioactive material in Bangladesh. In particular, the applicable legislation, the scope of authority and the regulatory functions of the competent authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (author)

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

    International Nuclear Information System (INIS)

    Rubin, L.S.

    1986-01-01

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

  15. Low-Level Radioactive Waste siting simulation information package

    International Nuclear Information System (INIS)

    1985-12-01

    The Department of Energy's National Low-Level Radioactive Waste Management Program has developed a simulation exercise designed to facilitate the process of siting and licensing disposal facilities for low-level radioactive waste. The siting simulation can be conducted at a workshop or conference, can involve 14-70 participants (or more), and requires approximately eight hours to complete. The exercise is available for use by states, regional compacts, or other organizations for use as part of the planning process for low-level waste disposal facilities. This information package describes the development, content, and use of the Low-Level Radioactive Waste Siting Simulation. Information is provided on how to organize a workshop for conducting the simulation. 1 ref., 1 fig

  16. 49 CFR 173.428 - Empty Class 7 (radioactive) materials packaging.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Empty Class 7 (radioactive) materials packaging... SHIPPERS-GENERAL REQUIREMENTS FOR SHIPMENTS AND PACKAGINGS Class 7 (Radioactive) Materials § 173.428 Empty Class 7 (radioactive) materials packaging. A packaging which previously contained Class 7 (radioactive...

  17. Detection of smuggling of nuclear material covered by a legal transport of radioactive material

    International Nuclear Information System (INIS)

    Safar, J.; Zsigrai, J.; Tam, N.C.; Lakosi, L.

    2001-01-01

    Full text: One of the worst scenarios for detection of illicit trafficking of nuclear material is when a legal transport of radioactive material is used to cover the radiation of the smuggled uranium. Feasibility study was performed in the Institute of Isotopes and Surface Chemistry of the Chemical Research Centre of the Hungarian Academy of Sciences (hereinafter: Institute) in order to study the possible on site measurement techniques and approaches applicable in such cases. As the type A and type B packages always incorporate a feature such as a seal, in a realistic scenario the confiscated nuclear material is expected to be placed outside the package. The passive neutron emission of the uranium is negligible for a reasonable isotopic abundance therefore the feasibility study was concentrating on non-destructive, passive gamma- spectrometric methods. Possible application of Nal (diameter 40x40 mm 3 , large planar (15x15x3 mm 3 ) and a hemispheric CdZnTe (500 mm 3 , and high purity Germanium detectors was investigated. During the on site measurements portable electronics, mini multichannel analyzer, palmtop and/or notebook computer were used. The shielding material of the packages was lead or depleted uranium. The smuggled material was simulated by a package of reactor fuel pellets containing low enriched or natural uranium (materials confiscated in earlier cases) and standards containing low enriched uranium. During the supposed scenario the portal monitor provides an indication of an elevated level of the environmental radioactivity. Then the responsible (e.g. customs) officer investigate the vehicle by a hand-held survey meter in order to search for peaks in dose rates. If a peak was localized, which is different from the position of the legally transported package(s) the officer requests for the expertise of the designated institutes. The following model cases provided the basic conclusion: 1. The legal transport of the radioactive material was simulated by a

  18. The radioactivity of house-building materials

    International Nuclear Information System (INIS)

    Sos, K.

    2007-01-01

    The paper compares the natural radioactivity and radon emission properties of different building materials like bricks, concretes, cements, sands, limes, marmors of different origin. A description of the radioactive model of apartments is also given. (TRA)

  19. Procedures for the Safe Transport of Radioactive Material

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jang Lyul; Chung, K. K.; Lee, J. I.; Chang, S. Y.; Lee, T. Y

    2007-11-15

    This technical report describes the procedure and work responsibility along with the regulation and standard necessary for the safe transport of radioactive or contaminated materials. This report, therefore, can be effectively used to secure the public safety as well as to prevent the disastrous event which might be resulted from the transport process of radioactive materials by establishing a procedure and method on the safe packing, handling and transport of radioactive materials.

  20. Test for radioactive material transport package safety

    International Nuclear Information System (INIS)

    Li Guoqiang; Zhao Bing; Zhang Jiangang; Wang Xuexin; Ma Anping

    2012-01-01

    Regulations on radioactive material transport in China were introduced. Test facilities and data acquiring instruments for radioactive material package in China Institute for Radiation Protection were also introduced in this paper, which were used in drop test and thermal test. Test facilities were constructed according to the requirements of IAEA's 'Regulations for the Safe Transport of Radioactive Material' (TS-R-l) and Chinese 'Regulations for the Safe Transport of Radioactive Material' (GB 11806-2004). Drop test facilities were used in free drop test, penetration test, mechanical test (free drop test Ⅰ, free drop test Ⅱ and free drop test Ⅲ) of type A and type B packages weighing less than thirteen tons. Thermal test of type B packages can be carried out in the thermal test facilities. Certification tests of type FCo70-YQ package, type 30A-HB-01 package, type SY-I package and type XAYT-I package according to regulations were done using these facilities. (authors)

  1. Issues in recycling and disposal of radioactively contaminated materials

    International Nuclear Information System (INIS)

    Kluk, A.F.; Hocking, E.K.; Roberts, R.; Phillips, J.W.

    1993-01-01

    The Department of Energy's present stock of potentially re-usable and minimally radioactively contaminated materials will increase significantly as the Department's remediation activities expand. As part of its effort to minimize wastes, the Department is pursuing several approaches to recover valuable materials such as nickel, copper, and steel, and reduce the high disposal costs associated with contaminated materials. Key approaches are recycling radioactively contaminated materials or disposing of them as non-radioactive waste. These approaches are impeded by a combination of potentially conflicting Federal regulations, State actions, and Departmental policies. Actions to promote or implement these approaches at the Federal, State, or Departmental level involve issues which must be addressed and resolved. The paramount issue is the legal status of radioactively contaminated materials and the roles of the Federal and State governments in regulating those materials. Public involvement is crucial in the debate surrounding the fate of radioactively contaminated materials

  2. Combating illicit trafficking in nuclear and other radioactive material. Reference material

    International Nuclear Information System (INIS)

    2007-01-01

    This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

  3. Radioactive Material Containment Bags

    National Research Council Canada - National Science Library

    2000-01-01

    The audit was requested by Senator Joseph I. Lieberman based on allegations made by a contractor, Defense Apparel Services, about the Navy's actions on three contracts for radioactive material containment bags...

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

    International Nuclear Information System (INIS)

    Scott, L.M.

    1997-01-01

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

  5. Transportation accidents/incidents involving radioactive materials (1971--1991)

    International Nuclear Information System (INIS)

    Cashwell, C.E.; McClure, J.D.

    1992-01-01

    The Radioactive Materials Incident Report (RMIR) database contains information on transportation-related accidents and incidents involving radioactive materials that have occurred in the United States. The RMIR was developed at Sandia National Laboratories (SNL) to support its research and development program efforts for the US Department of Energy (DOE). This paper will address the following topics: background information on the regulations and process for reporting a hazardous materials transportation incident, overview data of radioactive materials transportation accidents and incidents, and additional information and summary data on how packagings have performed in accident conditions

  6. Denials and Delays of Radioactive Material Shipments

    International Nuclear Information System (INIS)

    El-Shinawy, R.M.K.

    2011-01-01

    delays of shipments of radioactive materials forms an important issue today. Radioactive materials need to be transported using all modes of transport for use in different applications such as public health, industry, research and production of nuclear power. The transport of radioactive materials is governed by national and international regulations, which are based on the International Atomic Energy Agency (IAEA) regulations for safe transport of radioactive materials (TS-R-1). These regulations ensure high standards of safety. Recently there were increasing numbers of instances of denials and delays of shipments of radioactive materials even when complying with the regulations. The denials and delays can result in difficulties to patients and others who rely on products sterilized by radiation. Therefore there is an urgent need for a universally accepted approach to solve this problem. In response, the IAEA has formed an International Steering Committee (ISC) on denials and delays of radioactive materials. Also, it designate the National Focal Points (NFP) representative to help the ISC members and the IAEA by informing about denial operations and how they can help. The Steering Committee developed and adopted an action plan which includes the action to be taken. This plan is based on: Awareness, Training, Communication, Lobbying for marketing, Economic and Harmonization among member states. It is important to work within the mandate of the ISC and in the line of action plan on denials and delays. It identified the following network members such as: National Focal Points, Regional Coordinators, National Committee, National Representative for different modes of transport and similar bodies, Carriers, Producers and Suppliers, Different civil societies, NGO's, Ministry of transport and others.

  7. Treating agent for urea containing radioactive materials

    International Nuclear Information System (INIS)

    Ogawa, Hiroshi; Maki, Kentaro.

    1973-01-01

    Object: To add a coagulant into urea containing radioactive material to precipitate and remove the radioactive material in the urea. Structure: Iodosalt is added into urea and next, a mixed reagent in which silver ion or silver acetic ion and iron hydroxide precipitation or ferrite ion coexist is added therein. The urea is treated to have a sufficient alkaline, after which it is introduced into a basket type centrifuge formed with a filter layer in combination of an upper glass fiber layer and a lower active carbon layer. The treating agent can uniformly remove radioactive ion and radioactive chelate within urea containing inorganic salt and various metabolites. (Nakamura, S.)

  8. Safety of transport of radioactive material. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    Radioactive material has been transported for decades within and between countries as the use of radioactive material to benefit mankind has expanded. The transport can involve many types of materials (radionuclides and radiation sources for applications in agriculture, energy production, industry, and medicine) and all modes of transport (road, rail, sea and waterways, and air). Among the organizations in the United Nations system, the International Atomic Energy Agency (IAEA) has the statutory function to establish or adopt standards of safety for protection of health against exposure to ionizing radiation. Within its statutory mandate and pursuant to this request, in 1961, the IAEA issued Regulations for the Safe Transport of Radioactive Material (the IAEA Transport Regulations). The Transport Regulations were periodically reviewed and, as appropriate, have been amended or revised. The latest version of the Transport Regulations was issued in 2000 by the IAEA as Publication TS-R-1 (ST-1, Revised). In addition, the IAEA is entrusted by its Statute to provide for the application of its standards at the request of States. The objective of the Conference is to foster the exchange of information on issues related to the safety of transport of radioactive material by providing an opportunity for representatives from sponsoring international organizations and their Member States and from other co-operating and participating organizations to discuss critical issues relating to the safety of transport of radioactive material by all modes and to formulate recommendations, as appropriate, regarding further international co-operation in this area. The following topics have been identified by the Technical Programme Committee as the subjects to be covered in the background briefing sessions: History and Status of the IAEA Transport Regulation Development; Experience in adoption of the IAEA Transport Regulations at the international level; Implementation of the IAEA Transport

  9. Alternate Materials In Design Of Radioactive Material Packages

    International Nuclear Information System (INIS)

    Blanton, P.; Eberl, K.

    2010-01-01

    This paper presents a summary of design and testing of material and composites for use in radioactive material packages. These materials provide thermal protection and provide structural integrity and energy absorption to the package during normal and hypothetical accident condition events as required by Title 10 Part 71 of the Code of Federal Regulations. Testing of packages comprising these materials is summarized.

  10. Spread-sheet application to classify radioactive material for shipment

    International Nuclear Information System (INIS)

    Brown, A.N.

    1998-01-01

    A spread-sheet application has been developed at the Idaho National Engineering and Environmental Laboratory to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by this spread-sheet are used to confirm the proper US DOT classification when offering radioactive material packages for transport. The user must input to the spread-sheet the mass of the material being classified, the physical form (liquid or not) and the activity of each regulated nuclide. The spread-sheet uses these inputs to calculate two general values: 1)the specific activity of the material and a summation calculation of the nuclide content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive material. If the material is calculated to be radioactive, the specific activity is also used to determine if the material meets the activity requirement for one of the three low specific activity designations (LSA-I, LSA-II, LSA-III, or not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity). This spread-sheet has proven to be an invaluable aid for shippers of radioactive materials at the Idaho National Engineering and Environmental Laboratory. (authors)

  11. Fire simulation in radioactive waste disposal and the radiation risk associated

    International Nuclear Information System (INIS)

    Domingos, Érica Nascimento

    2018-01-01

    An atmospheric dispersion of radioactive material is one of the possible consequences of an accident scenario in nuclear installations, radiative and radioactive waste deposit. Taking into account a possibility of this release of radioactive material into the atmosphere this work proposes a modeling of the atmospheric dispersion from a fire scenario in a deposit of radioactive waste of low and middle level of radiation varying the amount of inventory released in the fire. For this simulation was adopted the software of physical codes of medical health, the HotSpot Health Physics Codes which uses the Gaussian model to calculate an atmospheric dispersion based on the Pasquill atmospheric stability classes. This software calculates a total effective dose in relation to distance, such as a compromised dose in a list of specific organs, among them the lung, object of work study for calculating the risk of cancer associated with a low dose of radiation. The radiological risk calculation is held by the BEIR V model, Biological Effects of Ionizing Radiations, one of the models to estimate the relative risk of cancer induced by ionizing radiation. (author)

  12. The safe transport of radioactive material in South Africa

    International Nuclear Information System (INIS)

    Jutle, K.K.

    1997-01-01

    An overview is presented of the activities related to the transport of radioactive material in South Africa. In particular, the applicable legislation, the scope of authority and regulatory functions of the Competent Authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (Author)

  13. The safe transport of radioactive material in South Africa

    International Nuclear Information System (INIS)

    Jutle, K.K.

    2000-01-01

    An overview is presented of the activities related to the transport of radioactive material in South Africa. In particular, the applicable legislation, the scope of authority and the regulatory functions of the Competent Authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (author)

  14. The measurement theory of radioactivity in building materials

    International Nuclear Information System (INIS)

    Qu Jinhui; Wang Renbo; Zhang Xiongjie; Tan Hai; Zhu Zhipu; Man Zaigang

    2010-01-01

    Radioactivity in Building Materials is the main source of natural radiation dose that the individual is received, which has caused serious concern of all Social Sector. The paper completely introduce the measurement theory of the Radioactivity in Building Materials along with the measurement principle of natural radioactivity, design of shielding facility, choosing measurement time, sample prepared and spectrum analyzed. (authors)

  15. Miscellaneous radioactive materials detected during uranium mill tailings surveys

    International Nuclear Information System (INIS)

    Wilson, M.J.

    1993-10-01

    The Department of Energy's (DOE) Office of Environmental Restoration and Waste Management directed the Oak Ridge National Laboratory Pollutant Assessments Group in the conduct of radiological surveys on properties in Monticello, Utah, associated with the Mendaciously millsite National Priority List site. During these surveys, various radioactive materials were detected that were unrelated to the Monticello millsite. The existence and descriptions of these materials were recorded in survey reports and are condensed in this report. The radioactive materials detected are either naturally occurring radioactive material, such as rock and mineral collections, uranium ore, and radioactive coal or manmade radioactive material consisting of tailings from other millsites, mining equipment, radium dials, mill building scraps, building materials, such as brick and cinderblock, and other miscellaneous sources. Awareness of the miscellaneous and naturally occurring material is essential to allow DOE to forecast the additional costs and schedule changes associated with remediation activities. Also, material that may pose a health hazard to the public should be revealed to other regulatory agencies for consideration

  16. Nuclear radioactive techniques applied to materials research

    CERN Document Server

    Correia, João Guilherme; Wahl, Ulrich

    2011-01-01

    In this paper we review materials characterization techniques using radioactive isotopes at the ISOLDE/CERN facility. At ISOLDE intense beams of chemically clean radioactive isotopes are provided by selective ion-sources and high-resolution isotope separators, which are coupled on-line with particle accelerators. There, new experiments are performed by an increasing number of materials researchers, which use nuclear spectroscopic techniques such as Mössbauer, Perturbed Angular Correlations (PAC), beta-NMR and Emission Channeling with short-lived isotopes not available elsewhere. Additionally, diffusion studies and traditionally non-radioactive techniques as Deep Level Transient Spectroscopy, Hall effect and Photoluminescence measurements are performed on radioactive doped samples, providing in this way the element signature upon correlation of the time dependence of the signal with the isotope transmutation half-life. Current developments, applications and perspectives of using radioactive ion beams and tech...

  17. Storage of solid and liquid radioactive material

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-01-01

    Solid radioactive waste collected during 1961 from the laboratories of the Institute amounted to 22.5 m 3 . This report contains data about activity of the waste collected from january to November 1961. About 70% of the waste are short lived radioactive material. Material was packed in metal barrels and stored in the radioactive storage in the Institute. There was no contamination of the personnel involved in these actions. Liquid radioactive wastes come from the Isotope production laboratory, laboratories using tracer techniques, reactor cooling; decontamination of the equipment. Liquid wastes from isotope production were collected in plastic bottles and stored. Waste water from the RA reactor were collected in special containers. After activity measurements this water was released into the sewage system since no activity was found. Table containing data on quantities and activity of radioactive effluents is included in this report

  18. Virtual reality in simulation of operational procedures in radioactive waste deposits

    International Nuclear Information System (INIS)

    Freitas, Victor Goncalves Gloria

    2016-01-01

    One of the biggest problems in the nuclear area are still the radioactive waste generated in the various applications of this form of energy, all these tailings are stored in warehouses that often are monitored and restructured for better allocation of then. These tailings are stored until it is safe to release into the environment. This work presents a methodology based on virtual reality, for the development of virtual deposits of radioactive waste in order to enable virtual simulations in these deposits. As application will be developed virtually the nuclear waste repository located at the Institute of Nuclear Engineering IEN/CNEN. The development of a virtual warehouse, more specifically, makes it possible to simulate/train the allocation and reallocation of materials with low and medium level of radioactivity, seen the possibility of locomotion of virtual objects and dynamic calculation of the rate of radiation in this environment. Using this methodology it also possible know the accumulated dose, by the virtual character, during the procedures run in the virtual environment. (author)

  19. Licenses for possessing and applying radioactive sources, materials, etc

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Commercial and governmental institutions have been licensed by Dutch authorities to possess and apply radioactive sources, materials, etc. A summary is given and the list is subdivided into a number of sections such as radioactive sources, radioactive materials, X-ray equipment and technetium-generators

  20. RADIOACTIVE MATERIALS SENSORS

    International Nuclear Information System (INIS)

    Mayo, Robert M.; Stephens, Daniel L.

    2009-01-01

    Providing technical means to detect, prevent, and reverse the threat of potential illicit use of radiological or nuclear materials is among the greatest challenges facing contemporary science and technology. In this short article, we provide brief description and overview of the state-of-the-art in sensor development for the detection of radioactive materials, as well as an identification of the technical needs and challenges faced by the detection community. We begin with a discussion of gamma-ray and neutron detectors and spectrometers, followed by a description of imaging sensors, active interrogation, and materials development, before closing with a brief discussion of the unique challenges posed in fielding sensor systems.

  1. Regulation of Transportation of Radioactive Material in Indonesia

    International Nuclear Information System (INIS)

    Nirwono, Muttaqin Margo; Choi, Kwang Sik

    2011-01-01

    1.1. Background Indonesia is a biggest archipelago country with 17,508 islands in 33 provinces. In transportation Indonesia has large number of airports, railways, roadways, waterways, and merchant marines. Since nuclear and radiation utilizations are expanding on whole country, the mobilization of these is usually placed outside of controlled facilities, in the public domain, and often entails movement between countries. The Indonesian Nuclear Energy Regulatory Agency (BAPETEN) is responsible for supervision and also authorization of the transport of radioactive material (TRM). TRM is the specific movement of a radioactive material consignment from origin to destination by public transportation (road or rail, water and air). This study aims to determine whether national regulation is harmonized with international practice in ensuring safety and security of TRM. The finding of this study will provide recommendation for enhancement of regulation on TRM. 1.2. Regulation of TRM in Indonesia Government Regulation (GR) No. 26, 2002 on the Safe Transport of Radioactive Material is implemented pursuant to Act 10, 1997 on Nuclear Energy. This GR was repealed GR 13, 1975 on TRM. The GR 26 consist of 16 chapters and 39 articles, included licensing: authority and responsibilities: packaging: radiation protection programme; training: quality assurance programme: type and activity limit of radioactive materials: radioactive materials with other dangerous properties: emergency preparedness: administrative sanction: and penal provisions. Principally, this GR adopted IAEA-TS-R-1, 'Regulations for the Safe Transport of Radioactive Material', 1996's Edition

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

    International Nuclear Information System (INIS)

    2003-05-01

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

  3. Study on rich alumina alkali-activated slag clay minerals cementitious materials for immobilization of radioactive waste

    International Nuclear Information System (INIS)

    Li Yuxiang; Qian Guangren; Yi Facheng; Shi Rongming; Fu Yibei; Li Lihua; Zhang Jun

    1999-01-01

    The composition and some properties of its pastes of rich alumina alkali-activated slag clay minerals (RAAASCM) cementitious materials for immobilization of radioactive waste are studied. Experimental results show that heat activated kaolinite, Xingjiang zeolite, modified attapulgite clay are better constituents of RAAASCM. RAAASCM cementitious materials pastes exhibit high strength, low porosity, fewer harmful pore, and high resistance to sulphate corrosion as well as gamma irradiation. The Sr 2+ , Cs + leaching portion of the simulated radioactive waste forms based on RAAASCM, is low

  4. State statutes and regulations on radioactive materials transportation

    International Nuclear Information System (INIS)

    Foster, B.

    1981-11-01

    The transport of radioactive material is controlled by numerous legislative and regulatory actions at the federal, state, and local levels. This document is a compilation of the state level laws and regulations. The collected material is abstracted and indexed by states. Each state section contains three divisions: (1) abstracts of major statutes, (2) legislative rules, and (3) photocopies of relevant paragraphs from the law or regulation. This document was prepared for use by individuals who are involved in the radioactive material transportation process. This document will not be updated. The legislative rules section contains the name of the state agency primarily responsible for monitoring the transport of radioactive materials

  5. Measurement of liquid radioactive materials for monitoring radioactive emissions

    International Nuclear Information System (INIS)

    1977-10-01

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

  6. Security of radioactive materials for medical use

    International Nuclear Information System (INIS)

    Elliott, A.

    2006-01-01

    Both sealed and unsealed radioactive sources are used in hospitals throughout the world for diagnostic and therapeutic purposes. High activity single sealed sources are used in teletherapy units, although these are becoming less common as they are replaced by linear accelerators, and in blood irradiator units, which are in widespread use. Lower activity sealed sources are used in brachytherapy. High activity unsealed sources are used typically for the treatment of thyroid cancer and neuroblastoma in inpatients while diagnostic doses of unsealed radioactive materials have much lower activities. In the case of a central radiopharmacy producing patient doses of radiopharmaceutical for several Nuclear Medicine departments, however, quite large amounts of radioactive materials may be held. Hospitals are, by their nature, less secure than other licensed nuclear sites and the ever-changing patient /visitor (and staff) population is a further complicating factor. Hitherto, security of radioactive materials in hospitals has tended to be considered from the perspective only of radiation safety but this approach is no longer sufficient

  7. Safe Transport of Radioactive Material, Philosophy and Overview

    Energy Technology Data Exchange (ETDEWEB)

    EL-Shinawy, R M.K. [Radiation Protection Dept., Nuclear Rasearch Center, Atomic Energy Authority, Cairo (Egypt)

    2008-07-01

    Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international and national regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1(ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series Nos 7and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series Nos 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS no.113), compliance assurance (SS no. 112), the training manual and others.

  8. Safe Transport of Radioactive Material, Philosophy and Overview

    International Nuclear Information System (INIS)

    EL-Shinawy, R.M.K.

    2008-01-01

    Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international and national regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1(ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series Nos 7and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series Nos 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS no.113), compliance assurance (SS no. 112), the training manual and others

  9. Radioactivity of building materials

    International Nuclear Information System (INIS)

    Terpakova, E.

    2000-01-01

    In this paper the gamma-spectrometric determination of natural radioactivity in the different building materials and wares applied in Slovakia was performed. The specific activities for potassium-40, thorium, radium as well as the equivalent specific activities are presented

  10. Statistics of foreign trade in radioactive materials

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    The German Federal Office for Industry and Foreign Trade Control (BAFA) keeps annual statistics of the imports and exports of radioactive materials, nuclear fuels included. The entries, some of them with precise details, cover the participating countries and the radionuclides concerned as well as all kinds of radioactive materials. The tables listed in the article represent the overall balance of the development of imports and exports of radioactive materials for the years 1983 to 2000 arranged by activity levels, including the development of nuclear fuel imports and exports. For the year 2000, an additional trade balance for irradiated and unirradiated nuclear fuels and source materials differentiated by enrichment is presented for the countries involved. In 2000, some 2446 t of nuclear fuels and source materials were imported into the Federal Republic, while approx. 2720 t were exported. The chief trading partners are countries of the European Union and Russia, South Korea, and Brazil. (orig.) [de

  11. Radioactive Substances Act 1960. Keeping and use of radioactive materials; list of registrations in England and Wales issued under the Radioactive Substances Act 1960 for the keeping and use of radioactive materials and mobile

    International Nuclear Information System (INIS)

    1989-05-01

    Through the Radioactive Substances Act 1960 (RSA 60), Her Majesty's Inspectorate of Pollution (Radioactive Substances) (HMIP) exercises control, on behalf of the Secretary of State for the Environment, over the keeping and use of radioactive material and the accumulation and disposal of radioactive waste in England. HMIP also provides technical advice to the Secretary of State for Wales in connection with the enforcement of RSA 60 in Wales. Registrations under RSA 60 for the keeping and use of radioactive materials in England and Wales are issued respectively by the Secretaries of State for the Environment and Wales, following careful assessment of the radiological consequences for members of the public. Registrations impose strict limits and conditions and premises and apparatus are subject to scrutiny by HMIP Inspectors to ensure compliance. A list contains names and addresses of those registered in England and Wales for the keeping and use of radioactive materials and mobile apparatus

  12. Transport of bundles and equipment which contain radioactive material

    International Nuclear Information System (INIS)

    1987-01-01

    This norm settles down: 1) The requirements that should be completed in relation to safety precautions and protection against ionizing radiations during the transport radioactive material and/or equipment containing it, in order to avoid risks to the collective and the environment. 2) The basic information on procedures that will be completed in the event of happening accidents during the transport or the transit storage of radioactive material and/or equipment that contain it. 3) The measures of security and physical protection during the transport of radioactive material and/or equipment containing it. This norm is applied: 1) To all the ways of transport (by air, by ground and by ship, fluvial and marine) of radioactive material and/or equipment that contain it. 2) To all natural or legal, public or private person, devoted to install, produce, trade, market, import or export radioactive materials and/or equipment containing it, and that needs to transport them as main or secondary activity [es

  13. Novel methods for estimating 3D distributions of radioactive isotopes in materials

    Energy Technology Data Exchange (ETDEWEB)

    Iwamoto, Y., E-mail: y.iwamoto0805@ruri.waseda.jp [Research Institute for Science and Engineering, Waseda University, Shinjuku, Tokyo 169-8555 (Japan); Kataoka, J.; Kishimoto, A.; Nishiyama, T.; Taya, T.; Okochi, H.; Ogata, H. [Research Institute for Science and Engineering, Waseda University, Shinjuku, Tokyo 169-8555 (Japan); Yamamoto, S. [Nagoya University Graduate School of Medicine, 1-1-20, Daikominami, Higashi-ku, Nagoya-shi, Aichi 461-8673 (Japan)

    2016-09-21

    In recent years, various gamma-ray visualization techniques, or gamma cameras, have been proposed. These techniques are extremely effective for identifying “hot spots” or regions where radioactive isotopes are accumulated. Examples of such would be nuclear-disaster-affected areas such as Fukushima or the vicinity of nuclear reactors. However, the images acquired with a gamma camera do not include distance information between radioactive isotopes and the camera, and hence are “degenerated” in the direction of the isotopes. Moreover, depth information in the images is lost when the isotopes are embedded in materials, such as water, sand, and concrete. Here, we propose two methods of obtaining depth information of radioactive isotopes embedded in materials by comparing (1) their spectra and (2) images of incident gamma rays scattered by the materials and direct gamma rays. In the first method, the spectra of radioactive isotopes and the ratios of scattered to direct gamma rays are obtained. We verify experimentally that the ratio increases with increasing depth, as predicted by simulations. Although the method using energy spectra has been studied for a long time, an advantage of our method is the use of low-energy (50–150 keV) photons as scattered gamma rays. In the second method, the spatial extent of images obtained for direct and scattered gamma rays is compared. By performing detailed Monte Carlo simulations using Geant4, we verify that the spatial extent of the position where gamma rays are scattered increases with increasing depth. To demonstrate this, we are developing various gamma cameras to compare low-energy (scattered) gamma-ray images with fully photo-absorbed gamma-ray images. We also demonstrate that the 3D reconstruction of isotopes/hotspots is possible with our proposed methods. These methods have potential applications in the medical fields, and in severe environments such as the nuclear-disaster-affected areas in Fukushima.

  14. Novel methods for estimating 3D distributions of radioactive isotopes in materials

    Science.gov (United States)

    Iwamoto, Y.; Kataoka, J.; Kishimoto, A.; Nishiyama, T.; Taya, T.; Okochi, H.; Ogata, H.; Yamamoto, S.

    2016-09-01

    In recent years, various gamma-ray visualization techniques, or gamma cameras, have been proposed. These techniques are extremely effective for identifying "hot spots" or regions where radioactive isotopes are accumulated. Examples of such would be nuclear-disaster-affected areas such as Fukushima or the vicinity of nuclear reactors. However, the images acquired with a gamma camera do not include distance information between radioactive isotopes and the camera, and hence are "degenerated" in the direction of the isotopes. Moreover, depth information in the images is lost when the isotopes are embedded in materials, such as water, sand, and concrete. Here, we propose two methods of obtaining depth information of radioactive isotopes embedded in materials by comparing (1) their spectra and (2) images of incident gamma rays scattered by the materials and direct gamma rays. In the first method, the spectra of radioactive isotopes and the ratios of scattered to direct gamma rays are obtained. We verify experimentally that the ratio increases with increasing depth, as predicted by simulations. Although the method using energy spectra has been studied for a long time, an advantage of our method is the use of low-energy (50-150 keV) photons as scattered gamma rays. In the second method, the spatial extent of images obtained for direct and scattered gamma rays is compared. By performing detailed Monte Carlo simulations using Geant4, we verify that the spatial extent of the position where gamma rays are scattered increases with increasing depth. To demonstrate this, we are developing various gamma cameras to compare low-energy (scattered) gamma-ray images with fully photo-absorbed gamma-ray images. We also demonstrate that the 3D reconstruction of isotopes/hotspots is possible with our proposed methods. These methods have potential applications in the medical fields, and in severe environments such as the nuclear-disaster-affected areas in Fukushima.

  15. International measures needed to protect metal recycling facilities from radioactive materials

    International Nuclear Information System (INIS)

    Mattia, M.; Wiener, R.

    1999-01-01

    In almost every major city and region of every country, there is a recycling facility that is designed to process or consume scrap metal. These same countries will probably have widespread applications of radioactive materials and radiation generating equipment. This material and equipment will have metal as a primary component of its housing or instrumentation. It is this metal that will cause these sources of radioactivity, when lost, stolen or mishandled, to be taken to a metal recycling facility to be sold for the value of the metal. This is the problem that has faced scrap recycling facilities for many years. The recycling industry has spent millions of dollars for installation of radiation monitors and training in identification of radioactive material. It has expended millions more for the disposal of radioactive material that has mistakenly entered these facilities. Action must be taken to prevent this material from entering the conventional recycling process. There are more than 2,300 known incidents of radioactive material found in recycled metal scrap. Worldwide, more than 50 smeltings of radioactive sources have been confirmed. Seven fatal accidents involving uncontrolled radioactive material have also been documented. Hazardous exposures to radioactive material have plagued not just the workers at metal recycling facilities. The families of these workers, including their children, have been exposed to potentially harmful levels of radioactivity. The threat from this material does not stop there. Radioactive material that is not caught at recycling facilities can be melted and the radioactivity has been found in construction materials used to build homes, as well as shovels, fencing material, and furniture offered for sale to the general public. The time has come for the international community to address the issue of the uncontrolled sources of radioactive material. The following are the key points that must be addressed. (i) Identification of sources

  16. Dynamic analysis to establish normal shock and vibration of radioactive material shipping packages

    International Nuclear Information System (INIS)

    Fields, S.R.

    1980-01-01

    A computer model, CARDS (Cask-Railcar Dynamic Simulator) was developed to provide input data for a broad range of radioactive material package-tiedown structural assessments. CARDS simulates the dynamic behavior of shipping packages and their transporters during normal transport conditions. The model will be used to identify parameters which significantly affect the normal shock and vibration environments which, in turn, provide the basis for determining the forces transmitted to the packages

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

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

    International Nuclear Information System (INIS)

    Masinza, S.A.

    2004-01-01

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

  20. Trasmar: automated vehicle for transport of radioactive materials

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  1. Ionising radiations, radioactive materials and the fire services

    International Nuclear Information System (INIS)

    Button, J.C.E.

    1981-05-01

    Extensive experience has shown that ionizing radiations and radioactive materials can be used safely in a wide variety of applications, provided a number of precautions are implemented. Transport of radioactive materials is common and regulations designed to ensure safety in such transport have resulted in an excellent safety record. Pre-planning for fire situations in buildings where radioactive materials are known to be present is very desirable. An Australian Standard, AS2243, recommends that Station Officers of the local fire brigade be appraised of the hazards and the need to take particular care in areas marked with ionizing radiation warning signs

  2. Storage containers for radioactive material

    International Nuclear Information System (INIS)

    Cassidy, D.A.; Dates, L.R.; Groh, E.F.

    1981-01-01

    A radioactive material storage system is disclosed for use in the laboratory. This system is composed of the following: a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof; a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate; the groove and the gasket, and a clamp for maintaining the cover and the plate are sealed together, whereby the plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage

  3. Method of treatment in a system passing radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Kamiya, K; Kinoshita, M; Asakura, Y

    1976-05-14

    A method to ensure the safety of the reactor and reduce radiation exposure dose by preventing oxygen hydrogen reaction of the reactor off-gas and accumulation of the radioactive material is described. Substances which are accumulated in an off-gas duct and are likely to capture radioactive material (for instance Pd catalyst falling from a recombiner) is changed into a stable material (for instance, PdI/sub 2/) which is hot likely to capture radioactive material through reaction with a stabilizer (for instance, I/sub 2/, Cl/sub 2/, HCl, etc.). This stabilized material is washed off the atomic power plant system.

  4. The development of shifting radioactive material

    International Nuclear Information System (INIS)

    Chen Haiteng; Chen Yonghong; Yin Fujun; Che Mingsheng; Hu Xiaodan; Yao Shouzhong

    2010-01-01

    In nuclear field, When the nuclear material shifting from the glove-box,use the technology of plastic welding package in accordance with tradition. There are some defects in this technology because of the plastic character, such as package pierced easily, wrapper not fitted storage for long term, etc. Because of this limit. Plastic shifting technology is only fit for shifting radwaste and nuclear material not need storage from radioactive close area to non-radioactive open area for long term.As the nuclear material exiting leak when shifting in plastic package,and the plastic material don't meet the need of storaging safely for long term.We research into a new technology of nuclear material shifting. When nuclear material is carried out from the glove box. It should be sealed by welding case, then it can be storaged safely for long term. At the same time, nuclear material wouldn't pollute the glove box outside.The study achieved well effect in apply. (authors)

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

    International Nuclear Information System (INIS)

    Smith, L.

    1996-01-01

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

  6. Safe transport of radioactive materials in Egypt

    International Nuclear Information System (INIS)

    El-Shinawy, R.M.K.

    1994-01-01

    In Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the International Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the gained experience. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the canal from 1963 and 1991 and their nationalities are also discussed. The protective measures are mentioned. A review of the present situation of the radioactive wastes storage facilities at the Atomic Energy site at Inshas is given along with the regulation for safe transportation and disposal of radioactive wastes. (Author)

  7. 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)

  8. The regulation concerning transportation of radioactive materials by vehicles

    International Nuclear Information System (INIS)

    1978-01-01

    The Regulation is established on the basis of The law for the regulations of nuclear source materials, nuclear fuel materials and reactors'' and the ''Law for the prevention of radiation injuries due to radioisotopes.'' The prescriptions cover the transport of radioactive materials by railway, street rail way, ropeway, trolley buses, motorcars and light vehicles. Terms are explained, such as nuclear fuel materials, radioisotopes, radioactive substances, transported radioactive things, transported fissile things, vehicles, containers, exclusive loading, surrounding inspection area. Four types of transported radioactive things are specified, L and A types being less dangerous and BM and BU being more dangerous. Transported fissile things are classified to three kinds according to the safety to criticality of such things. Transported radioactive things except those of L type and containers with transported fissile things shall not be loaded or unloaded at the places where persons other than those concerned come in usually. Loading and unloading of such things shall be carried out so that the safety of such things is not injured. The maximum dose rate of radiation of the containers with transported radioactive things shall not be more than 200 millirem per hour on the surface and 10 millirem per hour at the distance of 1 meter. Specified transported radioactive things shall be particularly marked by the letter of ''radioactive'' or other signs indicating as such. (Okada, K.)

  9. Safe transport of radioactive material. Second edition

    International Nuclear Information System (INIS)

    1991-01-01

    The transport of radioactive material embraces the carriage of radioisotopes for industrial, medical and research uses, and the movement of waste, in addition to consignments of nuclear fuel cycle material. It has been estimated that between eighteen and thirty-eight million package shipments take place each year. On the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), which enjoys wide representations from the Agency's Member States and international organizations, the Secretariat is preparing a training kit comprising this training manual and complementary visual aids. The kit is intended to be the basis for an extensive course on the subject and can be used in whole or in part for inter-regional, regional and even national training purposes. Member States can thus benefit from the material either through training courses sponsored by the Agency, or, alternatively, organized by themselves. As a step towards achieving that goal, the current training manual was compiled using material from the first Inter-Regional Training Course on the Safe Transport of Radioactive material that was held in co-operation with the Nuclear Power Training Centre of the then Central Electricity Generating Board at Bristol, United Kingdom. This Manual was initially published in 1990. On the recommendation of the Agency's Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), the Manual has since been expanded and updated in time for the second Inter-Regional Training Course, that will in 1991 similarly be held in Bristol. Refs, figs, tabs

  10. Illicit trafficking of radioactive material in Hungary

    International Nuclear Information System (INIS)

    Golder, I.

    1996-01-01

    Hungary, due to its geographical location is a convenient region for illegal transit of nuclear material between source and target countries. In recent years nine cases have became known and altogether 21.7 kg depleted, 4.6 kg natural, and 2.5 kg low enriched uranium have been confiscated. A brief summary is given of possible origin of the illicitly transported radioactive material. The most important elements of the security of sources including the national and accounting system of radioactive material and the intervention plans are discussed. (author)

  11. Method of processing radioactive materials

    International Nuclear Information System (INIS)

    Kondo, Susumu; Moriya, Tetsuo; Ishibashi, Tadashi; Kariya, Masahiro.

    1986-01-01

    Purpose: To improve contamination proofness, water proofness, close bondability and stretching performance of strippable paints coated to substrates liable to be contaminated with radioactive materials. Method: Strippable paints are previously coated on substrates which may possibly be contaminated with radioactive materials. After the contamination, the coated membranes are stripped and removed. Alternatively, the strippable paints may be coated on the already contaminated substrates and, after drying, the paints are stripped and removed. The strippable paints used herein have a composition comprising a styrene-butadiene block copolymer containing from 60 to 80 wt% of styrene as a main ingredient and from 0.3 to 5 % by weight of a higher alkyl amine compound having 12 to 18 carbon atoms blended with the copolymer. (Ikeda, J.)

  12. Instructions for safe transport of radioactive materials

    International Nuclear Information System (INIS)

    2005-01-01

    This entrance includes 5 chapters and tables and supplement. Chapter I contains the definitions and general provisions contained 5 materials. Chapter II contains radioactive materials packaging and permissible limits and it contains 8 materials. The provisions of Chapter III contains descriptions Missionaries. Chapter IV describes shipping instructions. As for the separation of V It contains Final provisions. The entrance contains number of tables speaks of the basic values of radioactive isotopes and radiation also limits activity and the requirements of industrial parcels and limits transactions to transport freight containers, as well as the International Classification of hazardous materials. This also includes entrance to the Supplement to some forms and Alohat

  13. Storage of radioactive material - accidents - precipitation - personnel monitoring

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-12-01

    This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

  14. The safety of radioactive materials transport; La surete des transports de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The rule of the radioactive materials transport contains two different objectives: the safety, or physical protection, consists in preventing the losses, the disappearances, the thefts and the diversions of the nuclear materials (useful materials for weapons); the high civil servant of defence near the Minister of Economy, Finance and Industry is the responsible authority; the safety consists in mastering the risks of irradiation, contamination and criticality presented by the radioactive and fissile materials transport, in order that man and environment do not undergo the nuisances. The control of the safety is within the competence of the Asn. (N.C.)

  15. Material for radioactive protection

    Science.gov (United States)

    Taylor, R.S.; Boyer, N.W.

    A boron containing burn resistant, low-level radiation protection material useful, for example, as a liner for radioactive waste disposal and storage, a component for neutron absorber, and a shield for a neutron source is described. The material is basically composed of borax in the range of 25 to 50%, coal tar in the range of 25 to 37.5%, with the remainder being an epoxy resin mix. A preferred composition is 50% borax, 25% coal tar and 25% epoxy resin. The material is not susceptible to burning and is about 1/5 the cost of existing radiation protection material utilized in similar applications.

  16. Import/export Service of Radioactive Material

    CERN Multimedia

    2004-01-01

    Please note that the Import/Export service of radioactive material (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Web site: http://cern.ch/service-rp-shipping/ Tel.: 73171 E-mail: service-rp-shipping@cern.ch Radioactive Sources Service Please note that the radioactive sources service (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Moreover, the service being reduced transports between Swiss and French sites (and vice versa) will now be achieved by internal transport. Web site : http://cern.ch/service-radioactive-sources/ Tel.: 73171 E-mail: service-rp-shipping@cern.ch

  17. Radioactive material transport

    International Nuclear Information System (INIS)

    White, M.C.

    1979-10-01

    All movements of radioactive materials in Canada are governed by a comprehensive body of regqlations, both national and international. These regulations are designed to maximize shielding to the public and transport workers, allow for heat dissipation, and to prevent criticality accidents, by prescribing specific packaging arrangements, administrative controls, labelling and storage measures. This report describes in some detail specific requirements and summarizes some incidents that occurred between 1974 and 1978

  18. Radioactive Material (Road Transport) Act 1991

    International Nuclear Information System (INIS)

    1991-01-01

    This Act came into force on 27 August 1991. It replaces earlier legislation dating from 1948 and enables the United Kingdom to give effect to the International Atomic Energy Agency's (IAEA) latest recommended Regulations for the Safe Transport of Radioactive Material. The new Act clarifies and extends the power of the Secretary of State to make regulations regarding, among other things, the design, labelling, handling, transport and delivery of packages containing radioactive material and the placarding of vehicles transporting such packages. The Act gives the Secretary of State the power to appoint inspectors to assist him in enforcing the regulations. (NEA)

  19. Microwave processing of radioactive materials-I

    International Nuclear Information System (INIS)

    White, T.L.; Berry, J.B.

    1989-01-01

    This paper is the first of two papers that reviews the major past and present applications of microwave energy for processing radioactive materials, with particular emphasis on processing radioactive wastes. Microwave heating occurs through the internal friction produced inside a dielectric material when its molecules vibrate in response to an oscillating microwave field. For this presentation, we shall focus on the two FCC-approved microwave frequencies for industrial, scientific, and medical use, 915 and 2450 MHz. Also, because of space limitations, we shall postpone addressing plasma processing of hazardous wastes using microwave energy until a later date. 13 refs., 4 figs

  20. Information from the Import/Export of radioactive material Service

    CERN Multimedia

    DGS Unit

    2010-01-01

    The radiation protection group reminds you that the import/export of all radioactive material must be declared in advance. In the case of exports, an EDH shipping request form must be completed, ticking the box “radioactive material”. In the case of imports, an electronic form must be completed before the material arrives on the CERN site. Any requests which do not comply with the above procedure will be refused. The import of any radioactive material that has not been declared in advance will be systematically refused. For further information, please consult the web site: http://cern.ch/service-rp-shipping Yann Donjoux / Radioactive Shipping Service Tél: +41 22 767.31.71 Fax: +41 22 766.92.00

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

    International Nuclear Information System (INIS)

    Hovingh, J.

    1991-01-01

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

  2. Determination of detailed standards for transportation of radioactive materials by ships

    International Nuclear Information System (INIS)

    1978-01-01

    These provisions are established on the basis of the ''Regulations on the transport and storage of dangerous things by ships''. The terms used hereinafter are according to those used in the Regulations. Radioactive materials, etc., include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, the compounds of such materials and the substances containing one or two and more of such materials, excluding such materials of not more than 15 grams. The permissible surface density of radioactive materials is 1/100,000 of one microcurie per cm 2 for the radioactive materials emitting alpha-ray and 1/10,000 of one microcurie per cm 2 for the radioactive materials not emitting alpha-ray. For the radioactive materials which can be transported as L type cargo, their quantity of radioactivity is defined in their solid, liquid and gaseous forms. The limit of quantity of such cargo is described in detail in the lists attached. Transporting conditions of A, BM and BU type cargos are specified respectively in the particular sections. (Okada, K.)

  3. Transport of radioactive materials

    International Nuclear Information System (INIS)

    Lenail, B.

    1984-01-01

    Transport of radioactive materials is dependent of transport regulations. In practice integrated doses for personnel during transport are very low but are more important during loading or unloading a facility (reactor, plant, laboratory, ...). Risks occur also if packagings are used outside specifications. Recommendations to avoid these risks are given [fr

  4. Radiological impact of radioactive materials transport in France

    International Nuclear Information System (INIS)

    Hamard, J.

    1987-01-01

    Radiation doses of personnel and populations are estimated between 1983 and 1985 during road transport of radiopharmaceuticals, spent fuels, wastes and other radioactive materials. Dose equivalent received by air transport and others are difficult to know. Results are summed up in 8 tables. Radioactive materials transport represents less than 1% of exposures related to the fuel cycle [fr

  5. Natural radioactivity for some Egyptian building material

    International Nuclear Information System (INIS)

    Eissa, M. F.; Mostafa, R. M.; Shahin, F.; Hassan, K. F.; Saleh, Z. A.; Yahia, A.

    2007-01-01

    Study of the radiation hazards for the building materials is interested in most international countries. Measurements of natural radioactivity was verified for some egyptian building materials to assess any possible radiological hazard to man by the use of such materials. The measurements for the level of natural radioactivity in the materials was determined by γ-ray spectrum using HP Ge detector. A track detector Cr-39 was used to measure the radon exhalation rate from these materials. The radon exhalation rates were found to vary from 2.83±0.86 to 41.57 ± 8.38 mBqm -2 h -1 for egyptian alabaster. The absorbed dose rate in air is lower than the international recommended value (55 n Gy h -1 ) for all test samples

  6. Licensing of radioactive materials and facilities in the Philippines

    International Nuclear Information System (INIS)

    Mateo, A.J.

    1976-12-01

    The importation, acquisition, possession, use, sale and/ or transfer of radioactive materials need to be regulated and controlled in order to safeguard the importer, possessor, user or seller and the general public as well. The Philippine Atomic Energy Commission pursuant to Republic Act No. 2067, as amended and Republic Act No. 5207, has been charged by the government to control, regulate and license all the radioactive materials and facilities in the Philippines. Licensing and control is accomplished through a system of rules and regulations applicable to all importers, possessors, users or sellers of radioactive materials

  7. 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

  8. Ontario hydro radioactive material transportation field guide

    International Nuclear Information System (INIS)

    Howe, W.

    1987-01-01

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

  9. HMPT: Basic Radioactive Material Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Hypes, Philip A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-02-29

    Hazardous Materials and Packaging and Transportation (HMPT): Basic Radioactive Material Transportation Live (#30462, suggested one time) and Test (#30463, required initially and every 36 months) address the Department of Transportation’s (DOT’s) function-specific [required for hazardous material (HAZMAT) handlers, packagers, and shippers] training requirements of the HMPT Los Alamos National Laboratory (LANL) Labwide training. This course meets the requirements of 49 CFR 172, Subpart H, Section 172.704(a)(ii), Function-Specific Training.

  10. Management of radioactive wastes produced by users of radioactive materials

    International Nuclear Information System (INIS)

    1985-01-01

    This report is intended as a document to provide guidance for regulatory, administrative and technical authorities who are responsible for, or are involved in, planning, approving, executing and reviewing national waste management programmes related to the safe use of radioactive materials in hospitals, research laboratories, industrial and agricultural premises and the subsequent disposal of the radioactive wastes produced. It provides information and guidance for waste management including treatment techniques that may be available to establishments and individual users

  11. Advisory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 3. ed.

    International Nuclear Information System (INIS)

    1990-01-01

    The IAEA Regulations for the Safe Transport of Radioactive Material provide standards for ensuring a high level of safety of people, property and the environment against radiation and criticality hazards as well as thermal effects associated with the transport of radioactive material. The basic requirements to be met are: Effective containment of radioactive material; Effective control of radiation emitted from the package; A subcritical condition for any fissile material; and Adequate dissipation of any heat generated within the package. Effective quality assurance and compliance assurance programmes are required, for example: (a) Appropriate and sound packages are used; (b) The activity of radioactive material in each package does not exceed the regulatory activity limit for that material and that package type; (c) The radiation levels external to, and the contamination levels on, surfaces of packages do not exceed the appropriate limits; (d) Packages are properly marked and labelled and transport documents are completed; (e) the number of packages containing radioactive material in a conveyance is within the regulatory limits; (f) Packages of radioactive material are stowed in conveyances and are stored at a safe distance from persons and photosensitive materials; (g) Only those transport and lifting devices which have been tested are used in loading, conveying and unloading packages of radioactive material; and (h) Packages of radioactive material are properly secured for transport. The control of the transport of radioactive materials may be necessary also for other reasons, e.g. safeguards control and physical protection of nuclear materials and control of a property. For radioactive materials having other dangerous properties, the regulations of Member States, modal conventions and agreements, and other relevant documents of international organizations need to be applied. A Member State may require in its national regulations that an additional approval be

  12. 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)

  13. Data about shipping of radioactive material for medical use

    International Nuclear Information System (INIS)

    Sanches, M.P.; Rodrigues, D.L.

    2006-01-01

    The transport of radioactive materials implies a risk for the personnel of the team, those members of the public and the environment. While the safety in the transports is based on the designs of the bulks, the programs of radiological protection are important to assure the radiological control to the workers, the public and the environment during the transport of these materials. Although the biggest interest in the transport of radioactive materials it spreads to be centered in the nuclear industry, the transport in great measure it happens for the materials of medical use. These are mainly transported in bulks of the A Type and excepted bulks. The transport ones are forced, by national regulations, to send to the competent authority, in our case the National Comissao of Nuclear Energy (CNEN), all the data of the transported materials. This work has by objective to aim the efforts made to settle down and to manage the data regarding the transported radioactive materials. The existent data in the Radiopharmaceuticals Center, of the Institute of Energy and Nuclear Investigations 'IPEN/CNEN' it contains the information on all the radioactive materials consigned for the transport during every year. A statistic of the number of deliveries of the radioactive material for the period from 2001 to 2005 is provided. Based on this statistic its are presented the number of bulks, the quantity of activity and the ways of the transport for the period in study. (Author)

  14. Transport of radioactive material in Canada

    International Nuclear Information System (INIS)

    1997-09-01

    In this report, the Advisory Committee on Nuclear Safety (ACNS) presents the results of its study on how the system of the transport of radioactive material (TRM) in Canada is regulated, how it operates, and how it performs. The report deals with the transport of packages, including Type B packages which are used to carry large quantities of radioactive material, but not with the transport of spent nuclear fuel or with the transport of low-level historical waste. The ACNS has examined the Canadian experience in the TRM area, the regulatory framework in Canada with respect to the TRM some relevant aspects of training workers and monitoring compliance with regulatory requirements, the state of the emergency preparedness of organizations involved in the TRM and the process of updating present regulations by the Atomic Energy Control Board (AECB). As a result of this study, the ACNS concludes that the current Canadian regulatory system in the TRM is sound and that the TRM is, for the most part, conducted safely. However, improvements can be made in a number of areas, such as: determining the exposures of workers who transport radioactive material; rewording the proposed Transport Regulations in plain language; training all appropriate personnel regarding the AECB and Transport Canada (TC) Regulations; enforcing compliance with the regulations; and increasing the level of cooperation between the federal agencies and provincial authorities involved in the inspection and emergency preparedness aspects of the TRM. It is also noted that Bill C-23, the Nuclear Safety and Control Act, imposes a new requirement, subject to the Regulations, for a licence for a carrier to transport some types of radioactive material

  15. Transport of radioactive material in Canada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    In this report, the Advisory Committee on Nuclear Safety (ACNS) presents the results of its study on how the system of the transport of radioactive material (TRM) in Canada is regulated, how it operates, and how it performs. The report deals with the transport of packages, including Type B packages which are used to carry large quantities of radioactive material, but not with the transport of spent nuclear fuel or with the transport of low-level historical waste. The ACNS has examined the Canadian experience in the TRM area, the regulatory framework in Canada with respect to the TRM some relevant aspects of training workers and monitoring compliance with regulatory requirements, the state of the emergency preparedness of organizations involved in the TRM and the process of updating present regulations by the Atomic Energy Control Board (AECB). As a result of this study, the ACNS concludes that the current Canadian regulatory system in the TRM is sound and that the TRM is, for the most part, conducted safely. However, improvements can be made in a number of areas, such as: determining the exposures of workers who transport radioactive material; rewording the proposed Transport Regulations in plain language; training all appropriate personnel regarding the AECB and Transport Canada (TC) Regulations; enforcing compliance with the regulations; and increasing the level of cooperation between the federal agencies and provincial authorities involved in the inspection and emergency preparedness aspects of the TRM. It is also noted that Bill C-23, the Nuclear Safety and Control Act, imposes a new requirement, subject to the Regulations, for a licence for a carrier to transport some types of radioactive material.

  16. Development of solid water-equivalent radioactive certified reference materials

    International Nuclear Information System (INIS)

    Finke, E.; Greupner, H.; Groche, K.; Rittwag, R.; Geske, G.

    1991-01-01

    This paper presents a brief description of the development of solid water-equivalent beta volume radioactive certified reference materials. These certified reference materials were prepared for the beta fission nuclides 90 Sr/ 90 Y, 137 Cs, 147 Pm and 204 Tl. Comparative measurements of liquid and solid water-equivalent beta volume radioactive certified reference materials are discussed. (author)

  17. Radioactive materials and emergencies at sea

    International Nuclear Information System (INIS)

    Shaw, K.B.

    1988-01-01

    Recent events have heightened awareness of the problems raised by accidents at sea involving radioactive materials. The NEA Committee on Radiation Protection and Public Health (CRPPH) noted that, while the transport of radioactive materials at sea is governed by extensive international regulations, deficiencies remained, particularly concerning mechanisms for early accident reporting and the development of generic safety assessments and accident analysises for various kinds of sea transport. As a contribution towards improving international guidance in this field, the NEA appointed a consultant to review the current status of activities carried out by the principal international organizations concerned with the transport of radioactive materials (the IAEA, IMO and the CEC), to identify the various areas where additional work is required and to suggest appropriate improvements. Only the radiation protection aspects of sea transport have been considered here. After having examined the consultant report, the CRPPH felt that its wide distribution to national regulatory authorities in OECD countries would serve a useful purpose. The report is published under the responsibility of the Secretary-General of the OECD and does not commit Member Governments or the Organization

  18. Transport of radioactive materials

    International Nuclear Information System (INIS)

    Huck, W.

    1992-01-01

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

  19. Determination of detailed regulations concerning transportation of radioactive materials by vehicles

    International Nuclear Information System (INIS)

    1978-01-01

    These provisions are established on the basis of the ''Regulations concerning transportation of radioactive materials by vehicles''. The terms used hereinafter are according to those used in the Regulations. Radioactive materials include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, the compounds of such materials and the substances containing one or two and more of such materials, excluding the radioactive materials with not more than 15 grams of such uranium and plutonium. The permissible surface density is 1/100,000 microcurie per cm 2 for radioactive materials emitting alpha-ray and 1/10,000 microcurie per cm 2 for such materials which does not emit alpha-ray. For the radioactive materials which can be transported as L type loads, their kinds and quantities are specified in the forms of solid, liquid and gas, respectively. Transporting conditions including the quantity and leakage in A, BM and BU type loads are provided for, respectively, in the lists attached and in the particular sections. (Okada, K.)

  20. Measures Against-Illicit Trafficking of Nuclear Materials and Other Radioactive Sources

    International Nuclear Information System (INIS)

    Barakat, M.B.; Nassef, M.H.; El Mongy, S.A.

    2008-01-01

    Since the early nineties, illicit trafficking (IT) of nuclear materials and radioactive sources appeared as a new trend which raised the concern of the international community due to the grave consequences that would merge if these materials or radioactive sources fell into the hands of terrorist groups. However, by the end of the last century illicit trafficking of nuclear materials and radioactive sources lost its considerable salience, in spite of seizure of considerable amounts of 2 '3'5U (76% enrichment) in Bulgaria (May 1999) and also 235 U (30% enrichment) in Georgia (April 2000). Nevertheless, IT should be always considered as a continued and viable threat to the international community. Awareness of the problem should be developed and maintained among concerned circles as the first step towards combating illicit trafficking of nuclear materials and radioactive sources. Illicit trafficking of nuclear and radioactive materials needs serious consideration and proper attention by the governmental law enforcement authorities. Measures to combat with IT of nuclear material or radioactive sources should be effective in recovery, of stolen, removed or lost nuclear materials or radioactive sources due to the failure of the physical protection system or the State System Accounting and Control (SSAC) system which are normally applied for protecting these materials against illegal actions. Measures such as use of modern and efficient radiation monitoring equipment at the borders inspection points, is an important step in preventing the illicit trafficking of nuclear and radioactive materials across the borders. Also providing radiological training to specific personnel and workers in this field will minimize the consequences of a radiological attack in case of its occurrence. There is a real need to start to enter into cooperative agreements to strengthen borders security under the umbrella of IAEA to faster as an international cooperation in the illicit trafficking

  1. Statistics of foreign trade in radioactive materials 2004

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    The German Federal Office for Industry and Foreign Trade Control (BAFA) keeps annual statistics of the imports and exports of radioactive materials, nuclear fuels included. The entries, some of them with precise details, cover the participating countries and the radionuclides concerned as well as all kinds of radioactive materials. The tables listed in the article represent the overall balance of the development of imports and exports of radioactive materials for the years 1986 to 2004 arranged by activity levels, including the development of nuclear fuel imports and exports. For the year 2004, an additional trade balance for irradiated and unirradiated nuclear fuels and source materials differentiated by enrichment is presented for the countries involved. In 2004, some 2,558 t of nuclear fuels and source materials were imported into the Federal Republic, while approx. 1,971 t were exported. The chief trading partners are countries of the European Union, Canada, Russia and the USA. (orig.)

  2. Statistics of foreign trade in radioactive materials 2002

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    The German Federal Office for Industry and Foreign Trade Control (BAFA) keeps annual statistics of the imports and exports of radioactive materials, nuclear fuels included. The entries, some of them with precise details, cover the participating countries and the radionuclides concerned as well as all kinds of radioactive materials. The tables listed in the article represent the overall balance of the development of imports and exports of radioactive materials for the years 1983 to 2002 arranged by activity levels, including the development of nuclear fuel imports and exports. For the year 2002, an additional trade balance for irradiated and unirradiated nuclear fuels and source materials differentiated by enrichment is presented for the countries involved. In 2002, some 3 070 t of nuclear fuels and source materials were imported into the Federal Republic, while approx. 3 052 t were exported. The chief trading partners are countries of the European Union, Russia, and the USA. (orig.)

  3. Dispersion of radioactive materials in air and water

    International Nuclear Information System (INIS)

    Tolksdorf, P.; Meurin, G.

    1976-01-01

    A review of current analytical methods for treating the dispersion of radioactive material in air and water is given. It is shown that suitable calculational models, based on experiments, exist for the dispersion in air. By contrast, the analysis of the dispersion of radioactive material in water still depends on the evaluation of experiments with site-specific models. (orig.) [de

  4. Computerized simulation of the mechanical behavior of wood-filled shock absorbers of radioactive materials transport casks; Rechnerische Simulation des mechanischen Verhaltens von holzgefuellten Stossdaempfern von Transportbehaeltern fuer radioaktive Stoffe

    Energy Technology Data Exchange (ETDEWEB)

    Neumann, Martin; Wille, Frank [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany)

    2011-07-01

    In Germany the mechanical component inspection of transport containers for radioactive materials is performed by BAM (Bundesanstalt fuer Materialforschung und -pruefung) under consideration of national and international standards and guidelines. Experimental and calculative (analytical and numerical) techniques combined with material and/or component testing are the basis of assessment concepts according the state of the art. The authors describe the experiences of BAM concerning assessment and description of the mechanical behavior of shock absorbing components, including modeling strategies, material models, drop tests and experiment-calculation comparison. Energy absorbing components are used to reduce the impact forces at the container in case of a transport accident. In Germany wood filled thin-walled constructions are used. The deformation behavior of the wood is a main part of the calculative simulation procedures in comparison with experimental tests.

  5. Radioactive materials transporting container and vehicles

    International Nuclear Information System (INIS)

    Reese, S.L.

    1980-01-01

    A container and vehicle therefor for transporting radioactive materials is provided. The container utilizes a removable system of heat conducting fins made of a light weight highly heat conductive metal, such as aluminum or aluminum alloys. This permits a substantial reduction in the weight of the container during transport, increases the heat dissipation capability of the container and substantially reduces the scrubbing operation after loading and before unloading the radioactive material from the container. The vehicle utilizes only a pair of horizontal side beams interconnecting a pair of yoke members to support the container and provide the necessary strength and safety with a minimum of weight

  6. Mesoscale meteorological model based on radioactive explosion cloud simulation

    International Nuclear Information System (INIS)

    Zheng Yi; Zhang Yan; Ying Chuntong

    2008-01-01

    In order to simulate nuclear explosion and dirty bomb radioactive cloud movement and concentration distribution, mesoscale meteorological model RAMS was used. Particles-size, size-active distribution and gravitational fallout in the cloud were considered. The results show that the model can simulate the 'mushroom' clouds of explosion. Three-dimension fluid field and radioactive concentration field were received. (authors)

  7. Regulations of safe transport of radioactive material

    International Nuclear Information System (INIS)

    Patel, R.J.; Sumathi, E.

    2017-01-01

    BARC is a multi-disciplinary nuclear research organisation with facilities located at various parts of the country. The nuclear and radiological facilities in BARC include fuel fabrication facilities, nuclear research reactors, radiological laboratories, nuclear recycle facilities, waste management facilities and other associated facilities. RAdioactive Material (RAM) such as fresh nuclear fuel, irradiated fuel, radioactive sources, vitrified high level wastes, special nuclear material etc., are transported between these facilities either within the controlled premises or in public domain. In BARC the regulatory approval for the packages used for transport of RAM is issued by BARC Safety Council (BSC). Competent Authority for issuing the design approval for the BARC packages in public domain is Director, BARC. In this aspect BSC is assisted by Safety Review Committee-Transport of Radioactive Material (SRC-TRM) constituted by BSC entrusted with the mandate to ensure the packages are designed, manufactured and transported in accordance with the current regulations. This article summarizes the regulatory requirements for transport of RAM and experience in BARC facilities

  8. 2009 National inventory of radioactive material and wastes. Synthesis report

    International Nuclear Information System (INIS)

    2009-01-01

    Third edition of the ANDRA's national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). After a brief historical review of the national inventory and the way it is constructed, the report gives the basics on radioactive wastes, their classification, origins and management processes, followed by a general presentation and discussion of the inventory results (radioactive wastes and materials). Results are then detailed for the different activity sectors using radioactive materials (nuclear industry, medical domain, scientific research, conventional industry, Defense...). Information is also given concerning radioactive polluted areas (characterization and site management) and radioactive waste inventories in various foreign countries

  9. Technical regulations for road transport of radioactive materials

    International Nuclear Information System (INIS)

    Juul-Jensen, P.; Ulbak, K.

    1990-01-01

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

  10. Development of solid water-equivalent radioactive certified reference materials

    Energy Technology Data Exchange (ETDEWEB)

    Finke, E.; Greupner, H.; Groche, K.; Rittwag, R. (Office for Standardization, Metrology and Quality Control (ASMW), Berlin (Germany, F.R.)); Geske, G. (Jena Univ. (Germany, F.R.))

    1991-01-01

    This paper presents a brief description of the development of solid water-equivalent beta volume radioactive certified reference materials. These certified reference materials were prepared for the beta fission nuclides {sup 90}Sr/{sup 90}Y, {sup 137}Cs, {sup 147}Pm and {sup 204}Tl. Comparative measurements of liquid and solid water-equivalent beta volume radioactive certified reference materials are discussed. (author).

  11. Actions of radiation protection in the collection of discarded radioactive material

    International Nuclear Information System (INIS)

    Neri, E.P.M.; Silva, F.C.A. da

    2017-01-01

    Brazil has approximately 2000 radiative facilities that use radiation sources in their processes and are controlled by The Brazilian Nuclear Energy Commission - CNEN through standards, authorizations and inspections. These radioactive materials, whether in the form of waste or radioactive source, used in medical, industrial, research, etc. are sometimes discarded and found in inappropriate places, such as garbage dumps, industrial waste, streets, squares, etc. found by urban cleaning professionals without the proper knowledge of them. The work presents the radiation protection actions required for the safe collection of radioactive material to be performed by these professionals. According to the type of radioactive material the main actions of radiation protection are, among others: recognition of a radioactive material; correct use of personal protective equipment to contain possible radiation contamination; implementation of an area control etc. In order for the actions of recognition and collection of discarded radioactive material to be effective, there is a need to implement a training program in radiation protection for urban cleaning professionals

  12. Simulation of the dispersion of radioactive substances, for the case of Chernobyl as an example

    International Nuclear Information System (INIS)

    Memmesheimer, M.; Hass, H.; Jakobs, H.J.; Geiss, H.; Laube, M.

    1989-01-01

    On April 25, 1989, an accident with the so far most serious consequences occurred in the nuclear power plant at Chernobyl. As a result during the period April 25 to May 6, 1986, about 4% of the core inventory of radionuclides was released. The large scale atmospheric circulation dispersed the emitted radioactive material during and after this period over the complete northern hemisphere whereby the European area was affected in particular. The distribution and deposition of the radioactive air admixtures in the European region provides an interesting possibility to test the EURAD model. The transport and deposition of the radioactive material can then, within the frame of the model, be treated as a dispersal problem with consideration of the deposition processes. Simulating the reactor accident provides the possibility to test the role of emission heights of point sources. The calculations accomplished so far indicate among others that a determination as exact as possible of the meteorologic fields is decisive. Improvements appear to be possible with a nudging version of MM4, with which presently first simulation tests for the Chernobyl case are conducted. (orig./KW) [de

  13. State summary of radioactive material transport sector in Brazil

    International Nuclear Information System (INIS)

    Heilbron Filho, P.F.L.; Xavier, A.M.

    1991-07-01

    The main aim of this work is the scientific cooperation with the CNEA (Argentina) in the area of safe transport of radioactive materials, intending to find solutions to some rural problems and, also, to standardize the transport of radioactive materials between Brazil and Argentina. (E.O.)

  14. 44 years of testing radioactive materials packages at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Shappert, L.B.; Ludwig, S.B. [Oak Ridge National Lab., Oak Ridge, TN (United States)

    2004-07-01

    This paper briefly reviews the package testing at the Oak Ridge National Laboratory (ORNL) since 1960 and then examines the trends in the testing activities that occurred during the same period. Radioactive material shipments have been made from ORNL since the 1940s. The first fully operating reactor built at the ORNL site was patterned after the graphite pile constructed by Enrico Fermi under Stagg Field in Chicago. After serving as a test bed for future reactors, it became useful as a producer of radioactive isotopes. The Isotopes Division was established at ORNL to furnish radioactive materials used in the medical community. Often these shipments have been transported by aircraft worldwide due to the short half-lives of many of the materials. This paper touches briefly on the lighter and smaller radioisotope packages that were being shipped from ORNL in large numbers and then deals with the testing of packages designed to handle large radioactive sources, such as spent fuel, and other fissile materials.

  15. 44 years of testing radioactive materials packages at ORNL

    International Nuclear Information System (INIS)

    Shappert, L.B.; Ludwig, S.B.

    2004-01-01

    This paper briefly reviews the package testing at the Oak Ridge National Laboratory (ORNL) since 1960 and then examines the trends in the testing activities that occurred during the same period. Radioactive material shipments have been made from ORNL since the 1940s. The first fully operating reactor built at the ORNL site was patterned after the graphite pile constructed by Enrico Fermi under Stagg Field in Chicago. After serving as a test bed for future reactors, it became useful as a producer of radioactive isotopes. The Isotopes Division was established at ORNL to furnish radioactive materials used in the medical community. Often these shipments have been transported by aircraft worldwide due to the short half-lives of many of the materials. This paper touches briefly on the lighter and smaller radioisotope packages that were being shipped from ORNL in large numbers and then deals with the testing of packages designed to handle large radioactive sources, such as spent fuel, and other fissile materials

  16. Benchmark studies of induced radioactivity and remanent dose rates produced in LHC materials

    International Nuclear Information System (INIS)

    Brugger, M.; Mayer, S.; Roesler, S.; Ulrici, L.; Khater, H.; Prinz, A.; Vincke, H.

    2005-01-01

    Samples of materials that will be used for elements of the LHC machine as well as for shielding and construction components were irradiated in the stray radiation field of the CERN-EU high-energy Reference Field facility. The materials included various types of steel, copper, titanium, concrete and marble as well as light materials such as carbon composites and boron nitride. Emphasis was put on an accurate recording of the irradiation conditions, such as irradiation profile and intensity, and on a detailed determination of the elemental composition of the samples. After the irradiation, the specific activity induced in the samples as well as the remanent dose rate were measured at different cooling times ranging from about 20 minutes to two months. Furthermore, the irradiation experiment was simulated using the FLUKA Monte Carlo code and specific activities. In addition, dose rates were calculated. The latter was based on a new method simulating the production of various isotopes and the electromagnetic cascade induced by radioactive decay at a certain cooling time. In general, solid agreement was found, which engenders confidence in the predictive power of the applied codes and tools for the estimation of the radioactive nuclide inventory of the LHC machine as well as the calculation of remanent doses to personnel during interventions. (authors)

  17. 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

  18. Risk associated with the transport of radioactive materials in the fuel cycle

    International Nuclear Information System (INIS)

    Lange, F.; Mairs, J.; Niel, C.

    1997-01-01

    This paper sets out the regulatory framework within which nuclear fuel cycle materials are transported. It establishes the basic principles of those safety regulations and explains the graded approach to satisfying those requirements depending on the hazard of the radioactive contents. The paper outlines the minimum performance standards required by the Regulations. It covers the performance standards for Type C packages in a little more detail because these are new to the 1996 Edition of the IAEA's Regulations for the Safe Transport of Radioactive Material and are less well reported elsewhere at present. The paper then gives approximate data on the number of shipments of radioactive materials that service the nuclear fuel cycles in France, Germany and the UK. The quantities are expressed as average annual quantities per GW el installed capacity. There is also a short discussion of the general performance standards required of Type B packages in comparison with tests that have simulated specific accident conditions involving particular packages. There follows a discussion on the probability of packages experiencing accident conditions that are comparable with the tests that Type B packages are required to withstand. Finally there is a summary of the implementation of the Regulations for sea and air transport and a description of ongoing work that may have a bearing on the future development of mode related Regulations. Nuclear fuel cycle materials are transported in accordance with strict and internationally agreed safety regulations which are the result of a permanent and progressive process based on social concern and on the advancement of knowledge provided by research and development. Transport operations take place in the public domain and some become high profile events in the management of these materials, attracting a lot of public, political and media attention. The risks associated with the transport of radioactive materials are low and it is important

  19. Simulation of decay processes and radiation transport times in radioactivity measurements

    Energy Technology Data Exchange (ETDEWEB)

    García-Toraño, E., E-mail: e.garciatorano@ciemat.es [Laboratorio de Metrología de Radiaciones Ionizantes, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain); Peyres, V. [Laboratorio de Metrología de Radiaciones Ionizantes, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain); Bé, M.-M.; Dulieu, C.; Lépy, M.-C. [CEA, LIST, Laboratoire National Henri Becquerel (LNE-LNHB), Bldg 602, PC111, 91191 Gif-sur-Yvette Cedex (France); Salvat, F. [Facultat de Física (FQA and ICC), Universitat de Barcelona, Diagonal 647, 08028 Barcelona (Spain)

    2017-04-01

    The Fortran subroutine package PENNUC, which simulates random decay pathways of radioactive nuclides, is described. The decay scheme of the active nuclide is obtained from the NUCLEIDE database, whose web application has been complemented with the option of exporting nuclear decay data (possible nuclear transitions, branching ratios, type and energy of emitted particles) in a format that is readable by the simulation subroutines. In the case of beta emitters, the initial energy of the electron or positron is sampled from the theoretical Fermi spectrum. De-excitation of the atomic electron cloud following electron capture and internal conversion is described using transition probabilities from the LLNL Evaluated Atomic Data Library and empirical or calculated energies of released X rays and Auger electrons. The time evolution of radiation showers is determined by considering the lifetimes of nuclear and atomic levels, as well as radiation propagation times. Although PENNUC is designed to operate independently, here it is used in conjunction with the electron-photon transport code PENELOPE, and both together allow the simulation of experiments with radioactive sources in complex material structures consisting of homogeneous bodies limited by quadric surfaces. The reliability of these simulation tools is demonstrated through comparisons of simulated and measured energy spectra from radionuclides with complex multi-gamma spectra, nuclides with metastable levels in their decay pathways, nuclides with two daughters, and beta plus emitters.

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  1. 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.)

  2. Applications of inorganic ion-exchange materials in managing radioactivity wastewater

    International Nuclear Information System (INIS)

    He Jiaheng; Li Xingliang; Li Shoujian

    2007-01-01

    This article introduces the application of abio-ion exchange materials in managing radioactivity wastewater, which would be useful for latter research of new inorganic materials that used in managing radioactivity wastewater. (authors)

  3. Radioactive waste solidification material

    International Nuclear Information System (INIS)

    Nishihara, Yukio; Wakuta, Kuniharu; Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

    1992-01-01

    The present invention concerns a radioactive waste solidification material containing vermiculite cement used for a vacuum packing type waste processing device, which contains no residue of calcium hydroxide in cement solidification products. No residue of calcium hydroxide means, for example, that peak of Ca(OH) 2 is not recognized in an X ray diffraction device. With such procedures, since calcium sulfoaluminate clinker and Portland cement themselves exhibit water hardening property, and slugs exhibit hydration activity from the early stage, the cement exhibits quick-hardening property, has great extension of long term strength, further, has no shrinking property, less dry- shrinkage, excellent durability, less causing damages such as cracks and peeling as processing products of radioactive wastes, enabling to attain highly safe solidification product. (T.M.)

  4. Method of electrolytic decontamination of contaminated metal materials for radioactivity

    International Nuclear Information System (INIS)

    Harada, Yoshio; Ishibashi, Masaru; Matsumoto, Hiroyo.

    1985-01-01

    Purpose: To electrolytically eliminate radioactive materials from metal materials contaminated with radioactive materials, as well as efficiently remove metal ions leached out in an electrolyte. Method: In the case of anodic dissolution of metal materials contaminated with radioactivity in an electrolyte to eliminate radioactive contaminating materials on the surface of the metal materials, a portion of an electrolytic cell is defined with partition membranes capable of permeating metal ions therethrough. A cathode connected to a different power source is disposed to the inside of the partition membranes and fine particle of metals are suspended and floated in the electrolyte. By supplying an electric current between an insoluble anode disposed outside of the partition membranes and the cathode, metal ions permeating from the outside of the partition membranes are deposited on the fine metal particles. Accordingly, since metal ions in the electrolyte are removed, the electrolyte can always be kept clean. (Yoshihara, H.)

  5. Development and implementation of automated radioactive materials handling systems

    International Nuclear Information System (INIS)

    Jacoboski, D.L.

    1992-12-01

    Material handling of radioactive and hazardous materials has forced the need to pursue remotely operated and robotic systems in light of operational safety concerns. Manual maneuvering, repackaging, overpacking and inspecting of containers which store radioactive and hazardous materials is the present mode of operation at the Department of Energy (DOE) Fernald Environmental Management Project (FEMP) in Fernald Ohio. The manual methods are unacceptable in the eyes of concerned site workers and influential community oversight committees. As an example to respond to the FEMP material handling needs, design efforts have been initiated to provide a remotely operated system to repackage thousands of degradated drums containing radioactive Thorium: Later, the repackaged Thorium will be shipped offsite to a predesignated repository again requiring remote operation

  6. Development of supporting system for emergency response to maritime transport accidents involving radioactive material

    International Nuclear Information System (INIS)

    Odano, N.; Matsuoka, T.; Suzuki, H.

    2004-01-01

    National Maritime Research Institute has developed a supporting system for emergency response of competent authority to maritime transport accidents involving radioactive material. The supporting system for emergency response has functions of radiation shielding calculation, marine diffusion simulation, air diffusion simulation and radiological impact evaluation to grasp potential hazard of radiation. Loss of shielding performance accident and loss of sealing ability accident were postulated and impact of the accidents was evaluated based on the postulated accident scenario. Procedures for responding to emergency were examined by the present simulation results

  7. Evaluation on construction quality of pit filler material of cavern type radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Takechi, Shin-ichi; Yokozeki, Kosuke; Shimbo, Hiroshi; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

    2014-01-01

    The pit filler material of the underground cavern-type radioactive waste disposal facility, which is poured directly around the radioactive waste packages where high temperature environment is assumed by their decay heat, is concerned to be adversely affected on the filling behavior and its hardened properties. There also are specific issues that required quality of construction must be achieved by unmanned construction with remote operation, because the pit filler construction shall be done under radiation environment. In this paper, the mix proportion of filler material is deliberated with filling experiments simulating high temperature environment, and also the effect of temperature on hardened properties are confirmed with high temperature curing test. Subsequently, the feasibility of unmanned construction method of filler material by pumping, and by movable bucket, are comparatively discussed through a real size demonstration. (author)

  8. Nuclide-related exemption limits for radioactive materials

    International Nuclear Information System (INIS)

    Przyborowski, S.; Scheler, R.

    1984-01-01

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

  9. Considerations concerning the secure transport of radioactive materials in Romania

    International Nuclear Information System (INIS)

    Vieru, Gheorghe

    2002-01-01

    As UNO member and founding member of the IAEA, Romania has implemented national regulations concerning the transport of radioactive materials in complete safety, complying with recommendations by IAEA and other international organizations. Accordingly, the National Commission for Nuclear Activities Control, CNCAN, issued the Directive no. 374/October 2001 which provides the rules for secure radioactive material transport in Romania on roads, rail ways, sea/fluvial and air ways. The paper presents the main sources of producing radioactive materials focussing the following: mining of natural uranium ore, nuclear fuel fabrication plants, nuclear power plants operation, nuclear research reactors, industrial use of radioactive sources (as gamma radiography), use of radioisotope in scientific, educational or medical units. The paper pays attention to the special routes and containers adopted for most secure transport of radioactive waste. Finally, one presents specific issues relating to identification and evaluation of the risk factors occurring at the transport of radioactive waste, as well as the potential radiological consequences upon population and environment. Estimated are the collective risk doses for different categories of populations from areas adjacent to the routes of radioactive materials transportation. It is stressed that the annual collective dose which the population is exposed to in case of accident is comparable with the dose from the natural (cosmic radiation background)

  10. Meeting the regulatory information needs of users of radioactive materials

    International Nuclear Information System (INIS)

    MacDurmon, G.W.

    1996-01-01

    The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff

  11. Meeting the regulatory information needs of users of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    MacDurmon, G.W. [American Cyanamid Company, Princeton, NJ (United States)

    1996-10-01

    The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff.

  12. The Safe Transportation of Radioactive Materials

    International Nuclear Information System (INIS)

    Megrahi, Abdulhafeed; Abu-Ali, Giuma; Enhaba; Ahmed

    2008-01-01

    In this paper, we present the essential conditions that should be required for transporting the radioactive materials. We demonstrate the procedure for transporting the radioactive iodine-131 from the Centre of Renewable Energies and Desalination of Water in Tajoura, Libya to Tripoli Medical Center. The safe measures were taken during the process of the transportation of the isotope produced in the centre including dosimetry analysis and the thickness of the container. (author)

  13. Optimization of cask for transport of radioactive material under impact loading

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, Kuldeep, E-mail: kuldeep.brit@gmail.com [Indian Institute of Technology Bombay (India); Pawaskar, D.N.; Guha, Anirban [Indian Institute of Technology Bombay (India); Singh, R.K. [Bhabha Atomic Research Center (India)

    2014-07-01

    Highlights: • Cost and weight are important criteria for fabrication and transportation of cask used for transportation of radioactive material. • Reduction of cask cost by modifying few cask geometry parameters using complex search method. • Maximum von Mises stress generated and deformation after impact as design constraints. • Up to 6.9% reduction in cost and 4.6% reduction in weight observed in the examples used. - Abstract: Casks used for transporting radioactive material need to be certified fit by subjecting them to a specific set of tests (IAEA, 2012). The high cost of these casks gives rise to the need for optimizing them. Conducting actual experiments for the process of design iterations is very costly. This work outlines a procedure for optimizing Type B(U) casks through simulations of the 9 m drop test conducted in ABAQUS{sup ®}. Standard designs and material properties were chosen, thus making the process as realistic as reasonable even at the cost of reducing the options (design variables) available for optimization. The results, repeated for different source cavity sizes, show a scope for 6.9% reduction in cost and 4.6% reduction in weight over currently used casks.

  14. First response to transportation emergencies involving radioactive materials

    International Nuclear Information System (INIS)

    1994-01-01

    This FEMA/DOE/DOT videocourse describes the basis for procedures to be used by emergency first responders for transportation accidents which involve radioactive materials. Various commercial and government sector radioactive materials shipment programs will be described and will include information about hazards and the elements of safety, proper first response actions, notification procedures, and state or federal assistance during emergencies. Primary audience: fire service and emergency management personnel

  15. Development of a state radioactive materials storage facility

    International Nuclear Information System (INIS)

    Schmidt, P.S.

    1995-01-01

    The paper outlines the site selection and facility development processes of the state of Wisconsin for a radioactive materials facility. The facility was developed for the temporary storage of wastes from abandoned sites. Due to negative public reaction, the military site selected for the facility was removed from consideration. The primary lesson learned during the 3-year campaign was that any project involving radioactive materials is a potential political issue

  16. Radioactive materials in ashes from peat fired plants

    International Nuclear Information System (INIS)

    Erlandsson, B.; Hedvall, R.

    1984-11-01

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

  17. Simulated Irradiation of Samples in HFIR for use as Possible Test Materials in the MPEX (Material Plasma Exposure Experiment) Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ellis, Ronald James [ORNL; Rapp, Juergen [ORNL

    2014-01-01

    The importance of Plasma Material Interaction (PMI) is a major concern in fusion reactor design and analysis. The Material-Plasma Exposure eXperiment (MPEX) facility will explore PMI under fusion reactor plasma conditions. Samples with accumulated displacements per atom (DPA) damage produced by irradiations in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) will be studied in the MPEX facility. The project presented in this paper involved performing assessments of the induced radioactivity and resulting radiation fields of a variety of potential fusion reactor materials. The scientific code packages MCNP and SCALE were used to simulate irradiation of the samples in HFIR; generation and depletion of nuclides in the material and the subsequent composition, activity levels, gamma radiation fields, and resultant dose rates as a function of cooling time. These state-of-the-art simulation methods were used in addressing the challenge of the MPEX project to minimize the radioactive inventory in the preparation of the samples for inclusion in the MPEX facility.

  18. Radioactive materials transportation life-cycle cost

    International Nuclear Information System (INIS)

    Gregory, P.C.; Donovan, K.S.; Spooner, O.R.

    1993-01-01

    This paper discusses factors that should be considered when estimating the life-cycle cost of shipping radioactive materials and the development of a working model that has been successfully used. Today's environmental concerns have produced an increased emphasis on cleanup and restoration of production plants and interim storage sites for radioactive materials. The need to transport these radioactive materials to processing facilities or permanent repositories is offset by the reality of limited resources and ever-tightening budgets. Obtaining the true cost of transportation is often difficult because of the many direct and indirect costs involved and the variety of methods used to account for fixed and variable expenses. In order to make valid comparisons between the cost of alternate transportation systems for new and/or existing programs, one should consider more than just the cost of capital equipment or freight cost per mile. Of special interest is the cost of design, fabrication, use, and maintenance of shipping containers in accordance with the requirements of the U.S. Nuclear Regulatory Commission. A spread sheet model was developed to compare the life-cycle costs of alternate fleet configurations of TRUPACT-II, which will be used to ship transuranic waste from U.S. Department of Energy sites to the Waste Isolation Pilot Plant near Carlsbad, New Mexico

  19. Radioactive materials in construction projects

    International Nuclear Information System (INIS)

    Herrmann, Ralf; Ohlendorf, Frank; Kaltz, Andrea Christine

    2014-01-01

    Till 1990 residues often of the former uranium mining were partly used as building material for road construction, terrain compensation and house construction in Saxony. These recommendations for action are addressed to applicants, planners and building constructors in the engineering and construction sector. It provides information for planning, preliminary investigations, applications, construction supervision related to radiation protection measures and documentation of construction projects where radioactive materials are expected.

  20. Recent advances of numerical simulation studies for radioactive cesium adsorption on soil materials

    International Nuclear Information System (INIS)

    Okumura, Masahiko; Nakamura, Hiroki; Machida, Masahiko

    2013-01-01

    Radiocesium (Cesium 134 and 137) emitted from destroyed Fukushima Daiichi Nuclear Power Production Station is known mostly to remain for a long time on earth's surfaces and to become sources of radiation exposure to habitants. Large scale decontamination work carried out by national and local governments inevitably produces tremendous amount of radioactive wastes of soils whose volume must be effectively and economically reduced based on a scientifically reliable technique. This paper employs the atomic and molecular simulation method applied to adsorption mechanism of soils and cesium ions and presents the examples of proposals with the results of this field. (S. Ohno)

  1. Truck transportation of radioactive materials

    International Nuclear Information System (INIS)

    Madsen, M.M.; Wilmot, E.L.

    1983-01-01

    Analytical models in RADTRAN II are used to calculate risks to population subgroups such as people along transport routes, people at stops, and crewman. The stops model, which calculates the dose to persons adjacent to the transport vehicle while it is stopped, frequently provides the largest contribution to incident-free radiological impacts. Components such as distances from the vehicle containing radioactive material to nearby people at stops, stop duration, and number of crew members are required for the stops model as well as other incident-free models. To provide supporting data for RADTRAN II based on operational experience, selected truck shipments of radioactive material were observed from origin to destination. Other important aspects of this program were to correlate package size to effective shipment transport index (TI) using radiological surveys and to characterize population distributions and proximities of people to the shipment at a generic truck stop

  2. Effect of Hydrogen Peroxide Content on the Preparation of Peroxotitanate Materials for the Treatment of Radioactive Wastewater

    Directory of Open Access Journals (Sweden)

    Wein-Duo Yang

    2016-01-01

    Full Text Available The modification of peroxotitanate using hydrogen peroxide significantly improved the ion-exchange capacity of titanate materials as sorbents for metal ions contained in a radioactive waste simulant solution. The effects of hydrogen peroxide content (hydrogen peroxide/titanium isopropoxide molar ratios, hereafter expressed as H/T on the properties of as-prepared titanate synthesized at 130°C and at pH of 6-7, followed by freeze-drying, were investigated. The peroxotitanate materials thus obtained were characterized by XRD, BET, SEM, TEM, EDX, ICP, and Raman spectroscopy. At an H/T ratio of 2, peroxotitanate predominantly exhibited an amorphous structure, with a clearly observed tubular or fibrous structure. Furthermore, peroxotitanate modified at an H/T ratio of 2 exhibited the best ion-exchange capacity of 191 mg g−1 for metal ions contained in a radioactive waste simulant solution. Hence, these peroxotitanate materials are suitable for removing metal ions from wastewater, especially lanthanide ions (Ln3+ and Sr2+.

  3. Raising students and educators awareness of radioactive materials transport through creative classroom materials and exhibits

    International Nuclear Information System (INIS)

    Holm, J.; Sandoz, C.; Dickenson, J.; Lee, J.C.; Smith, A.M.

    1994-01-01

    The public is concerned about how the shipping and handling of radioactive materials affects them and their environment. Through exhibit showings doing professional education conferences and smaller, focussed workshops, the United States Department of Energy (DOE) has found teachers and students to be an especially interested audience for hazardous and radioactive materials transportation information. DOE recognizes the importance of presenting educational opportunities to students about scientific and societal issues associated with planning for and safely transporting these types of materials. Raising students' and educators' awareness of hazardous and radioactive materials transport through creative classroom materials and exhibits may help them make informed decisions as adults about this often controversial and difficult issue

  4. Radioactive waste solidifying material

    International Nuclear Information System (INIS)

    Ono, Keiichi; Sakai, Etsuro.

    1989-01-01

    The solidifying material according to this invention comprises cement material, superfine powder, highly water reducing agent, Al-containing rapid curing material and coagulation controller. As the cement material, various kinds of quickly hardening, super quickly hardening and white portland cement, etc. are usually used. As the superfine powder, those having average grain size smaller by one order than that of the cement material are desirable and silica dusts, etc. by-produced upon preparing silicon, etc. are used. As the highly water reducing agent, surface active agents of high decomposing performance and comprising naphthalene sulfonate, etc. as the main ingredient are used. As the Al-containing rapidly curing material, calcium aluminate, etc. is used in an amount of less than 10 parts by weight based on 100 parts by weight of the powdery body. As the coagulation controller, boric acid etc. usually employed as a retarder is used. This can prevent dissolution or collaption of pellets and reduce the leaching of radioactive material. (T.M.)

  5. Determination of detailed standards for transportation of radioactive materials by ships

    International Nuclear Information System (INIS)

    1979-01-01

    The notification is defined under the regulations concerning marine transport and storage of dangerous things. Radioactive materials include hereunder uranium 233 and 235, plutonium 238, 239 and 241, their compounds and those materials which contain one or more than two of such materials. Materials whose quantities or quantities of components are less than 15 grams, and natural or depleted uranium are excluded. Permissible surface concentrations are 1/100,000 micro-curie per centi-meter 2 for radioactive materials emitting alpha rays, and 1/10,000 micro-curie per centi-meter 2 for radioactive materials not emitting alpha rays. Radioactive materials to be transported as L loads shall be not dispersing solid substances or those tightly enclosed in capsules, one of whose exterior sides at least is more than 0.5 centi-meter, having other several specified features. Other kinds of liquid and gas L loads are stipulated. Limits of radioactivity of L and A loads are provided for with tables attached. Transport conditions of A, BM and BU loads are fixed with bylaws. Leakages of BM and BU loads are also prescribed. Radioactive loads shall be marked by particular signals. Measures shall be taken to control exposures, which involve measurement of doses and exposure doses on board and appointment of exposure controllers. (Okada, K.)

  6. Safe transport of radioactive material

    International Nuclear Information System (INIS)

    1990-01-01

    Recently the Agency redefined its policy for education and training in radiation safety. The emphasis is now on long-term strategic planning of general education and training programmes. In line with this general policy the Agency's Standing Advisory Group for the Safe Transport of Radioactive Material (SAGSTRAM) in its 7th meeting (April 1989) agreed that increased training activity should be deployed in the area of transport. SAGSTRAM specifically recommended the development of a standard training programme on this subject area, including audio-visual aids, in order to assist Member States in the implementation of the Agency's Regulations for the Safe Transport of Radioactive Material. This training programme should be substantiated by a biennial training course which is thought to be held either as an Interregional or a Regional Course depending on demand. This training manual, issued as a first publication in the Training Course Series, represents the basic text material for future training courses in transport safety. The topic areas covered by this training manual and most of the texts have been developed from the course material used for the 1987 Bristol Interregional Course on Transport Safety. The training manual is intended to give guidance to the lecturers of a course and will be provided to the participants for retention. Refs, figs and tabs

  7. 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)

  8. Regulatory requirements on management of radioactive material safe transport in China

    International Nuclear Information System (INIS)

    Chu, C.

    2016-01-01

    Since 1980s, the IAEA Regulation for safe transport of radioactive material was introduced into China; the regulatory system of China began with international standards, and walked towards the institutionalized. In 2003 the National People’s Congress (NPC) promulgated “the Act on the Prevention of Radioactive Pollution of the People's Republic of China”. In 2009 “Regulation for the Safe Transport of Radioactive Material” (Referred to “Regulation”) was promulgated by the State Council. Subsequently, the National Nuclear Safety Administration (NNSA) began to formulate executive detailed department rules, regulations guidelines and standards. The present system of acts, regulations and standards on management of safe transport of radioactive material in China and future planning were introduced in this paper. Meanwhile, the paper described the specific administration requirements of the Regulation on classification management of radioactive materials, license management of transport packaging including design, manufacture and use, licensing management of transport activities and the provisions of illegal behaviors arising in safe transport of radioactive material. (author)

  9. Legislative developments in radioactive materials transportation, September 1993--June 1994

    International Nuclear Information System (INIS)

    Worthley, J.A.; Reed, J.B.; Cummins, J.

    1994-07-01

    This is the eighth report prepared by the National Conference of State Legislatures (NCSL) on developments in radioactive materials transportation. It updates information contained in the September 1993 report on Legislative Developments in Radioactive Materials Transportation and describes activities for the period September 1, 1993--June 30, 1994. NCSL currently is updating an on-line data base that contains abstracts of federal, state and local laws and regulations relating to the transportation of radioactive materials. The data base will be operated by NCSL under a cooperative agreement with the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management. Availability of on-line capability is anticipated by the end of August 1994. Users approved by DOE and NCSL will have access to the data base. This report contains the current status of legislation introduced in the 1993 and 1994 state legislative sessions, not previously reviewed in past reports. Bills that address nuclear materials transportation and the broader area of hazardous materials transportation are grouped by state according to their status--enacted, pending or failed. In addition, bills that deal with emergency preparedness are described. (General nuclear waste legislation with no transportation element is no longer tracked.) Also included are Federal Register notices and changes in federal regulations pertinent to radioactive waste and hazardous materials transportation

  10. Import/export Service of Radioactive Material

    CERN Multimedia

    2004-01-01

    Please note that the Import/Export service of radioactive material (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Web site: http://cern.ch/service-rp-shipping/ Tel.: 73171 E-mail: service-rp-shipping@cern.ch Radioactive Sources Service Please note that the radioactive sources service (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Moreover, the service being reduced, transports between Swiss and French sites (and vice versa) will now be achieved by internal transport. Web site : http://cern.ch/service-rp-sources Tel.: 73171 E-mail: service-rp-sources@cern.ch

  11. Inventory of accidents and losses at sea involving radioactive material

    International Nuclear Information System (INIS)

    2001-09-01

    The present report describes the content of the inventory of accidents and losses at sea involving radioactive material. It covers accidents and losses resulting in the actual release of radioactive materials into the marine environment and also those which have the potential for release. For completeness, records of radioactive materials involved in accidents but which were recovered intact from the sea are also reported. Information on losses of sealed sources resulting in actual or potential release of activity to the marine environment nad of sealed sources that were recovered intact is also presented

  12. Some Experience with Illicit Trafficking of Radioactive Materials in Tanzania

    International Nuclear Information System (INIS)

    Ngaile, J.E.; Banzi, F.P.; Kifanga, L.D.

    2008-01-01

    Illicit trafficking of radioactive materials (orphan sources or disuse sources) is of global concern. Reports on the IAEA Illicit Trafficking Data Base (ITDB) indicates increasing trend of incidents recorded in more than 40 countries on six continents[1]. It is suspected that nuclear trafficking is fueled by nuclear terrorism and is a threat for increasing illegal trade in nuclear and radioactive materials to manufacture Radiological Disposal Devices (RDD)- dirty bombs. As such, the international co-operative efforts are needed to uncover and combat nuclear trafficking in order to minimize its consequences such as external radiation exposure of persons from source to various radiation levels during illicit movement and after seizure; rupture of source leading to internal exposure of persons and environmental contamination. Although accidents with radioactive materials have not occurred in the United Republic of Tanzania (URT), incidents of illicit trafficking and unauthorized possession of radioactive materials has occurred thus prompting the Tanzania Atomic Energy Commission (TAEC) to strengthen its nuclear security of nuclear and radioactive material in the URT. Nuclear faclities and radioactive sources lacks adequate physical protection against theft, fire or different forms of unauthorized access. Tanzaniaia has recorded about thirteen (13) illicit trafficking incidents of radioactive between 1996-2006. Caesium-137, Uranium-238; and Uranium oxide standard and Radium-226 with activity ranging from low to significantly high were among the radiounuclides which were intercepted. Most of these incidents had their original outside Tanzania. The incidents were uncovered by informers in cooperation with the police. Despite the fact that the management of these incidents by the police were adequate, it was observed that there is an inadequate radiation protection arrangements during transport of seized sources; lack of precautions for safety when handling seized

  13. Transportation of radioactive materials: legislative and regulatory information system

    International Nuclear Information System (INIS)

    Fore, C.S.; Heiskell, M.M.

    1980-01-01

    The transportation of radioactive materials, as well as hazardous materials in general, has been an issue of ever-increasing concern and an object of numerous regulations and legislative actions worldwide. The Transportation Technology Center of the US Department of Energy's Sandia Laboratories in Albuquerque, New Mexico, is currently involved in developing a national program to assure the safe shipment of radioactive materials. At Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, this overall effort is being supported in a specialized manner. As part of the Logistics Modeling program at ORNL, the Ecological Sciences Information Center has developed comprehensive data bases containing legislative and regulatory actions relevant to the transportation of hazardous materials. The data bases are separated according to status level of the legislation. The Current Legislation Data Base includes all new legislative actions introduced during the present year (1980) or those bills carried over from the previous year's sessions. The second data file, Historical Legislation Data Base, consists of all legislative actions since 1976 that have passed and become public laws, as well as those actions that were unsuccessful and were classified as denied by law. Currently the data bases include state-, local-, and federal, level legislation, with emphasis on the transportation of radioactive materials. Because of their relevance to the transportation issues, actions involving related subject areas such as, disposal and storage of radioactive wastes, moratoriums on power plant construction, and remedial actions studies, special agencies to regulate shipment of radioactive materials, and requirements of advanced notification, permits and escorts are also included in the data bases

  14. Emergency preparedness and response in transport of radioactive material

    International Nuclear Information System (INIS)

    Takani, Michio

    2008-01-01

    Nuclear power has been providing clean, affordable electricity in many parts of the world for nearly half a century. The national and international transport of nuclear fuel cycle materials is essential to support this activity. To sustain the nuclear power industry, fuel cycle materials have to be transported safely and efficiently. The nature of the industry is such that most countries with large-scale nuclear power industries cannot provide all the necessary fuel services themselves and consequently nuclear fuel cycle transport activities are international. The radioactive material transport industry has an outstanding safety record spanning over 45 years; however the transport of radioactive materials cannot and most not be taken for granted. Efficient emergency preparedness and response in the transport of radioactive material is an important element to ensure the maximum safety in accident conditions. The World Nuclear Transport Institute (WNTI), founded by International Nuclear Services (INS) of the United Kingdom, AREVA of France an the Federation of Electric Power Companies (FEPC) of Japan, represents the collective interest of the radioactive material transport sector, and those who rely on safe, effective and reliable transport. As part of its activities, WNTI has conducted two surveys through its members on emergency preparedness and response in the transport of radioactive material and emergency exercises. After recalling the International Atomic Energy Agency approach on emergency response, this paper will be discussing the main conclusion of surveys, in particular the national variations in emergency response and preparedness on the national and local levels of regulations, the emergency preparedness in place, the emergency response organisation (who and how), communication and exercises. (author)

  15. Natural Radioactivity in Ceramic Materials

    International Nuclear Information System (INIS)

    Abu Khadra, S.A.; Kamel, N.H.

    2005-01-01

    Ceramics are one of the most important types of the industrial building materials. The raw materials of the ceramic are made of a mixture of clay, feldspar, silica, talc kaolin minerals together with zirconium silicates (ZrSiO4).The ceramic raw materials and the final products contain naturally occurring radionuclide mainly U-238 and, Th-232 series, and the radioactive isotope of potassium K-40. Six raw ceramic samples were obtained from the Aracemco Company at Egypt together with a floor tile sample (final product) for measuring radioactive concentration levels., The activity of the naturally U-238, Th-232, and K-40 were determined as (Bq/kg) using gamma spectroscopy (Hyperactive pure germanium detector). Concentration of U and Th were determined in (ppm) using spectrophotometer technique by Arsenazo 111 and Piridy l-Azo -Resorcinol (PAR) indicators. Sequential extraction tests were carried out in order to determine the quantity of the radionuclide associated with various fractions as exchangeable, carbonate, acid soluble and in the residue. The results evaluated were compared to the associated activity indices (AI) that were defined by former USSR and West Germany

  16. Safe transport of radioactive material. 3. ed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-12-01

    The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA.

  17. Safe transport of radioactive material. 3. ed

    International Nuclear Information System (INIS)

    2002-01-01

    The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA

  18. Cementitious materials for radioactive waste management within IAEA coordinated research project - 59021

    International Nuclear Information System (INIS)

    Drace, Zoran; Ojovan, Michael I.

    2012-01-01

    The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, waste-forms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields); (vii) testing and non-destructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria for waste packages, waste forms and backfills; transport, long term storage and disposal requirements;and finally (ix) modelling or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling, especially in the post-closure phase. The CRP has gathered overall 26 research organizations from 22 Member States aiming to share their research and practices on the use of cementitious materials [2]. The main research outcomes of the CRP were summarized in a summary report currently under preparation to be published by IAEA. The generic topical sections covered by report are: a) conventional cementitious systems; b) novel cementitious

  19. Anticipated development in radioactive materials packaging and transport systems

    International Nuclear Information System (INIS)

    Williams, L.D.; Rhoads, R.E.; Hall, R.J.

    1976-07-01

    Closing the light water reactor fuel cycle and the use of mixed oxide fuels will produce materials such as solidified high level waste, cladding hulls and plutonium from Pu recycle fuel that have not been transported extensively in the past. Changes in allowable gaseous emissions from fuel cycle facilities may require the collection and transportation of radioactive noble gases and tritium. Although all of these materials could be transported in existing radioactive material packaging, economic considerations will make it desirable to develop new packaging specifically designed for each material. Conceptual package designs for these materials are reviewed. Special Nuclear Material transportation safeguards are expected to have a significant impact on future fuel cycle transportation. This subject is reviewed briefly. Other factors that could affect fuel cycle transportation are also discussed. Development of new packaging for radioactive materials is not believed to require the development of new technologies. New package designs will be primarily an adaptation of existing technology to fit the changing needs of a growing nuclear power industry. 23 references

  20. Refilling material for underground disposal of radioactive waste

    International Nuclear Information System (INIS)

    Yajima, Tatsuya; Kato, Hiroyasu.

    1995-01-01

    Generally, the underground circumstance where radioactive wastes are to be processed is in high pH and highly ionized state due to ingredients leached out of cement of a concrete pit and solidifying products. A refilling material for underground disposal are demanded to adsorb radioactive nuclides such as 137 Cs even in such a state. As the refilling material, a mixture of bentonite and sintered vermiculite, preferably, comprising 10 to 40wt% of vermiculite is used. The refilling material has a high water hold out barrier performance of bentonite and a high radioactive nuclide adsorbing performance of vermiculite. In a state of highly ionized state when the adsorbing performance of bentonite is reduced, the nuclide-absorbing performance is improved by vermiculite and since the content of the vermiculite is not more than 40wt%, the water hold out barrier performance of the bentonite is not deteriorated. (N.H.)

  1. The contribution of human factors to risks from radioactive material transport

    International Nuclear Information System (INIS)

    Blenkin, J.J.; Ridsdale, E.; Wilkinson, H.L.

    1998-01-01

    The use of probabilistic risk assessment to assess the safety of radioactive material transport operations is well accepted. However, quantitative risk assessment of radioactive material transport operations have generally not explicitly considered human factors in estimating risks. Given the high profile of human factors as the root cause of many serious transport incidents omission of an explicit consideration of human factors in a risk assessment could lead to assessments losing credibility. In addition, scrutiny of radioactive material transport incident databases reveals a large number of operational incidents and minor accidents that would have been avoided if more attention had been paid to human factors aspects, and provides examples of instances where improvements have been achieved. This paper examines the areas of radioactive material transport risk assessments (both qualitative and quantitative) which could be strengthened by further examination of the impact of human errors. It is concluded that a more complete and detailed understanding of the effects of human factors on the risks from radioactive material transport operations has been obtained. Quality assurance has a key part to play in ensuring that packages are correctly manufactured and prepared for transport. Risk assessments of radioactive material transport operations can be strengthened by concentrating on the key human factors effects. (authors)

  2. Status of radioactive material transport

    International Nuclear Information System (INIS)

    Kueny, Laurent

    2012-01-01

    As about 900.000 parcels containing radioactive materials are transported every year in France, the author recalls the main risks and safety principles associated with such transport. He indicates the different types of parcels defined by the regulation: excepted parcels, industrial non fissile parcels (type A), type B and fissile parcels, and highly radioactive type C parcels. He briefly presents the Q-system which is used to classify the parcels. He describes the role of the ASN in the control of transport safety, and indicates the different contracts existing between France or Areva and different countries (Germany, Japan, Netherlands, etc.) for the processing of used fuels in La Hague

  3. Environmental effects associated with the transportation of radioactive material

    International Nuclear Information System (INIS)

    McClure, J.D.; Pope, R.B.; Yoshimura, H.R.

    1979-01-01

    The primary aim of this paper has been to describe some of the background information concerning nuclear materials transportation systems, accident statistics, accident severities, and test information - all of which when combined yield an environmental statement of the risks associated with the transportation of radioactive materials. The results of the ultimate risk analysis are expressed in terms of numbers of fatalities and, in that sense at least, tend to be an absolute measure of risk. When these risks are compared with other accepted societal risks, the relative risks associated with radioactive material transportation can be established. This information can be used to make decisions at the governmental level and to inform an interested public about these risks. It can be concluded that the risks associated with the transportation of radioactive material are low relative to the other risks that society has already accepted

  4. Quality assurance for packaging of radioactive and hazardous materials

    International Nuclear Information System (INIS)

    Gustafson, L.D.

    1986-01-01

    The Department of Energy (DOE) has required for many years that quality assurance programs be established and implemented for the packaging of radioactive and hazardous materials. This paper identifies various requirement principles and related actions involved in establishing effective quality assurance for packaging of radioactive and hazardous materials. A primary purpose of these quality assurance program activities is to provide assurance that the packaging and transportation of hazardous materials, which includes radioactive and fissile materials, are in conformance with appropriate governmental regulations. Applicable regulations include those issued by the Nuclear Regulatory Commission (NRC), the Department of Transportation (DOT), and the Environmental Protection Agency (EPA). DOE Order 5700.6A establishes that quality assurance requirements are to be applied in accordance with national consensus standards where suitable ones are available. In the nuclear area, ANSI/ASME NQA-1 is the preferred standard

  5. Radioactive materials

    International Nuclear Information System (INIS)

    Sugiura, Yoshio; Shimizu, Makoto.

    1975-01-01

    The problems of radioactivity in the ocean with marine life are various. Activities in this field, especially the measurements of the radioactivity in sea water and marine life are described. The works first started in Japan concerning nuclear weapon tests. Then the port call to Japan by U.S. nuclear-powered naval ships began. On the other hand, nuclear power generation is advancing with its discharge of warm water. The radioactive pollution of sea water, and hence the contamination of marine life are now major problems. Surveys of the sea areas concerned and study of the radioactivity intake by fishes and others are carried out extensively in Japan. (Mori, K.)

  6. 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.

  7. Framework for assessing the effects of radioactive materials transportation

    International Nuclear Information System (INIS)

    Zoller, J.N.

    1996-01-01

    Radioactive materials transport may result in environmental effects during both incident-free and accident conditions. These effects may be caused by radiation exposure, pollutants, or physical trauma. Recent environmental impact analyses involving the transportation of radioactive materials are cited to provide examples of the types of activities which may be involved as well as the environmental effects which can be estimated

  8. Security of material: Preventing criminal activities involving nuclear and other radioactive materials

    International Nuclear Information System (INIS)

    Nilsson, A.

    2001-01-01

    The report emphasizes the need for national regulatory authorities to include in the regulatory systems, measures to control and protect nuclear materials from being used in illegal activities, as well as aspects of relevance for detecting and responding to illegal activities involving nuclear and other radioactive materials. The report will give an overview of the international treaties and agreements that underpin the establishment of a regulatory structure necessary for States to meet their non-proliferation policy and undertakings. Ongoing work to strengthen the protection of nuclear material and to detect and respond to illegal activities involving nuclear and other radioactive material will be included. The focus of the paper is on the need for standards and national regulation in the nuclear security area. (author)

  9. Method of preventing contaminations in radioactive material handling facilities

    International Nuclear Information System (INIS)

    Inoue, Shunji.

    1986-01-01

    Purpose: To prevent the contamination on the floor surface of working places by laying polyvinyl butyral sheets over the floor surface, replacing when the sheets are contaminated, followed by burning. Method: Polyvinyl butyral sheets comprising 50 - 70 mol% of butyral component are laid in a radioactive material handling facility, radioactive materials are handled on the polyvinyl butyral sheets and the sheets are replaced when contaminated. The polyvinyl butyral sheets used contain 62 - 68 mol% of butyral component and has 0.03 - 0.2 mm thickness. The contaminated sheets are subjected to burning processing. This can surely collect radioactive materials and the sheets have favorable burnability, releasing no corrosive or deleterious gases. In addition, they are inexpensive and give no hindrance to the workers walking. (Takahashi, M.)

  10. Using computer technology to identify the appropriate radioactive materials packaging

    International Nuclear Information System (INIS)

    Driscoll, K.L.; Conan, M.R.

    1989-01-01

    The Radioactive Materials Packaging (RAMPAC) database is designed to store and retrieve information on all non-classified packages certified for the transport of radioactive materials within the boundaries of the US. The information in RAMPAC is publicly available, and the database has been designed so that individuals without programming experience can search for and retrieve information using a menu-driven system. RAMPAC currently contains information on over 650 radioactive material shipping packages. Information is gathered from the US Department of Energy (DOE), the US Department of transportation (DOT), and the US Nuclear Regulatory Commission (NRC). RAMPAC is the only tool available to radioactive material shippers that contains and reports packaging information from all three Federal Agencies. The DOT information includes package listings from Canada, France, Germany, Great Britain, and Japan, which have DOT revalidations for their certificates of competent authority and are authorized for use within the US for import and export shipments only. RAMPAC was originally developed in 1981 by DOE as a research and development tool. In recent years, however, RAMPAC has proven to be highly useful to operational personnel. As packages become obsolete or materials to be transported change, shippers of radioactive materials must be able to determine if alternative packages exist before designing new packages. RAMPAC is designed to minimize the time required to make this determination, thus assisting the operational community in meeting their goals

  11. Legislative developments in radioactive materials transportation, April 1993--August 1993

    International Nuclear Information System (INIS)

    Reed, J.B.; Cummins, J.

    1993-09-01

    This is the seventh report prepared by the National Conference of State Legislatures (NCSL) on developments in radioactive materials transportation. It updates information contained in the April 1993 report on Legislative Developments in Radioactive Materials Transportation and describes activities for the period April 1, 1993--August 31, 1993. NCSL currently is updating an on-line data base that contains abstracts of federal, state and local laws and regulations relating to the transportation of radioactive materials. The data base will be operated by NCSL under a cooperative agreement with the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management. Limited availability of on-line capability is anticipated by the end of 1993. Users approved by DOE and NCSL will have access to the data base. A copy of any legislation listed in this report can be obtained by contacting the people listed below. This report contains the current status of legislation introduced in the 1993 state legislative sessions, not previously reviewed in past reports. Bills that address nuclear materials transportation and the broader area of hazardous materials transportation are grouped by state according to their status--enacted, pending or failed. In addition, bills that deal with emergency preparedness are described. (General nuclear waste legislation with no transportation element is no longer tracked.) Also included are Federal Register notices pertinent to radioactive waste and hazardous materials transportation

  12. Legislative developments in radioactive materials transportation, November 1992--March 1993

    International Nuclear Information System (INIS)

    Reed, J.B.; Cummins, J.

    1993-04-01

    This is the sixth report prepared by the National Conference of State Legislatures (NCSL) on developments in radioactive materials transportation. It updates information contained in the November 1992 Legislative and Legal Developments in Radioactive Materials Transportation report and describes activities for the period November 1, 1992--March 31, 1993. NCSL is working to bring on-line a data base that contains abstracts of state laws and regulations relating to the transportation of radioactive materials. The data base will be operated by NCSL under a cooperative agreement with the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management. Limited availability of on-line capability is anticipated by the end of July 1993. Users approved by DOE and NCSL will have access to the data base. Hard copy of any legislation listed in this report can be obtained by contacting the people listed below. This report contains summaries of legislation introduced in the 1993 state legislative sessions. Bills that address nuclear materials transportation and the broader area of hazardous materials transportation are grouped by state according to their status--enacted, pending or failed. In addition, bills that deal with emergency preparedness and general nuclear waste issues are described. Also included are Federal Register notices pertinent to radioactive waste and hazardous materials transportation. A recent court decision is also summarized

  13. The safe transport of radioactive materials

    International Nuclear Information System (INIS)

    Messenger, W. de L.M.

    1979-02-01

    The hazards of radioactive materials in transport are surveyed. The system whereby they are safely transported between nuclear establishments in the United Kingdom and overseas is outlined. Several popular misconceptions are dealt with. (author)

  14. Transportation incidents involving Canadian shipments of radioactive material

    International Nuclear Information System (INIS)

    Jardine, J.M.

    1979-06-01

    This paper gives a brief statement of the legislation governing the transportation of radioactive materials in Canada, reviews the types of shipments made in Canada in 1977, and surveys the transportation incidents that have been reported to the Atomic Energy Control Board over the period 1947-1978. Some of the more significant incidents are described in detail. A totAl of 135 incidents occurred from 1947 to 1978, during which time there were 644750 shipments of radioactive material in Canada

  15. Radiological consequences of radioactive substances in building materials

    International Nuclear Information System (INIS)

    Tschurlovits, M.

    1982-01-01

    A review of radiological consequences of radioactive substances in building materials is given. Where the other contributing papers are dealing with technical problems and measuring techniques, this paper is going beyond the term dose and is considering the risk by radioactive substances in building materials in relation to conventional risks. The present state of international standards is also discussed. If a limit of 1 mSv is adopted, it is shown that this limit is just met at present conditions. (Author) [de

  16. Priorities for technology development and policy to reduce the risk from radioactive materials

    International Nuclear Information System (INIS)

    Duggan, Ruth Ann

    2010-01-01

    The Standing Committee on International Security of Radioactive and Nuclear Materials in the Nonproliferation and Arms Control Division conducted its fourth annual workshop in February 2010 on Reducing the Risk from Radioactive and Nuclear Materials. This workshop examined new technologies in real-time tracking of radioactive materials, new risks and policy issues in transportation security, the best practices and challenges found in addressing illicit radioactive materials trafficking, industry leadership in reducing proliferation risk, and verification of the Nuclear Nonproliferation Treaty, Article VI. Technology gaps, policy gaps, and prioritization for addressing the identified gaps were discussed. Participants included academia, policy makers, radioactive materials users, physical security and safeguards specialists, and vendors of radioactive sources and transportation services. This paper summarizes the results of this workshop with the recommendations and calls to action for the Institute of Nuclear Materials Management (INMM) membership community.

  17. 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

  18. SOR/89-426, Transport Packaging of Radioactive Materials Regulations, amendment

    International Nuclear Information System (INIS)

    1989-01-01

    These Regulations of 24 August 1989 amend the Transport Packaging of Radioactive Materials Regulations by clarifying the text and specifying certain requirements. In particular certain definitions have been replaced, namely those of ''Fissile Class III package'' and ''Special form radioactive material''. Also, this latter material may not be carried without a certificate attesting that it meets the requirements of the Regulations. (NEA)

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

    International Nuclear Information System (INIS)

    Schwarz, Guenther

    2012-01-01

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

  20. Development of a wireless radioactive material sensor network

    Energy Technology Data Exchange (ETDEWEB)

    Katsis, Dimosthenis, E-mail: katsisdc@ieee.org [US Army Research Laboratory, Athena Energy Corporation, Adelphi, Bowie, MD (United States); Burns, David; Henriquez, Stanley; Howell, Steve; Litz, Marc [US Army Research Laboratory, Athena Energy Corporation, Adelphi, Bowie, MD (United States)

    2011-10-01

    Our team at the United States Army Research Laboratory (ARL) has designed and developed a low-power, compact, wireless-networked gamma sensor (WGS) array. The WGS system provides high sensitivity gamma photon detection and remote warning for a broad range of radioactive materials. This sensor identifies the presence of a 1 {mu}Ci Cs137 source at a distance of 1.5 m. The networked array of sensors presently operates as a facility and laboratory sensor for the movement of radioactive check sources. Our goal has been to apply this architecture for field security applications by incorporating low-power design with compact packaging. The performance of this radiation measurement network is demonstrated for both detection and location of radioactive material.

  1. 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

  2. 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

  3. Procedure for permanently storing radioactive material

    International Nuclear Information System (INIS)

    Canevall, J.

    1987-01-01

    This patent describes a method of storing radioactive material in a hollow construction having an access opening. The construction is located below the surface of the ground within a rock chamber. The chamber has walls, a floor, and a ceiling. The construction is completely spaced from the walls, floor, and ceiling of the rock chamber to form an outer spacing, and the construction is made of material impervious to water. The construction comprises a capsule storage area and a capsule handling passageway adjacent thereto having a track and being connected to a lift-shaft running to the surface. The method includes the steps of: completely filling the outer spacing between the walls, ceiling, and floor of the rock chamber and the construction with material not impervious to water; placing capsules containing the radioactive waste in encapsulated form into the capsule storage area; filling the storage area around the loaded capsule with a sealing material to enclose the capsules; repeating the placing and filling steps until the storage area has been completely filled in with the capsules and sealing material; loading the passageway adjacent the storage area with a removable material different than the sealing material; closing the construction and sealing the lift-shaft at least at the construction level and at ground level; and providing means for collecting any water penetrating into the outer spacing

  4. Measurement of naturally occurring radioactive materials in commonly used building materials in Hyderabad, India

    International Nuclear Information System (INIS)

    Balbudhe, A.Y.; Vishwa Prasad, K.; Vidya Sagar, D.; Jha, S.K.; Tripathi, R.M.

    2018-01-01

    Building materials can cause significant gamma dose indoors, due to their natural radioactivity content. The knowledge of the natural radioactivity level of building materials is important for determination of population exposure, as most people spend 80-90% of their time indoors furthermore, it is useful in setting the standards and national guidelines for the use and management of these materials. The concentrations of natural radionuclides in building materials vary depending on the local geological and geographical conditions as well as geochemical characteristics of those materials. The aim of the study is to determine levels of natural radionuclide in the commonly used building materials in Hyderabad, India

  5. Natural radioactivity in granite stones and their radiological aspects as building material

    International Nuclear Information System (INIS)

    Kumaravel, S.; Sunil, C.N.; Narashimha Nath, V.; Raghunath, T.; Prashanth Kumar, M.; Ramakrishna, V.; Nair, B.S.K.; Purohit, R.G.; Tripati, R.M.

    2014-01-01

    Natural radioactivity in building and building decorating materials comes mainly from natural radioactive series like 238 U, 232 Th and 40 K. India is one of the leading users of granite stones as it is preferred by decorators and architects. The knowledge of presence of natural radioactivity in these materials is required for the assessment of radiation exposure due to them. The objective of this study is to determine the natural radioactivity and radiological aspects of granite stones as building material

  6. Safe transport of radioactive material. 4. ed

    International Nuclear Information System (INIS)

    2006-01-01

    The IAEA has been publishing Regulations for the Safe Transport of Radioactive Material since 1961. Meeting its statutory obligation to foster the exchange and training of scientists and experts in the field of peaceful uses of atomic energy, the IAEA has developed a standardized approach to transport safety training. This training manual is an anchor of the standardized approach to training. It is a compendium of training modules for courses related to the different aspects of safety of transport of radioactive material. Keeping in view the specific needs of the potential users, the manual includes material that can be used for a variety of training programmes of duration ranging from half-a-day to ten days, for specific audiences such as competent authority personnel, public authorities, emergency response personnel and cargo handlers

  7. Processing method for liquid waste containing various kinds of radioactive material

    International Nuclear Information System (INIS)

    Toyabe, Keiji; Nabeshima, Masahiro; Ozeki, Noboru; Muraki, Tsutomu.

    1996-01-01

    Various kind of radioactive materials and heavy metal elements dissolved in liquid wastes are removed from the liquid wastes by adsorbing them on chitin or chitosan. In this case, a hydrogen ion concentration in the liquid wastes is adjusted to a pH value of from 1 to 3 depending on the kinds of the radioactive materials and heavy metal elements to be removed. Since chitin or chitosan has a special ion exchange performance or adsorbing performance, chemical species comprising radioactive materials or heavy metals dissolved in the liquid wastes are adsorbed thereto by ion adsorption or physical adsorption. With such procedures, radioactive materials and heavy metal elements are removed from the liquid wastes, and the concentration thereof can be reduced to such a level that they can be discharged into environments. On the other hand, since chitin or chitosan adsorbing the radioactive materials and heavy metal elements has a structure of polysaccharides, it is easily burnt into gaseous carbon dioxide. Accordingly, the amount of secondary wastes can remarkably be reduced. (T.M.)

  8. Transportation of radioactive materials. Safety and regulation

    International Nuclear Information System (INIS)

    Niel, Jean-Christophe

    2013-01-01

    This engineering-oriented publication first presents fluxes and risks related to the transportation of radioactive materials: fluxes, risks, in-depth defence, and parcel typology. The author then describes the elaboration process for transportation regulations: IAEA recommendations for the transportation of radioactive materials and their review process, IAEA recommendations for modal regulations. He presents the French transportation regulation framework: evolutions of IAEA recommendations, case of aerial transport, and case of maritime transport. The next part addresses the specific case of the transportation of uranium hexafluoride. The last part addresses incidents and accidents occurring during transportation: declarations to be made, brief presentations of several examples of incidents and accidents

  9. Physical protection of radioactive material in transport

    International Nuclear Information System (INIS)

    1975-01-01

    Safety in the transport of radioactive material is ensured by enclosing the material, when necessary, in packaging which prevents its dispersal and which absorbs to any adequate extent any radiation emitted by the material. Transport workers, the general public and the environment are thus protected against the harmful effects of the radioactive material. The packaging also serves the purpose of protecting its contents against the effects of rough handling and mishaps under normal transport conditions, and against the severe stresses and high temperatures that could be encountered in accidents accompanied by fires. If the radioactive material is also fissile, special design features are incorporated to prevent any possibility of criticality under normal transport conditions and in accidents. The safe transport requirements are designed to afford protection against unintentional opening of packages in normal handling and transport conditions and against damage in severe accident conditions; whereas the physical protection requirements are designed to prevent intentional opening of packages and deliberate damage. This clearly illustrates the difference in philosophical approach underlying the requirements for safe transport and for physical protection during transport. This difference in approach is, perhaps, most easily seen in the differing requirements for marking of consignments. While safety considerations dictate that packages be clearly labelled, physical protection considerations urge restraint in the use of special labels. Careful consideration must be given to such differences in approach in any attempt to harmonize the safety and physical protection aspects of transport. (author)

  10. The safety of radioactive materials transport

    International Nuclear Information System (INIS)

    Niel, J.Ch.

    1997-01-01

    Five accidents in radioactive materials transport have been studied; One transport accident by road, one by ship, one by rail, and the two last in handling materials from ships in Cherbourg port and Le Havre port. All these accidents were without any important consequences in term of radiation protection, but they were sources of lessons to improve the safety. (N.C.)

  11. Method of melting and decontaminating radioactive contaminated aluminum material

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Miura, Noboru; Kawasaki, Katsuo; Iba, Hajime.

    1986-01-01

    Purpose: To improve the decontaminating efficiency upon melting decontamination of radioactive-contaminated aluminum materials. Method: This invention concerns an improvement for the method of melting decontamination by adding slug agent composed of organic compound to contaminated aluminum material and extracting the radioactive materials into the slug thereby decontaminating the aluminum material. Specifically metals effective for reducing the active amount of aluminum are added such that the content is greater than a predetermined value in the heat melting process. The metal comprises Mg, Cu or a mixture thereof and the content is more than 4 % including those previously contained in the aluminum material. (Ikeda, J.)

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

    International Nuclear Information System (INIS)

    Brehm, W.F.

    1980-03-01

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

  13. The design, construction and testing of packaging[Radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-07-01

    Essentially uniform regulations, based on the IAEA Regulations for the Safe Transport of Radioactive Materials, have been adopted on a world-wide basis with the aim of ensuring safety in the transport of radioactive and fissile substances by road, rail, sea and air. The application of these regulations over a period of almost 20 years has resulted in practically complete safety in the sense that there has been no evidence of death or injury that could be attributed to the special properties of the material even when consignments were involved in serious accidents. In the regulations, reliance is placed, to the greatest extent possible, on the packaging to provide adequate shielding and containment of the contents under both normal transport and accident conditions. The Agency organized an international seminar in 1971 to consider the performance tests that have to be applied to packaging to demonstrate compliance with the regulatory requirements. The general conclusion was that the testing programme specified in the regulations was adequate for the near future, but that further consideration should be given to assessing the risks presented by the increasing volume of transport. The second international seminar, which is the subject of this report, dealt with all aspects of the design, construction and testing of packaging for the transport both of relatively small quantities of radioactive substances, which are being used to an ever increasing extent for medical and research purposes, and of the much larger quantities arising in various stages of the nuclear fuel cycle. The programme covered the general requirements for packaging; risk assessment for the transport of various radioactive and fissile substances, including plutonium; specific features of the design and construction of packaging; quality assurance; damage simulation tests, including calculational methods and scale-model testing; tests for the retention of shielding and containment after damage; and the

  14. Analysis on the atmospheric dispersion of radioactive materials

    International Nuclear Information System (INIS)

    Nagai, Haruyasu

    2012-01-01

    JAEA has been developing a new prediction system of comprehensive movement, SPEEDI-MP (SPEEDI Multi-model Package), which can treat continuously and strictly with the migration behavior of radioactive materials at atmosphere, sea, and land region. JAEA has been further promoting the detail analysis of atmospheric migration of radioactive materials dispersed by an accident. Then, using a part of this system, the atmospheric-diversion prediction system, WSPEEDI-II, the atmospheric diversion mass and the atmospheric diffusion analysis were carried out. This issue reports the summary. (M.H.)

  15. Radioactive material handling for radiopharmaceutical production

    International Nuclear Information System (INIS)

    Anwar Abd Rahman; Rosli Darmawan; Mohd Khairi Mohd Said; Mohd Arif Hamzah; Mohd Fadil Ismail; Mohd Nor Atan; Mohd Azam Safawi Omar; Zulkifli Hashim; Wan Anuar Wan Awang

    2005-01-01

    Construction of clean room at Block 21 had changed the flow of radioactive material Moly-99 into the hotcell. The existing flow which use the transport cask cannot be used in order to prevent the clean room from contamination. Therefore, the new technique which consist of robotic, pneumatic and transfer box system had been introduced to transfer the radioactive source into the hotcell without going through the clean room.This technique that has been introduced provides safety where the radiation workers control the transfer process by using remote system. (Author)

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

    International Nuclear Information System (INIS)

    Norris, G.H.

    1987-11-01

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

  17. Lessons learned by southern states in transportation of radioactive materials

    International Nuclear Information System (INIS)

    1992-03-01

    This report has been prepared under a cooperative agreement with DOE's Office of Civilian Radioactive Waste Management (OCRWM) and is a summary of the lessons learned by southern states regarding the transportation of radioactive materials including High-Level Radioactive Wastes (HLRW) and Spent Nuclear Fuel (SNF). Sources used in this publication include interviews of state radiological health and public safety officials that are members of the Southern States Energy Board (SSEB) Advisory Committee on Radioactive Materials Transportation, as well as the Board's Transuranic (TRU) Waste Transportation Working Group. Other sources include letters written by the above mentioned committees concerning various aspects of DOE shipment campaigns

  18. Transport of radioactive material

    International Nuclear Information System (INIS)

    Lombard, J.

    1996-01-01

    This work deals with the transport of radioactive materials. The associated hazards and potential hazards are at first described and shows the necessity to define specific safety regulations. The basic principles of radiological protection and of the IAEA regulations are given. The different types of authorized packages and of package labelling are explained. The revision, updating and the monitoring of the regulations effectiveness is the subject of the last part of this conference. (O.M.)

  19. Radioactive material air transportation

    International Nuclear Information System (INIS)

    Pader y Terry, Claudio Cosme

    2002-01-01

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

  20. Over the border - the problems of uncontrolled radioactive materials crossing national borders

    Energy Technology Data Exchange (ETDEWEB)

    Duftschmid, K.E. E-mail: k.duftschmid@aon.at

    2002-03-01

    Cross-border movement of radioactive materials and contaminated items, in particular metallurgical scrap, has become a problem of increasing importance. Radioactive sources out of regulatory control, now often called 'orphan sources', have frequently caused serious, even deadly, radiation exposures and widespread contamination. The United States Nuclear Regulatory Commission reported over 2300 incidents of radioactive materials found in recycled metal scrap and more than 50 accidental smeltings of radioactive sources. A further potentially serious problem is illicit trafficking in nuclear and other radioactive materials. In 1995 the International Atomic Energy Agency (IAEA) started a programme to combat illicit trafficking in nuclear and other radioactive materials, which includes an international database on incidents of illicit trafficking, receiving reports from some 80 member states. For the period 1993-2000 the IAEA database includes 345 confirmed incidents. While from 1994-1996 the frequency declined significantly, this trend has been reversed since 1997, largely due to radioactive sources rather than nuclear material. This paper compares monitoring techniques for radioactive materials in scrap applied at steel plants and scrap yards with monitoring at borders, a completely different situation. It discusses the results of the 'Illicit Trafficking Radiation Detection Assessment Program', a large international pilot study, conducted in cooperation between the IAEA, the Austrian Government and the Austrian Research Centre Seibersdorf. The aim of this exercise was to derive realistic and internationally agreed requirements for border monitoring instrumentation. Finally the present extent of border monitoring installations is discussed. (author)

  1. Radioactive source simulation for half-life experiment

    International Nuclear Information System (INIS)

    Wanitsuksombut, Warapon; Decthyothin, Chanti

    1999-01-01

    A simulation of radioactivity decay by using programmable light source with a few minutes half-life is suggested. A photodiode with digital meter label in cps is use instead of radiation detector. Both light source and photodiode are installed in a black box to avoid surrounding room light. The simulation set can also demonstrate Inverse Square Law experiment of radiation penetration. (author)

  2. Numerical study of thermal test of a cask of transportation for radioactive material

    International Nuclear Information System (INIS)

    Vieira, Tiago A.S.; Santos, André A.C. dos; Vidal, Guilherme A.M.; Silva Junior, Geraldo E.

    2017-01-01

    In this study numerical simulations of a transport cask for radioactive material were made and the numerical results were compared with experimental results of tests carried out in two different opportunities. A mesh study was also made regarding the previously designed geometry of the same cask, in order to evaluate its impact in relation to the stability of numerical results for this type of problem. The comparison of the numerical and experimental results allowed to evaluate the need to plan and carry out a new test in order to validate the CFD codes used in the numerical simulations

  3. Transportation of radioactive materials: the legislative and regulatory information system

    International Nuclear Information System (INIS)

    Fore, C.S.

    1982-03-01

    The US Department of Energy is carrying out a national program to assure the safe shipment of radioactive materials. As part of this overall effort, the Hazardous Materials Information Center of Oak Ridge National Laboratory has developed the comprehensive Legislative and Regulatory Information System, which contains information on federal-, state-, and local-level legislative and regulatory actions pertaining primarily to the shipment of radioactive materials. Specific subject areas chosen to highlight particular transportation restrictions include: (1) identification of state agency responsible for regulating transportation, (2) type of escorts required, (3) areas requiring prior notification, (4) areas requiring permits or licenses, and (5) areas totally banning transportation of all radioactive materials. Other legislative information being categorized and of immediate relevance to the transportation issues is covered under the areas of disposal, storage, and management of radioactive materials; establishment of additional regulations; emergency response regulations; moratoriums on power plant construction and siting; radiation safety and control studies; and remedial action studies. The collected information is abstracted, indexed, and input into one of the two data bases developed under this information system - Current Legislation Data Base and Historical Legislation Data Base. An appendix is included which provides a summary of the state and local laws affecting the transportation of radioactive materials throughout the United States. The Legislative and Regulatory Information System is supported by the Transportation Technology Center located at Sandia National Laboratories, Albuquerque, New Mexico

  4. Transportation of radioactive materials: the legislative and regulatory information system

    Energy Technology Data Exchange (ETDEWEB)

    Fore, C.S.

    1982-03-01

    The US Department of Energy is carrying out a national program to assure the safe shipment of radioactive materials. As part of this overall effort, the Hazardous Materials Information Center of Oak Ridge National Laboratory has developed the comprehensive Legislative and Regulatory Information System, which contains information on federal-, state-, and local-level legislative and regulatory actions pertaining primarily to the shipment of radioactive materials. Specific subject areas chosen to highlight particular transportation restrictions include: (1) identification of state agency responsible for regulating transportation, (2) type of escorts required, (3) areas requiring prior notification, (4) areas requiring permits or licenses, and (5) areas totally banning transportation of all radioactive materials. Other legislative information being categorized and of immediate relevance to the transportation issues is covered under the areas of disposal, storage, and management of radioactive materials; establishment of additional regulations; emergency response regulations; moratoriums on power plant construction and siting; radiation safety and control studies; and remedial action studies. The collected information is abstracted, indexed, and input into one of the two data bases developed under this information system - Current Legislation Data Base and Historical Legislation Data Base. An appendix is included which provides a summary of the state and local laws affecting the transportation of radioactive materials throughout the United States. The Legislative and Regulatory Information System is supported by the Transportation Technology Center located at Sandia National Laboratories, Albuquerque, New Mexico.

  5. Relevant documents to IAEA regulations for the safe transport of radioactive materials

    International Nuclear Information System (INIS)

    El-Shinawy, R.M.K.; Sabek, M.G.; Gomma, M.

    1998-01-01

    IAEA regulations for the safe transport of radioactive materials provide standards for insuring a high level of safety of people, property, and environment against radiation, contamination, and criticality hazards as well as thermal effects associated with the transport of radioactive materials. IAEA routinely publishes technical reports which are relevant to radioactive material transportation such as INTERTRAN, directory of transport packaging test facilities, and others. A case study was performed to assess the impact of transporting radioactive materials through the suez canal using the two computer codes namely INTERTRAN and RADTRAN-4 which are part of IAEA technical documents. A comparison of the results of these two codes is given

  6. Domestic smoke detectors using radioactive material

    International Nuclear Information System (INIS)

    Anon.

    1979-02-01

    Increasing numbers of technical and consumer products incorporating radioactive material are becoming available to the Australian public. One consumer device of this type coming into common use is the domestic smoke detector that uses Americium 241 in detecting smoke. This device has obvious life-saving and property-saving advantages and is attractive in that it is attractive in that it is self-contained, battery powered and needs little maintenance. The National Health and Medical Research Council in October 1978 recommended conditions, which are listed, are intended to ensure that radiation safety is preserved. They provide for the testing and approval of all models of domestic smoke detectors using radioactive material. The National Health and Medical Research Council stated that provided these conditions are applied it had no objection to the sale of these detectors by retailers

  7. 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)

  8. Infrastructure development for radioactive materials at the NSLS-II

    Energy Technology Data Exchange (ETDEWEB)

    Sprouster, D. J.; Weidner, R.; Ghose, S. K.; Dooryhee, E.; Novakowski, T. J.; Stan, T.; Wells, P.; Almirall, N.; Odette, G. R.; Ecker, L. E.

    2018-02-01

    The X-ray Powder Diffraction (XPD) Beamline at the National Synchrotron Light Source-II is a multipurpose instrument designed for high-resolution, high-energy X-ray scattering techniques. In this article, the capabilities, opportunities and recent developments in the characterization of radioactive materials at XPD are described. The overarching goal of this work is to provide researchers access to advanced synchrotron techniques suited to the structural characterization of materials for advanced nuclear energy systems. XPD is a new beamline providing high photon flux for X-ray Diffraction, Pair Distribution Function analysis and Small Angle X-ray Scattering. The infrastructure and software described here extend the existing capabilities at XPD to accommodate radioactive materials. Such techniques will contribute crucial information to the characterization and quantification of advanced materials for nuclear energy applications. We describe the automated radioactive sample collection capabilities and recent X-ray Diffraction and Small Angle X-ray Scattering results from neutron irradiated reactor pressure vessel steels and oxide dispersion strengthened steels.

  9. Transportation accidents/incidents involving radioactive materials (1971-1991)

    International Nuclear Information System (INIS)

    Cashwell, C.E.; McClure, J.D.

    1993-01-01

    In 1981, Sandia National Laboratories developed the Radioactive Materials Incident Report (RMIR) database to support its research and development activities for the U.S. Department of Energy (DOE). The RMIR database contains information on transportation accidents/incidents with radioactive materials that have occurred since 1971. The RMIR classifies a transportation accident/incident in one of six ways: as a transportation accident, a handling accident, a reported incident, missing or stolen, cask weeping, or other. This paper will define these terms and provide detailed examples of each. (J.P.N.)

  10. 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

  11. 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.

  12. 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.

  13. 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

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

    International Nuclear Information System (INIS)

    Legoux, P.; Wangler, M.

    2004-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  16. 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

  17. 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)

  18. Device for encapsulating radioactive materials

    International Nuclear Information System (INIS)

    Suthanthiran, K.

    1994-01-01

    A capsule for encapsulating radioactive material for radiation treatment comprising two or more interfitting sleeves, wherein each sleeve comprises a closed bottom portion having a circumferential wall extending therefrom, and an open end located opposite the bottom portion. The sleeves are constructed to fit over one another to thereby establish an effectively sealed capsule container. 3 figs

  19. Natural radioactivity of building materials used in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Omar, M. [Malaysian Inst. for Nuclear Technology Research (MINT), Bangi, Kajang, Selangor D.E. (Malaysia)

    2002-03-01

    A study has been carried out to determine the natural radioactive content of building materials used in Malaysia. The materials analysed include both old and new clay bricks, cement bricks, mortar, cement, sands, ceramic tiles and gypsum. Samples of the first three materials were collected from the 12 states of the Malay Peninsula. Radium-226 (from the U-238 series) and Ra-228 (from the Th-232 series), these both representing naturally occurring radionuclides, were analysed using high-resolution HpGe gamma spectrometers. The results of our investigations showed that some old clay bricks contain high levels (at more than 5 times the normal soil concentration) of natural radionuclides, with maximum concentrations of 590 Bq/kg and 480 Bq/kg for respectively Ra-226 and Ra-228. The reasons behind this finding were not clearly understood. As there are people living in old buildings, i.e. built using old clay bricks, there is a possibility that they are being exposed to significant radiation doses. However, there proved to be no significant overall difference between old and new clay bricks in terms of the natural radioactivity levels determined, at a 95% confidence level. The overall mean concentrations of Ra-226 and Ra-228 observed in Malaysian clay bricks were respectively 118 {+-} 58 Bq/kg and 120 {+-} 42 Bq/kg. The radioactive content of other materials was found to be not much different from that to be determined in normal soil from Malaysia. The data obtained can be used as a basis for reaching decisions on the regulatory limits for radioactivity levels in building materials in Malaysia. (orig.)

  20. The physical protection of radiation sources and radioactive materials in Tanzania

    International Nuclear Information System (INIS)

    Sungita, Y.Y.; Massalu, I.

    2002-01-01

    Full text: In recognition of the legal deficiency and the awareness of radiation safety, the parliament of the United Republic of Tanzania enacted the protection from radiation act no. 5 of 1983, which established the national radiation commission (NRC) as a regulatory authority. The main objective of the act was to provide for a legal framework and guidance of the control of the use of radiation sources and radioactive materials with the view to achieve an assurance for acceptance level of radiation protection and safety standard. Due to trade liberalization that is currently experienced in the country, the increase in the number of radiation practices is observed yearly. medical diagnostic x-ray facilities constitute 72 % of all radiation installations in the country. Radioactive materials used in research, teaching and industrial application constitute 24 % and those used in therapy and nuclear medicine is 4 %. About seven radioactive materials incidents occurred in Tanzania during 1996-2000. Among these cases, some were illegal possession and across-boarder trafficking of radioactive materials. Theft and losses radioactive equipments or sources were also experienced. This presentation discusses the experienced incidents of illegal possession, theft and loss of radioactive materials and the lesson learnt from those events in connection with our operational laws. The needs for improvement of the whole system of notification, authorization, registration and licensing to cope up with increase in radiation practices and cross-border illegal trafficking of radioactive materials. The importance of involving immigration officers, police and custom officer with proper training in radiation safety aspect is emphasized. The recommendation are given in an attempt to rescue the situation. (author)

  1. Technically enhanced naturally occurring radioactive materials; identification, characterization and treatment

    International Nuclear Information System (INIS)

    Aly, H.F.

    2001-01-01

    Radioactive materials (TENORM) is produced in a relatively large amount with relatively small radioactivity, however in many instances the radioactivity levels exceeds that permissible. In this presentation, the different industries where enhanced levels of natural radioactivity is identified and characterized will be given. The different approaches for treatment of this enhanced radioactivity will be addressed. Finally, our research and development activities in characterization and treatment of TENORM produced from the oil fields in Egypt will be presented. (authors)

  2. Prevention of the inadvertent movement and illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2004-05-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  3. Prevention of the inadvertent movement and illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2004-12-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  4. Prevention of the inadvertent movement and illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2003-08-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  5. Prevention of the inadvertent movement and illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2003-05-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  6. Prevention of the inadvertent movement and illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2002-09-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  7. Radiation safety in sea transport of radioactive material in Japan

    International Nuclear Information System (INIS)

    Odano, N.; Yanagi, H.

    2004-01-01

    Radiation safety for sea transport of radioactive material in Japan has been discussed based on records of the exposed dose of sea transport workers and measured data of dose rate equivalents distribution inboard exclusive radioactive material shipping vessels. Recent surveyed records of the exposed doses of workers who engaged in sea transport operation indicate that exposed doses of transport workers are significantly low. Measured distribution of the exposed dose equivalents inboard those vessels indicates that dose rate equivalents inside those vessels are lower than levels regulated by the transport regulations of Japan. These facts clarify that radiation safety of inboard environment and handling of transport casks in sea transport of radioactive material in Japan are assured

  8. The preventing of illicit trafficking of radioactive materials in Estonia

    International Nuclear Information System (INIS)

    Velbri, T.; Aasmann, L.

    1998-01-01

    This paper explains the situation of legislation, practical border-control and equipment of different relevant authorities dealing with the control of radioactive materials in Estonia. The overview of legislation concerning radiation and radiation protection is given. The roles of Estonian Customs Authority, Estonian border Guard, National Rescue Board and Police Authority in the preventing of illicit trafficking of radioactive materials are shown. The incidents of illicit trafficking of radioactive materials are listed. Also the most important border-crossing points and the types of equipment used there are shown. Finally the problems of controlling the borders in Estonia and the future plans in order to make the controlling system more efficient are discussed. (author)

  9. Radiation safety in sea transport of radioactive material in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Odano, N. [National Maritime Research Inst., Tokyo (Japan); Yanagi, H. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

    2004-07-01

    Radiation safety for sea transport of radioactive material in Japan has been discussed based on records of the exposed dose of sea transport workers and measured data of dose rate equivalents distribution inboard exclusive radioactive material shipping vessels. Recent surveyed records of the exposed doses of workers who engaged in sea transport operation indicate that exposed doses of transport workers are significantly low. Measured distribution of the exposed dose equivalents inboard those vessels indicates that dose rate equivalents inside those vessels are lower than levels regulated by the transport regulations of Japan. These facts clarify that radiation safety of inboard environment and handling of transport casks in sea transport of radioactive material in Japan are assured.

  10. Transportation of radioactive materials - a utility view

    International Nuclear Information System (INIS)

    Futter, J.L.

    1979-01-01

    Local restrictions to transportation of radioactive materials have proliferated, and the reasons for this are described. Some of the measures which could be undertaken to counteract this trend are discussed. People should speak out on the need for nuclear power in general and for transportation of nuclear materials in particular

  11. Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

    International Nuclear Information System (INIS)

    El-Shinawy, R.M.K.

    2005-01-01

    Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other

  12. Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

    Energy Technology Data Exchange (ETDEWEB)

    El-Shinawy, R M.K. [Radiation Protection Dept., NRC, Atomic Energy Authority, Cairo (Egypt)

    2005-04-01

    Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other.

  13. Illegal handling of radioactive and nuclear materials. Threats and suggestions for measures

    International Nuclear Information System (INIS)

    Oliver, Lena; Melin, Lena; Prawitz, Jan; Ringbom, Anders; Sandstroem, Bjoern; Wigg, Lars; Wirstam, Jens

    2004-01-01

    This project deals with threats from smuggling or other illegal transportation of radioactive or nuclear materials across the borders to Sweden, and with the security of handling such materials in Sweden. The project has included studies of relevant documentation; visits and interviews at industries, hospitals, research institutes and military institutions in Sweden that handle radioactive materials; a pilot study at the Stockholm freeport, where equipment for detection of radioactive materials has been tested for six months; an analysis of incidents reported to the IAEA database; and an analysis of Swedish incidents. The following conclusions are drawn: Stricter rules regarding the physical protection of radiation sources and radioactive materials should be implemented in Sweden. The recommendations recently issued by IAEA should serve as a point of departure for working out such rules

  14. International Regulations for Transport of Radioactive Materials, History and Security

    International Nuclear Information System (INIS)

    EL-Shinawy, R.M.K.

    2013-01-01

    International Regulations for the transport of radioactive materials have been published by International Atomic Energy Agency (IAEA) since 1961. These Regulations have been widely adopted into national Regulations. Also adopted into different modal Regulations such as International Air Transport Association (IATA) and International Martime Organization (IMO). These Regulations provide standards for insuring a high level of safety of general public, transport workers, property and environment against radiation, contamination, criticality hazard and thermal effects associated with the transport of radioactive wastes and materials. Several reviews conducted in consultation with Member States (MS) and concerned international organizations, resulted in comprehensive revisions till now. Radioactive materials are generally transported by specialized transport companies and experts. Shippers and carriers have designed their transport operations to comply with these international Regulations. About 20 million consignments of radioactive materials take place around the world each year. These materials were used in different fields such as medicine, industry, agriculture, research, consumer product and electric power generation. After September 11,2001, the IAEA and MS have worked together to develop a new guidance document concerning the security in the transport of radioactive materials. IAEA have initiated activities to assist MS in addressing the need for transport security in a comprehensive manner. The security guidance and measures were mentioned and discussed. The transport security becomes more developed and integrated into national Regulations of many countries beside the safety Regulations. IAEA and other International organizations are working with MS to implement transport security programs such as guidance, training, security assessments and upgrade assistance in these fields.

  15. RADIOACTIVE MATERIALS IN BIOSOLIDS: DOSE MODELING

    Science.gov (United States)

    The Interagency Steering Committee on Radiation Standards (ISCORS) has recently completed a study of the occurrence within the United States of radioactive materials in sewage sludge and sewage incineration ash. One component of that effort was an examination of the possible tra...

  16. 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)

  17. 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)

  18. Incidents of illicit trafficking and other unauthorized activities involving nuclear and other radioactive materials (1993-2005)

    International Nuclear Information System (INIS)

    2010-01-01

    The confirmed incidents of illicit trafficking and other unauthorized activities involving nuclear and other radioactive materials between 1993-2005 shows that, 27% involved nuclear materials, 62% radioactive materials,7% involved both nuclear and other radioactive materials while the remainder involved other radioactive and non radioactive materials.Also 80% of nuclear material which was recovered during the same period was not reported as stolen or lost.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  1. Safety in transport and storage of radioactive materials

    International Nuclear Information System (INIS)

    Mezrahi, A.; Xavier, A.M.

    1987-01-01

    The increasing utilization of radioisotopes in Industrial, Medical and Research Facilities as well as the processing of Nuclear Materials involve transport activities in a routine basis. The present work has the following main objectives: I) the identification of the safety aspects related to handling, transport and storage of radioactive materials; II) the orientation of the personnel responsible for the radiological safety of Radioactive Installations viewing the elaboration and implementation of procedures to minimize accidents; III) the report of case-examples of accidents that have occured in Brazil due to non-compliance with Transport Regulations. (author) [pt

  2. Radiation doses from the transport of radioactive materials

    International Nuclear Information System (INIS)

    Shaw, K.B.; Holyoak, B.

    1983-01-01

    A summary is given of a study on radiation exposure resulting from the transport of radioactive materials within the United Kingdom. It was concluded that the transport of technetium generators for hospital use accounts for about 49% of the occupational exposure for the normal transport of radioactive materials. Other isotopes for medical and industrial use contribute about 38% of the occupational exposure and the remainder can be attributed to transportation as a result of the nuclear fuel cycle including the transport of irradiated nuclear fuel. The occupational collective dose for all modes of transport is estimated at 1 man Sv y -1 . (UK)

  3. 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

  4. Regulatory Framework and Current Practices of the Radioactive Material Safe and Secure Transport in Albania

    International Nuclear Information System (INIS)

    Dollani, K.; Grillo, B.; Telhaj, E.

    2016-01-01

    Attempts for the establishing of a safe and secure radioactive material transport in Albania began a decade ago with formulation of the different regulation in the field of safe and secure handling of the radioactive materials. In 2004 a special regulation for the safe transport of radioactive material was prepared and approved by the National Radiation Protection Commission). This regulation has been based in the IAEA standards for the radioactive material transport and was reviewed periodically. The last regulation of the radioactive material transport was approved by Albanian government through a governmental ordinance. The transport of the radioactive material in Albania is performed by licensed subjects, which fulfill all requirements of the mentioned governmental ordinance. Based in the existing regulation, for each transport of radioactive material, a special permission is issued by NRPC. The issuing of permission allows competent authority to provide necessary information on transport regularity and to have under survey all transports of the radioactive material carried out inside the country. Last year were issued more than 80 permissions for the transport of the different types and categories of the radioactive sources. (author)

  5. Estimation of radioactivity in structural materials of ETRR-1 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Imam, M [National Center for Nuclear Safety and Radiation Control Atomic Energy Authority, Cairo (Egypt)

    1997-12-31

    Precise knowledge of the thermal neutron flux in the different structural materials of a reactor is necessary to estimate the radioactive inventory in these materials that are needed in any decommissioning study of the reactor. ETRR-1 is a research reactor that went critical on 2/1691. In spite of this long age of the reactor, the effective operation time of this reactor is very short since the reactor was shutdown for long periods. Because of this long age one may think of reactor decommissioning. For this purpose, the radioactivity of the reactor structural materials was estimated. Apart from the reactor core, the important structural materials in the ETRR-1 are the reactor tank, shielding concrete, and the graphite thermal column. The thermal neutron flux was determined by the monte Carlo method in these materials and the isotope inventory and the radioactivity were calculated by the international code ORIGEN-JR. 1 fig.

  6. Ontario Hydro's transportation of radioactive material and emergency response plan

    International Nuclear Information System (INIS)

    Karmali, N.

    1993-01-01

    Ontario Hydro has been transporting radioactive material for almost 30 years without any exposure to the public or release to the environment. However, there have been three accidents involving Hydro's shipments of radioactive material. In addition to the quality packaging and shipping program, Ontario Hydro has an Emergency Response Plan and capability to deal with an accident involving a shipment of radioactive material. The Corporation's ability to respond, to effectively control and contain the situation, site remediation, and to provide emergency public information in the event of a road accident minimizes the risk to the public and the environment. This emphasizes their commitment to worker safety, public safety and impact to the environment. Response capability is mandated under various legislation and regulations in Canada

  7. Safe transport of radioactive material. Second edition

    International Nuclear Information System (INIS)

    1996-01-01

    In 1991, the International Atomic Energy Agency published Training Course Series No. 1 (TCS-1), a training manual that provides in 20 chapters a detailed discussion of the background, philosophy, technical bases and requirements and implementation aspects of the Regulations for the Safe Transport of Radioactive Material. The Transport Regulations are widely implemented by the IAEA's Member States and are also used as the bases for radioactive material transport requirements of modal organisations such as the International Maritime Organization and the International Civil Aviation Organization. This document is a supplement of TCS-1 to provide additional material in the form of learning aids and new exercises, that have been developed with the use of TCS-1 at succeeding IAEA training courses. The learning aids in the first part of the supplement are hitherto unpublished material that provide detailed guidance useful in solving the exercises presented in the second part. Solutions to the exercises are on field at the IAEA Secretariat and are available by arrangement to lectures presenting IAEA training courses. 4 refs, 1 fig., 6 tabs

  8. Assessment of radioactivity in building material(granite) in Sudan

    International Nuclear Information System (INIS)

    Osman, Z. A; Salih, I; Albadwai, K. A; Salih, A. M; Salih, S. A.

    2016-01-01

    In the present work radioactivity in building materials (granite) central Sudan was evaluated. In general the building materials used in Sudan are derived either from rocks or soil. These contain trace amounts of naturally occurring radioactive materials(NORMs), so it contains radionuclides from uranium and thorium series and natural potassium. The levels of these radionuclides vary according to the geology of their site of origin. High levels increase the risk of radiation exposure in homes(especially exposure due to radon). Investigation of radioactivity in granite used of the building materials in Sudan is carried out, a total of 18 major samples of granite have been collected and measured using X- ray fluorescence system (30 mci). The activity concentrations have been determined for uranium ("2"3"8U), thorium ('2"3"2Th) and potassium("4"0K) in each sample. The concentrations of uranium have been found to range from 14.81 Bq/kg to 24.572 Bq/kg, thorium between 10.02 Bq/kg and 10.020-84.79 Bq/kg and the potassium concentration varies between 13.33 Bq/kg to 82.13 Bq/kg. Limits of radioactivity in the granite are based on dose criteria for controls. This study can be used as a reference for more extensive studies of the same subject in future. (Author)

  9. RADTRAN3, Risk of Radioactive Material Transport

    International Nuclear Information System (INIS)

    Madsen, M.M.; Taylor, J.M.; Ostmeyer, R.M.; Reardon, P.C.

    2001-01-01

    1 - Description of program or function: RADTRAN3 is a flexible analytical tool for calculating both the incident-free and accident impacts of transporting radioactive materials. The consequences from incident-free shipments are apportioned among eight population sub- groups and can be calculated for several transport modes. The radiological accident risk (probability times consequence summed over all postulated accidents) is calculated in terms of early fatalities, early morbidities, latent cancer fatalities, genetic effects, and economic impacts. Ground-shine, ingestion, inhalation, direct exposure, resuspension, and cloud-shine dose pathways are modeled to calculate the radiological health risks from accidents. Economic impacts are evaluated based on costs for emergency response, cleanup, evacuation, income loss, and land use. RADTRAN3 can be applied to specific scenario evaluations (individual transport modes or specified combinations), to compare alternative modes or to evaluate generic radioactive material shipments. Unit-risk factors can easily be evaluated to aid in performing generic analyses when several options must be compared with the amount of travel as the only variable. RADTRAN4 offers advances in the handling of route-related data and in the treatment of multiple-isotope materials. 2 - Method of solution: There are several modes used in the transporting of radioactive material such as trucks, passenger vans, passenger airplanes, rail and others. With these modes of transport come several shipment scenarios. The RADTRAN4 methodology uses material, transportation, population distribution, and health effects models to treat the incident-free case. To handle the vehicle accident impacts, accident severity and package release, meteorological dispersion, and economic models are also employed. 3 - Restrictions on the complexity of the problem: There are no apparent limitations due to programming dimensions

  10. Discrimination of Naturally Occurring Radioactive Material in Plastic Scintillator Material

    International Nuclear Information System (INIS)

    Ely, James H.; Kouzes, Richard T.; Geelhood, Bruce D.; Schweppe, John E.; Warner, Ray A.

    2003-01-01

    Plastic scintillator material is used in many applications for the detection of gamma-rays from radioactive material, primarily due to the sensitivity per unit cost compared to other detection materials. However, the resolution and lack of full-energy peaks in the plastic scintillator material prohibits detailed spectroscopy. Therefore, other materials such as doped sodium iodide are used for spectroscopic applications. The limited spectroscopic information can however be exploited in plastic scintillator materials to provide some discrimination. The discrimination between man-made and naturally occurring sources would be useful in reducing alarm screening for radiation detection applications which target man-made sources. The results of applying the limited energy information from plastic scintillator material for radiation portal monitors are discussed.

  11. The transport of radioactive materials - Future challenges

    International Nuclear Information System (INIS)

    Wilkinson, W.L.

    2008-01-01

    The International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Materials, TS-R-1, set the standards for the packages used in the transport of radioactive materials under both normal and accident conditions. Transport organisations are also required to implement Radiation Protection Programmes to control radiation dose exposure to both workers and the public. The industry has now operated under this regulatory regime safely and efficiently for nearly 50 years. It is vital that this record be maintained in the future when the demands on the transport industry are increasing. Nuclear power is being called upon more and more to satisfy the world's growing need for sustainable, clean and affordable electricity and there will be a corresponding demand for nuclear fuel cycle services. There will also be a growing need for other radioactive materials, notably large sources such as Cobalt 60 sources for a range of important medical and industrial uses, as well as radio-pharmaceuticals. A reliable transport infrastructure is essential to support all these industry sectors and the challenge will be to ensure that this can be maintained safely and securely in a changing world where public and political concerns are increasing. This paper will discuss the main issues which need to be addressed. The demand for uranium has led to increased exploration and the development of mines in new locations far removed from the demand centres. This inevitably leads to more transport, sometimes from areas potentially lacking in transport infrastructure, service providers, and experience. The demand for sources for medical applications will also increase, particularly from the rapidly developing regions and this will also involve new transport routes and increased traffic. This raises a variety of issues concerning the ability of the transport infrastructure to meet the future challenge, particularly in an environment where there already exists reluctance on

  12. Status of the Regulation for safe and secure transport of radioactive materials in Madagascar

    International Nuclear Information System (INIS)

    Raoelina Andriambololona; Zafimanjato, J.L.R.; Solofoarisina, W.C.; Randriantseheno, H.F.

    2011-01-01

    Radioactive sources are widely used in medicine, in industrial exploration and development, as well as in basic scientific research and education in Madagascar. The ability to use such radioactive materials in these sectors depends on their safe and secure transport both within and between countries. Transport safety of radioactive materials within the country is regulated. The law No. 97-041 on radiation protection and radioactive waste management in Madagascar promulgated in January 1998 and the decree No.2735/94 dealing the transport of radioactive materials promulgated in June 1994 govern all activities related to the transport of radioactive material. This law was established to meet the requirements of the International Basic Safety Standards (BSS, IAEA Safety Series 115). It is not fully consistent with current international standards (GS-R-1). Indeed, in order to enhance the security of radioactive sources, Madagascar has implemented the Code of Conduct and the Guidance on the Import and Export of Radioactive Sources. Faced with delays and denials of shipment of radioactive materials issues, the National Focal Point has been appointed to work with ISC members and the regional networks on the global basis.

  13. Status of the regulation for safe and secure transport of radioactive materials in Madagascar

    International Nuclear Information System (INIS)

    Andriambololona, Raoelina; Zafimanjato, J.L.R.; Solofoarisina, W.C.; Randriantseheno, H.F.

    2016-01-01

    Radioactive sources are widely used in medicine, in industrial exploration and development, as well as in basic scientific research and education in Madagascar. The ability to use such radioactive materials in these sectors depends on their safe and secure transport both within and between countries. Transport safety of radioactive materials within the country is regulated. The law n° 97-041 on radiation protection and radioactive waste management in Madagascar promulgated in January 1998 and the decree n° 2735/94 dealing the transport of radioactive materials promulgated in June 1994 govern all activities related to the transport of radioactive material. This law was established to meet the requirements of the International Basic Safety Standards (BSS, IAEA Safety Series 115). It is not fully consistent with current international standards (GS-R-1). Indeed, in order to enhance the security of radioactive sources, Madagascar has implemented the Code of Conduct and the Guidance on the Import and Export of Radioactive Sources. Faced with delays and denials of shipment of radioactive materials issues, the National Focal Point has been appointed to work with ISC members and the regional networks on the global basis. (author)

  14. Identification of tetraphenylborate radiolysis products in a simulated feedstock for radioactive waste processing

    International Nuclear Information System (INIS)

    Eibling, R.E.; Bartlett, M.G.; Carlson, R.E.; Testino, S.A. Jr.; Kunkel, G.J.; Browner, R.F.; Busch, K.L.

    1994-01-01

    The first step towards immobilization of the soluble radioactive species in borosilicate glass is the addition of sodium tetraphenylborate (TPB) and sodium titanate to the radioactive aqueous solution. Initial studies of the TPB hydrolysis process have found that some component of the radiolysis mixture inactivates the Cu catalyst. The interaction of organic materials with the catalyst, and the subsequent interference with the hydrolysis process, would have presented problems with the use of the vitrification process. Prevention of the catalyst deactivation is obtained by washing the irradiated TPB precipitate in the Late Wash Facility prior to hydrolysis to remove the soluble radiolysis products. Identification of the organic radiolysis products, their distribution in the Late Wash Facility, and their interactions with the Cu catalyst has become an important analytical issue. To further investigate the reaction products of the TPB precipitation process, a simulated feedstock was created from compounds known to be present in the starting materials. This simulated feedstock was precipitated with sodium TPB and then exposed to Co-60 gamma radiation to simulate two years of additional storage time prior to the hydrolysis process. The irradiated product was divided into two parts, the filtered supernatant liquid and the precipitate slurry, which contains the TPB and the solid sodium titanate. Using gas chromatography/mass spectrometry, liquid secondary ion mass spectrometry, inductively coupled plasma/mass spectrometry, ion chromatography, and high performance liquid chromatography, over 50 organic and inorganic species have been identified in the aqueous portion of a simulated feedstock for TPB hydrolysis. The major organic species present are benzene, phenol, benzamide and a variety of substituted phenylphenols. The major inorganic species present are sodium, nitrite, and oxalate ions

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

    International Nuclear Information System (INIS)

    Cao Fangfang; Que Ji; Zhang Min; Pan Yuting

    2012-01-01

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

  16. Transport of radioactive materials

    International Nuclear Information System (INIS)

    Hamel, P.E.

    In Canada, large numbers of packages containing radioactive materials are shipped for industrial, medical and commercial purposes. The nature of the hazards and the associated risks are examined; the protection measures and regulatory requirements are indicated. The result of a survey on the number of packages being shipped is presented; a number of incidents are analyzed as a function of their consequences. Measures to be applied in the event of an emergency and the responsibility for the preparation of contingency plans are considered. (author) [fr

  17. Radiation surveys of radioactive material shipments

    International Nuclear Information System (INIS)

    Howell, W.P.

    1986-07-01

    Although contractors function under the guidance of the Department of Energy, there is often substantial variation in the methods and techniques utilized in making radiation measurements. When radioactive materials are shipped from one contractor to another, the measurements recorded on the shipping papers may vary significantly from those measured by the receiver and has been a frequent cause of controversy between contractors. Although significant variances occur in both measurements of radiation fields emanating from shipment containers and measurements of residual radioactivity on the surfaces of the containers, the latter have been the most troublesome. This report describes the measurement of contamination on the exterior surfaces of shipment containers

  18. Quality assurance for the safe transport of radioactive material

    International Nuclear Information System (INIS)

    1994-01-01

    All activities related to the safe transport of radioactive material should be covered by a quality assurance programme. This publication recognizes that a single transport operation often involves several different organizations, each having specific responsibilities. Hence, it is unlikely that the operation will be covered by a single quality assurance programme. Each quality assurance programme should be tailored to the specific organizational structure for which the programme is prepared, with account taken of the particular transport activities of that organization and the interfaces with other organizations. The aim of this publication is to give a detailed interpretation of what must be done by whom to produce a quality assurance programme for radioactive material transport. This publication provides guidance on methods and practical examples to develop QA programmes for the safe transport of radioactive material. It provides information on how to develop the programme, the standards and the common features of a QA programme

  19. Need to increase public awareness of the safety of radioactive materials transport

    International Nuclear Information System (INIS)

    Bishop, R.W.

    1983-01-01

    There are two aspects to the problem of the public perception of radioactive materials transport: the first is a lack of knowledge on the part of the public about the facts, and the second is the distorted presentation by the media. These two problems are obviously interrelated - the more unaware the public is of the actual safety of radioactive materials transport, the more it is likely to be influenced, and frightened, by inaccurate reporting. The obvious question is, what can we as an industry do to educate the public and to facilitate more neutral reporting about the facts involving radioactive materials transport. This question is answered by describing an excellent example of a situation where the industry acted cohesively and effectively to respond to fallacious allegations concerning the safety of the transportation of radioactive materials

  20. US perspective of transporting radioactive materials by sea

    International Nuclear Information System (INIS)

    Chitwood, R.B.

    1978-01-01

    The reason for the US interest in transportation of radioactive materials by sea is discussed. The national and international institutional considerations related to this subject are covered. Some economic aspects in transporting these materials, particularly spent fuels, by sea are also presented

  1. Natural radioactivity in building materials in Iran

    International Nuclear Information System (INIS)

    Mehdizadeh, S.; Faghihi, R.; Sina, S.

    2011-01-01

    This work presents a comprehensive study of natural radioactivity in building materials used in Iran. For this purpose, 177 samples of five types of building material, i.e. cement, gypsum, cement blocks, gravel and brick, were gathered from different regions of the country and analyzed by gamma spectroscopy to quantify radioactivity concentrations using a high purity germanium (HPGe) detector and a spectroscopy system. According to the results of this investigation, cement samples had maximum values of the mean Ra-226 and Th-232 concentrations, 39.6 and 28.9 Bq/kg, respectively, while the lowest value for mean concentration of these two radionuclides were found in gypsum samples 8.1 and 2.2 Bq/kg, respectively. The highest (851.4 Bq/kg) and lowest (116.2 Bq/kg) value of K-40 mean concentration were found in brick and gypsum samples, respectively. The absorbed dose rate and the annual effective dose were also calculated from the radioactivity content of the radionuclides. The results show that the maximum values of dose rate and annual effective dose equivalent were 53.72 nGy/h and 0.37 mSv/y in brick samples. The radium equivalent activities R eq calculated were below the permissible level of 370 Bq/kg for all building materials. The values of hazard indexes were below the recommended levels, therefore, it is concluded that the buildings constructed from such materials are safe for the inhabitants. The results of this study are consistent with the results of other investigations in different parts of the world. (authors)

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  3. National inventory of radioactive wastes and valorizable materials. Synthesis report

    International Nuclear Information System (INIS)

    2004-01-01

    This national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. It contains: 1 - general introduction; 2 - the radioactive wastes: definition, classification, origin and management; 3 - methodology of the inventory: organization, accounting, prospective, production forecasting, recording of valorizable materials, exhaustiveness, verification tools; 4 - general results: radioactive waste stocks recorded until December 31, 2002, forecasts for the 2003-2020 era, post-2020 prospects: dismantling operations, recording of valorizable materials; 5 - inventory per producer or owner: front-end fuel cycle facilities, power generation nuclear centers, back-end fuel cycle facilities, waste processing or maintenance facilities, civil CEA research centers, non-CEA research centers, medical activities (diagnostics, therapeutics, analyses), various industrial activities (sources fabrication, control, particular devices), military research and experiment centers, storage and disposal facilities; 6 - elements about radioactive polluted sites; 7 - examples of foreign inventories; 8 - conclusion and appendixes. (J.S.)

  4. 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

  5. Radioactive material in the West Lake Landfill: Summary report

    International Nuclear Information System (INIS)

    1988-06-01

    The West Lake Landfill is located near the city of St. Louis in Bridgeton, St. Louis County, Missouri. The site has been used since 1962 for disposing of municipal refuse, industrial solid and liquid wastes, and construction demolition debris. This report summarizes the circumstances of the radioactive material in the West Lake Landfill. The radioactive material resulted from the processing of uranium ores and the subsequent by the AEC of processing residues. Primary emphasis is on the radiological environmental aspects as they relate to potential disposition of the material. It is concluded that remedial action is called for. 8 refs., 2 figs., 1 tab

  6. Radiation protection programmes for the transport of radioactive material. Safety guide

    International Nuclear Information System (INIS)

    2007-01-01

    This Safety Guide provides guidance on meeting the requirements for the establishment of radiation protection programmes (RPPs) for the transport of radioactive material, to optimize radiation protection in order to meet the requirements for radiation protection that underlie the Regulations for the Safe Transport of Radioactive Material. This Guide covers general aspects of meeting the requirements for radiation protection, but does not cover criticality safety or other possible hazardous properties of radioactive material. The annexes of this Guide include examples of RPPs, relevant excerpts from the Transport Regulations, examples of total dose per transport index handled, a checklist for road transport, specific segregation distances and emergency instructions for vehicle operators

  7. International dimension of illicit trafficking in nuclear and other radioactive material

    International Nuclear Information System (INIS)

    Zaitseva, L.; Bunn, G.; Steinhaeusler, F.

    2002-01-01

    Full text: Illicit trafficking in nuclear and other radioactive material is primarily associated with Russia and other former Soviet republics. Indeed, with the collapse of the former Soviet Union (FSU) in 1991, hundreds of tons of weapons-usable nuclear material and thousands of radiation sources were left without adequate control and protection, thus posing a risk for sabotage, theft and diversion. Out of 700 illicit trafficking incidents recorded in the Stanford's database on nuclear smuggling, theft and orphan radiation sources (DSTO), over 450 either took place in the former Soviet Union or involved material that had reportedly originated from the FSU. In the period 1992-1994, Western and Eastern Europe were heavily affected by the inflow of nuclear material smuggled from the FSU. Since then, various measures were taken by the European countries and former Soviet republics to prevent the trafficking of radioactive substances ranging from the improvement of physical security at nuclear facilities to the installation of detection equipment at international borders. However, although the number of illicit trafficking incidents in Western Europe has decreased dramatically since 1994 and the overall annual number of such cases has been lower than in 1994, evidence suggests that diverted nuclear material is still being smuggled out of the FSU. An increased number of interceptions of nuclear and other radioactive material in the Caucasus, Turkey and Central Asia, well-known for their drugs and arms smuggling routes, over the past three years demonstrates that the material may now be moving south rather than west. This is particularly alarming considering the proximity of three countries to the potential end-users of nuclear and other radioactive material, such as AI Qaida terrorist network and aspiring nuclear weapon states in the Middle East. Although the FSU remains the major potential source of nuclear and other radioactive material, it is not the only one. Thefts

  8. 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.

  9. Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

    International Nuclear Information System (INIS)

    Gillard, J.E.

    2001-01-01

    Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

  10. Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

    Energy Technology Data Exchange (ETDEWEB)

    Gillard, J.E

    2001-07-01

    Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

  11. DISPERSION AND SORPTION CHARACTERISTICS OF URANIUM IN THE ZEOLITE-QUARTZ MIXTURE AS BACKFILL MATERIAL IN THE RADIOACTIVE WASTE REPOSITORY

    Directory of Open Access Journals (Sweden)

    Herry Poernomo

    2010-06-01

    Full Text Available The experiment of sorption and dispersion characteristics of uranium in the zeolite-quartz mixture as candidate of raw material of backfill material in the radioactive waste repository has been performed. The objective is to know the effect of zeolite and quartz grain size on the zeolite-to-quartz weight ratio that gives porosity (ε, permeability (K, and dispersivity (α of uranium in the zeolite-quartz mixture as backfill material. The experiment was carried out by fixed bed method in the column filled by the zeolite-quartz mixture with zeolite-to-quartz weight percent ratio of 100/0, 80/20, 60/40, 40/60, 20/80, 0/100 wt. % in the water saturated condition flowed by uranyl nitrate solution of 500 ppm concentration (Co as uranium simulation which was leached from immobilized radioactive waste in the repository. The concentration of uranium in the effluents represented as Ct were analyzed by spectrophotometer Corning Colorimeter 253 every 15 minutes, then using Co and Ct uranium dispersivity (α in the backfill material was determined. The experiment data shown that 0.196 mm particle size of zeolite and 0.116 mm particle size of quartz on the zeolite-to-quartz weight ratio of 60/40 wt. % with ε = 0.678, K = 3.345x10-4 cm/second, and α = 0.759 cm can be proposed as candidate of raw material of backfill material in the radioactive waste repository.   Keywords: backfill material, quartz, radioactive waste, zeolite

  12. Radioactive materials system of the ININ (SMATRAD)

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  13. Scientific capabilities of the advanced light source for radioactive materials

    International Nuclear Information System (INIS)

    Shuh, D.K.

    2007-01-01

    The Advanced Light Source (ALS) of Lawrence Berkeley National Laboratory (LBNL) is a third-generation synchrotron radiation light source and is a U.S. Department of Energy (DOE) national user facility. Currently, the ALS has approximately forty-five operational beamlines spanning a spectrum of scientific disciplines, and provides scientific opportunities for more than 2 000 users a year. Access to the resources of the ALS is through a competitive proposal mechanism within the general user program. Several ALS beamlines are currently being employed for a range of radioactive materials investigations. These experiments are reviewed individually relying on a graded hazard approach implemented by the ALS in conjunction with the LBNL Environmental, Health, and Safety (EH and S) Radiation Protection Program. The ALS provides radiological work authorization and radiological control technician support and assistance for accepted user experimental programs. LBNL has several radioactive laboratory facilities located near the ALS that provide support for ALS users performing experiments with radioactive materials. The capabilities of the ALS beamlines for investigating radioactive materials are given and examples of several past studies are summarised. (author)

  14. IAEA regulatory initiatives for the air transport of large quantities of radioactive materials

    International Nuclear Information System (INIS)

    Luna, R.E.; Wangler, M.W.; Selling, H.A.

    1992-01-01

    The International Atomic Energy Agency (IAEA) has been laboring since 1988 over a far reaching change to its model regulations (IAEA, 1990) for the transport of radioactive materials (RAM). This change could impact the manner in which certain classes of radioactive materials are shipped by air and change some of the basic tenets of radioactive material transport regulations around the world. This report discusses issues associated with air transport regulations

  15. Regulations for the safe transport of radioactive material. 1996 ed.

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is the revised version of the IAEA's Regulations for the Safe Transport of Radioactive Materials as approved by the Board of Governors in September 1996. It establishes standards of safety which provide an acceptable level of control of the radiation, criticality and thermal hazards to persons, property and the environment that are associated with the transport of radioactive material. After an introductory section, the publication is structured as follows: Section 2 defines the terms that are required for the purposes of the Regulations; Section 3 provides general provisions; Section 4 gives the activity limits and material restrictions used throughout these Regulations; Section 5 provides requirements and controls for transport; Section 6 provides requirements for radioactive materials and for packagings and packages; Section 7 provides requirements for test procedures; Section 8 provides approval and administrative requirements. The requirements for the transport of specified types of consignments are included in an abbreviated form as Schedules. Refs, figs, tabs

  16. Specialized equipment needs for the transportation of radioactive material

    International Nuclear Information System (INIS)

    Condrey, D.; Lambert, M.

    1998-01-01

    To ensure the safe and reliable transportation of radioactive materials and components, from both the front and back-end of the nuclear fuel cycle, a transport management company needs three key elements: specialized knowledge, training and specialized equipment. These three elements result, in part, from national and international regulations which require specialized handling of all radioactive shipments. While the reasons behind the first two elements are readily apparent, the role of specialized equipment is often not considered until too late shipment process even though it plays an integral part of any radioactive material transport. This paper will describe the specialized equipment needed to transport three of the major commodities comprising the bulk of international nuclear transports: natural uranium (UF6), low enriched uranium (UF6) and fresh nuclear fuel. (authors)

  17. Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This Safety Guide provides guidance on various aspects of emergency planning and preparedness for dealing effectively and safely with transport accidents involving radioactive material, including the assignment of responsibilities. It reflects the requirements specified in Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, and those of Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Framework for planning and preparing for response to accidents in the transport of radioactive material; 3. Responsibilities for planning and preparing for response to accidents in the transport of radioactive material; 4. Planning for response to accidents in the transport of radioactive material; 5. Preparing for response to accidents in the transport of radioactive material; Appendix I: Features of the transport regulations influencing emergency response to transport accidents; Appendix II: Preliminary emergency response reference matrix; Appendix III: Guide to suitable instrumentation; Appendix IV: Overview of emergency management for a transport accident involving radioactive material; Appendix V: Examples of response to transport accidents; Appendix VI: Example equipment kit for a radiation protection team; Annex I: Example of guidance on emergency response to carriers; Annex II: Emergency response guide.

  18. The projected relative index of consequence equivalence of transport of radioactive materials

    International Nuclear Information System (INIS)

    Nandakumar, A.N.

    1999-01-01

    The need exists for defining a unit risk factor to enable analysis to make a proper decision when faced with many options relating to the transport of radioactive materials between sites. A method is discussed for deriving such a factor with reference to the collective dose receivable due to the transport of radioactive material incidental to the production of one GWe.a of nuclear power. This quantity would enable the analyst to determine the projected relative index of consequence equivalence (PRICE) for the transport of various types of radioactive materials. (author)

  19. Radioactive material defense construction using wind fan system against nuclear fallout in the aspect of nano-scopic dispersion

    International Nuclear Information System (INIS)

    Woo, Tae Ho

    2012-01-01

    Highlights: ► A realistic radiation protection system using aerodynamics is suggested. ► Manual formation procedure is constructed by this modeling. ► Chemical and natural accidents by wind fan are applicable. ► Nuclear disaster is avoided by national defense system. ► A sample case is realistically modeled. -- Abstract: Radioactive fallout defense system (RFDS) is suggested against possible nuclear accidents. A procedure consisting of several stages is considered. In particular, the dispersion of radioactive material is investigated for the case of wind fan operation where the radioactive molecules are considered as nano-scopic material. The modeling is done for one country dealing with a possible nuclear accident in another country. This study is thus applicable to regions where westerlies are prevailing. An aerodynamic fan analysis is performed. The incoming free wind stream is characterized by random sampling in Monte-Carlo simulation. The velocity of the fan is a critical aspect of the model. This model is applicable for volcanic ashes, nuclear bomb fallout, chemical material dispersion, and any other material combined with airflow. In addition, this fan could be studied, with nano-scale considerations, by a multi-scale technique.

  20. 2009 National inventory of radioactive material and wastes. In short

    International Nuclear Information System (INIS)

    2009-01-01

    This booklet gives a summary of the national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). Intended for public information, the booklet explains the basics of radioactive materials and wastes and waste management, and gives some data on present and future waste volumes, information about radioactive waste classification, the geographical distribution of waste sites in France, etc. The various types of radioactive wastes are described (classified by their lifetime and activity level) as well as historical storage sites, polluted areas where wastes are stored, radioactive objects, etc. and their respective management approaches are presented

  1. IAEA mode-related research in the safe transport of radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Blalock, L.G.; Rawl, R.R. [International Atomic Energy Agency, IAEA, Vienna (Austria)

    1998-07-01

    The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

  2. IAEA mode-related research in the safe transport of radioactive material

    International Nuclear Information System (INIS)

    Blalock, L.G.; Rawl, R.R.

    1998-01-01

    The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

  3. Regulations for the safe transport of radioactive materials. 1973 rev. ed

    International Nuclear Information System (INIS)

    1973-01-01

    The purpose of these Regulations is to establish standards of safety which provide an acceptable level of control of the radiation hazards to persons, property and the environment that are associated with the transport of radioactive material. These Regulations shall apply to the transport by land, water or air, including transport on own account, of radioactive material other than that which is an integral part of the means of transport. Transport shall be deemed to include any operation incidental to the whole course of carriage, such as loading, unloading and storage in transit. The term includes both normal transport and that under accident conditions. These Regulations do not apply within establishments where the radioactive material is produced, used or stored, other than in the course of transport, and in respect of which other appropriate safety regulations are in force. In the transport of radioactive materials, any other hazardous characteristics of these materials such as explosiveness, inflammability, pyrophoricity, chemical toxicity, and corrosiveness must be taken into account in such a manner as to be in compliance with the relevant transport regulations for dangerous goods of each of the countries through or into which the materials will be transported, as well as in compliance with these Regulations.

  4. Assessment of Transportation Risk of Radioactive Materials in Uganda

    International Nuclear Information System (INIS)

    Richard, Menya; Kim, Jonghyun

    2014-01-01

    Radioactive materials refer to any materials that spontaneously emit ionizing radiation and of which the radioactivity per gram is greater than 0.002 micro-curie. They include: spent nuclear fuel, nuclear wastes, medical sources i.e. Co-60, industrial sources i.e. Cs-137, Am-241:Be, Ra-226, and sources for research. In view of the rising reported cancer cases in Uganda, which might be as a result of radiation exposure due to constant transportation of radioactive materials i.e. industrial sources, a risk analysis was thought of and undertaken for the country's safety evaluation and improvement. It was therefore important to undertake a risk assessment of the actual and potential radiation exposure during the transportation process. This paper explains a study undertaken for transport risk assessment of the impact on the environment and the people living in it, from exposure to radioactivity during transportation of the industrial sources in Uganda. It provides estimates of radiological risks associated with visualized transport scenarios for the highway transport mode. This is done by calculating the human health impact and radiological risk from transportation of the sources along Busia transport route to Hoima. Busia is the entry port for the sources whilst Hoima, where various industrial practices that utilize sources like oil explorations are centered. During the study, a computer code RADTRAN-6 was used. The overall collective dose for population and package transport crew are 3.72E-4 and 1.69E-4 person-sievert respectively. These are less than the exemption value recommended by the IAEA and Uganda Regulatory Authority for public implying that no health effects like cancer are to be expected. Hence the rising cancer cases in the country are not as a result of increased transportation of radioactive materials in the Industrial sector

  5. Assessment of Transportation Risk of Radioactive Materials in Uganda

    Energy Technology Data Exchange (ETDEWEB)

    Richard, Menya; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    Radioactive materials refer to any materials that spontaneously emit ionizing radiation and of which the radioactivity per gram is greater than 0.002 micro-curie. They include: spent nuclear fuel, nuclear wastes, medical sources i.e. Co-60, industrial sources i.e. Cs-137, Am-241:Be, Ra-226, and sources for research. In view of the rising reported cancer cases in Uganda, which might be as a result of radiation exposure due to constant transportation of radioactive materials i.e. industrial sources, a risk analysis was thought of and undertaken for the country's safety evaluation and improvement. It was therefore important to undertake a risk assessment of the actual and potential radiation exposure during the transportation process. This paper explains a study undertaken for transport risk assessment of the impact on the environment and the people living in it, from exposure to radioactivity during transportation of the industrial sources in Uganda. It provides estimates of radiological risks associated with visualized transport scenarios for the highway transport mode. This is done by calculating the human health impact and radiological risk from transportation of the sources along Busia transport route to Hoima. Busia is the entry port for the sources whilst Hoima, where various industrial practices that utilize sources like oil explorations are centered. During the study, a computer code RADTRAN-6 was used. The overall collective dose for population and package transport crew are 3.72E-4 and 1.69E-4 person-sievert respectively. These are less than the exemption value recommended by the IAEA and Uganda Regulatory Authority for public implying that no health effects like cancer are to be expected. Hence the rising cancer cases in the country are not as a result of increased transportation of radioactive materials in the Industrial sector.

  6. Remote detection of radioactive material using high-power pulsed electromagnetic radiation.

    Science.gov (United States)

    Kim, Dongsung; Yu, Dongho; Sawant, Ashwini; Choe, Mun Seok; Lee, Ingeun; Kim, Sung Gug; Choi, EunMi

    2017-05-09

    Remote detection of radioactive materials is impossible when the measurement location is far from the radioactive source such that the leakage of high-energy photons or electrons from the source cannot be measured. Current technologies are less effective in this respect because they only allow the detection at distances to which the high-energy photons or electrons can reach the detector. Here we demonstrate an experimental method for remote detection of radioactive materials by inducing plasma breakdown with the high-power pulsed electromagnetic waves. Measurements of the plasma formation time and its dispersion lead to enhanced detection sensitivity compared to the theoretically predicted one based only on the plasma on and off phenomena. We show that lower power of the incident electromagnetic wave is sufficient for plasma breakdown in atmospheric-pressure air and the elimination of the statistical distribution is possible in the presence of radioactive material.

  7. Radioactive materials packaging standards and regulations: Making sense of it all

    International Nuclear Information System (INIS)

    Pope, R.B.; Rawl, R.R.

    1989-01-01

    Numerous regulations and standards, both national and international, apply to the packaging and transportation of radioactive material. These are legal and technical prerequisites to practically every action that a designer or user of a radioactive material transportation package will perform. The identity and applicability of these requirements and the bodies that formulate them are also not readily understood. This paper addresses the roles that various international bodies play in developing and implementing the various regulations and standards. It uses the US regulatory and standards-making bodies to illustrate how international requirements feed the domestic control of packaging and transport. It explains the scope and interactions between domestic and international regulatory and standards agencies and summarizes the status and major standards activities at the international level. The overview provided by this paper will be valuable to designers and users of radioactive material packages for better understanding and use of both standards and regulations, and for complying with regulatory requirements in the radioactive materials transportation field. 11 refs., 2 figs

  8. Safety and security of radioactive materials - The Indian scenario

    International Nuclear Information System (INIS)

    Kumar, A.; Agarwal, S.P.; Tripathi, U.B.; Murthy, B.K.S.; Bhatt, B.C.

    2001-01-01

    There has been a phenomenal increase in the use of radiation sources in diverse fields such as medicine, industry, agriculture, research and teaching in India and elsewhere. Though the radiation safety record in these applications has been good, there have been a few incidents/accidents during transport/use of radioactive materials. Current status and various aspects of regulatory control to ensure safety and security of radioactive material including incidents of missing/orphan sources in India are discussed in this paper. Regulatory Infrastructure: Government of India enacted the Atomic Energy Act in 1962 to provide a regulatory infrastructure for control and use of radioactive materials and radiation sources. Radiation Protection Rules, 1971, were promulgated under this Act and Chairman, Atomic Energy Regulatory Board (AERB) was appointed as the Competent Authority to enforce these rules. Radiological Physics and Advisory Division (RP and AD) of Bhabha Atomic Research Centre provides technical and executive support to AERB in implementation of the regulations in the non-nuclear applications of radiation. Under the Rules, the Competent Authority has notified the surveillance procedures for various applications. Various codes and guides on regulatory procedures relating to specific applications of radioactive material have also been issued by the Competent Authority. As per the regulatory procedures, each practice and source requires specific authorisation. The pre-requisites for the procurement of radioactive material for various applications are: (a) Approved source and equipment, (b) Approved installation, (c) Provision of an exclusive safe and secure storage facility for radioactive material when not in use or pending installation, (d) Trained manpower duly approved by the competent authority, (e) Radiation monitoring devices (area and personnel), (f) Emergency preparedness and (g) Commitment from the licensee for safe disposal of disused/decayed sources. In

  9. Natural radioactivity of building materials

    International Nuclear Information System (INIS)

    Mrnustik, J.

    1988-01-01

    Within a study of the natural radioactivity of building materials, coefficients were determined of the emanation from selected materials and raw materials, such as porous concrete, bricks, marlite, quartzite, etc. Measurements were made of ground samples using Lucas scintillation chambers which give an accuracy of determination of the coefficient of about 10%. Specific radium activity was also determined for the samples. Tabulated is a comparison of the average specific activity of radium in concrete, power plant ash and porous concrete in Czechoslovakia and abroad. It is stated that monitoring the content of natural radionuclides in building materials is an indispensable part of the production process in the building industry, this with regard to the radiation protection of the population. This will be enhanced by the new Czechoslovak standard determining methods of measuring the content of natural radionuclides and the coefficient of radon emanation, and the subsequent evaluation of the properties of building materials. (Z.M.) 3 figs., 3 tabs

  10. Determination of radioactivity levels from some Egyptian building materials

    International Nuclear Information System (INIS)

    Abd EL Sattar, M.; Morsy, A.A.

    2007-01-01

    Our world is radioactive and has been, since it was created. Over 60 radionuclides (radioactive elements) can be found in nature. Radon is naturally occurring radioactive gas, that is produced by the radioactive decay of radium. Breathing high concentration of radon can cause lung cancer. A set of experiments were carried out using Cr-39 as solid state nuclear track detectors with the optimum etching conditions, 6.25 N Na OH at 70 o C for 8 hours. The radon-222 activity in this survey was found to be in the range of 0.303 kBq/m 3 to 5.04 KBq/m 3 for different building materials in Egypt

  11. United States experience in the transportation of radioactive materials

    International Nuclear Information System (INIS)

    Platt, A.M.; Rhoads, R.E.; Hall, R.J.; Williams, L.D.; Brobst, W.A.; Shappert, L.B.; Jefferson, R.M.

    1977-01-01

    The transport of radioactive material forms a vital link in the nuclear fuel cycle in the United States. Actual U.S. experience and practice with such systems for the packaging and transport of uranium ore concentrates, uranium hexafluoride, fresh fuel, irradiated fuel, non-high-level waste, and plutonium with low heat generation rates are described. Specific shipping systems in current use for these services are illustrated. A comparison will be made of shipping requirements for nuclear parks versus dispersed facilities. Shipping systems for other fuel cycle materials (e.g., high-level waste and cladding hulls) have not been developed because there has been no need to transport these materials commercially. However, conceptual designs for packaging and transport of such materials have been developed. Selected systems are reviewed and summarized. Transport safety in the U.S. is regulated by the U.S. Department of Transportation and the Nuclear Regulatory Commission. Key regulations defining packaging requirements, allowable radiation dose rates, and handling procedures are reviewed. Although the radioactive material shipping industry has an outstanding safety record, opposition to nuclear fuel cycle shipments has surfaced in several areas. The U.S. congressional ban on the shipment of plutonium by air, the actions of New York City to prohibit certain shipments within the city limits, and the requirement of U.S. railroads to ship spent fuel casks only in dedicated trains are reviewed. In an attempt to provide information on the safety margins inherent in the design of radioactive materials packages, ERDA has undertaken a series of accident studies and full scale crash tests that stress the packages beyond the levels expected in severe accidents. In addition, the level of total risk associated with radioactive materials shipments is being evaluated. Current ERDA crash test and transportation risk assessment studies are reviewed. Concern about the possibility of

  12. Derivation of uranium residual radioactive material guidelines for the Ventron site

    International Nuclear Information System (INIS)

    Loureiro, C.; Yu, C.; Jones, L.

    1992-03-01

    Residual radioactive material guidelines for uranium were derived for the Ventron site in Beverly, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program of the US Department of Energy (DOE). The derivations for the single radionuclides and the total uranium guidelines were based on the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Ventron site should not exceed a dose of 100 mrem/yr following remedial action. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation

  13. INES- French application to radioactive material transport

    International Nuclear Information System (INIS)

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

    2004-01-01

    After gaining control of radioactive material transport in June 1997, the French Nuclear Safety Authority (ASN) decided to apply the International Nuclear Event Scale (INES scale) to transport events. The Directorate General for Nuclear Safety and Radioprotection (DGSNR) requests that radioactive material package consignors declare any event occurring during transport, and has introduced the use of the INES scale adapted to classify transport events in order to inform the public and to have feedback. The INES scale is applicable to events arising in nuclear installations associated with the civil nuclear industry and events occurring during the transport of radioactive materials to and from them. The INES scale consists of seven levels. It is based on the successive application of three types of criterion (off-site impact, on-site impact and degradation of defence in depth) and uses the maximum level to determine the rating of an accident. As the transport in question takes place on public thoroughfares, only the off-site impact criteria and degradation of defence in-depth criteria apply. This paper deals with DGSNR's feedback during the past 7 years concerning the French application of the INES scale. Significant events that occurred during transport are presented. The French experience was used by the International Atomic Energy Agency (IAEA) to develop a draft guide in 2002 and the IAEA asked countries to use a new draft for a trial period in July 2004. (author)

  14. Device for sampling liquid radioactive materials

    International Nuclear Information System (INIS)

    Vlasak, L.

    1987-01-01

    Remote sampling of radioactive materials in the process of radioactive waste treatment is claimed by the Czechoslovak Patent Document 238599. The existing difficulties are eliminated consisting in a complex remote control of sampling featuring the control of sliding and rotary movements of the sampling device. The new device consists of a vertical pipe with an opening provided with a cover. A bend is provided above the opening level housing flow distributors. A sampling tray is pivoted in the cover. In sampling, the tray is tilted in the vertical pipe space while it tilts back when filled. The sample flows into a vessel below the tray. Only rotary movement is thus sufficient for controlling the tray. (Z.M.)

  15. Denial of shipments of radioactive materials in Paraguay

    International Nuclear Information System (INIS)

    More Torres, Luis E.; Romero de Gonzalez, V.; Lopez Caceres, S.M.

    2008-01-01

    The Denials, Delays and Abandonment of the Radioactive Materials is a problem at world level that has been increased in the last times with more emphasis starting from the attack of September 11 the 2001 in the USA. From then radioactive materials have been denial or delayed and until abandoned. The materials of short periods used mainly in nuclear medicine as the 99m Tc or the 131 I, when they are rejected, delayed it usually causes the lost of the material because it has surpassed their useful life and in many cases they are abandoned. The rejections, delays and later abandonment of the materials in special of Medical use have originated serious damages for the nuclear medicine patients as much of diagnoses as of treatments, in Teleterapia for many patients of cancer who could not be treated. In the petroliferous prospecting and Industry has originated numerous economic damages due to the delays since most of the used sources they are of long period but the delay causes an important increase in the cost. (author)

  16. Naturally radioactivity in common building materials used in Thiruvannamalai city, Tamilnadu, India

    International Nuclear Information System (INIS)

    Ravisankar, R.; Vanasundari, K.; Suganya, M.; Sivakumar, S.; Senthilkumar, G.; Chandramohan, J.; Vijayagopal, P.; Venkatraman, B.

    2012-01-01

    The radioactivity of some building materials used in Thiruvannamalai city has been measured using a NaI(Tl) detector based gamma ray spectrometer. The distribution of natural occurring radionuclides ( 226 Ra, 232 Th and 40 K) in the building materials was studied. The radium equivalent activity (Ra eq ), external hazard index (H ex ) internal radiation hazard index (H in ) and the activity utilization index (I) associated with the natural radionuclide are calculated to assess the radiation hazard of the natural radioactivity in the building materials. The present work shows that the natural radioactivity levels in the building construction materials used in Thiruvannamalai city is well below the acceptable limits. From the analysis, it was found that these materials may be safely used as construction materials and do not pose significant radiation hazards. (author)

  17. 49 CFR 173.476 - Approval of special form Class 7 (radioactive) materials.

    Science.gov (United States)

    2010-10-01

    ... (radioactive) materials must maintain on file for at least one year after the latest shipment, and provide to... evidence based on calculative methods to show that the material is able to pass the tests; or other... shipping papers as “Radioactive Material, Special Form, n.o.s.” [Amdt. 173-244, 60 FR 50307, Sept. 28, 1995...

  18. 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)

  19. Radioactive materials transportation emergency response plan

    International Nuclear Information System (INIS)

    Karmali, N.

    1987-05-01

    Ontario Hydro transports radioactive material between its nuclear facilities, Atomic Energy of Canada Limited at Chalk River Laboratories and Radiochemical Company in Kanata, on a regular basis. Ontario Hydro also occasionally transports to Whiteshell Laboratories, Hydro-Quebec and New Brunswick Electric Power Commission. Although there are stringent packaging and procedural requirements for these shipments, Ontario Hydro has developed a Radioactive Materials Transportation Emergency Response Plan in the event that there is an accident. The Transportation Emergency Response plan is based on six concepts: 1) the Province id divided into three response areas with each station (Pickering, Darlington, Bruce) having identified response areas; 2) response is activated via a toll-free number. A shift supervisor at Pickering will answer the call, determine the hazards involved from the central shipment log and provide on-line advice to the emergency worker. At the same time he will notify the nearest Ontario Hydro area office to provide initial corporate response, and will request the nearest nuclear station to provide response assistance; 3) all stations have capability in terms of trained personnel and equipment to respond to an accident; 4) all Ontario Hydro shipments are logged with Pickering NGS. Present capability is based on computerized logging with the computer located in the shift office at Pickering to allow quick access to information on the shipment; 5) there is a three tier structure for emergency public information. The local Area Manager is the first Ontario Hydro person at the scene of the accident. The responding facility technical spokesperson is the second line of Corporate presence and the Ontario Hydro Corporate spokesperson is notified in case the accident is a media event; and 6) Ontario Hydro will respond to non-Hydro shipments of radioactive materials in terms of providing assistance, guidance and capability. However, the shipper is responsible

  20. The natural radioactivity of building materials used in the Christchurch urban area

    International Nuclear Information System (INIS)

    Chapman, R.H.

    1984-01-01

    The natural gamma radioactivity of a variety of common building materials in Christchurch, has been measured by gamma spectroscopy. Using conversion factors from the literature, relative dose rate indices for the various building materials were calculated and compared. An increasing order of radioactivity concentration was found from timber to compressed limestone to brick products. These levels are however less than the acceptable limits of radioactivity based on some overseas criteria suggested as building standards

  1. BENTONITE-QUARTZ SAND AS THE BACKFILL MATERIALS ON THE RADIOACTIVE WASTE REPOSITORY

    Directory of Open Access Journals (Sweden)

    Raharjo Raharjo

    2010-06-01

    Full Text Available An investigation of the contribution of quartz sand in the bentonite mixture as the backfill materials on the shallow land burial of radioactive waste has been done. The experiment objective is to determine the effect of quartz sand in a bentonite mixture with bentonite particle sizes of -20+40, -40+60, and -60+80 mesh on the retardation factor and the uranium dispersion in the simulation of uranium migration in the backfill materials. The experiment was carried out by the fixed bed method in the column filled by the bentonite mixture with a bentonite-to-quartz sand weight percent ratio of 0/100, 25/75, 50/50, 75/25, and 100/0 on the water saturated condition flown by uranyl nitrate solution at concentration (Co of 500 ppm. The concentration of uranium in the effluents in interval 15 minutes represented as Ct was analyzed by spectrophotometer, then using Co and Ct, retardation factor (R and dispersivity ( were determined. The experiment data showed that the bentonite of -60+80 mesh and the quartz sand of -20+40 mesh on bentonite-to-quartz sand with weight percent ratio of 50/50 gave the highest retardation factor and dispersivity of 18.37 and 0.0363 cm, respectively.   Keywords: bentonite, quartz sand, backfill materials, radioactive waste

  2. Radioactivity distribution measurement of various natural material surfaces with imaging plate

    International Nuclear Information System (INIS)

    Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Yanagida, K.; Wu, Y.; Nishizawa, K.

    1996-01-01

    Distribution images of natural radioactivity in natural materials such as vegetables were obtained by using Imaging Platc. In ssuch cases, it is necessary to reduce background radiation intensity by one order or more. Graded shielding is very important. Espacially, the innermost surface of a shielding box sshould be covered with acrylic rein plate. We obtained natural radioactivity distribution images of vegetable, sea food, mea etc. Most β-rays emitted from 40 K print the radioactivity distribution image. Comparison between γ-ray intensity of KCL solution measured with HPGe detector and that of natural material specimen gave the radioactivity around 0.06- 0.04Bq/g depending on the kind and the part of specimens. (author). 6 refs., 5 figs., 1 tab

  3. Liquid filter for liquids containing radioactive materials

    International Nuclear Information System (INIS)

    Rohleder, N.; Schwarz, F.

    1986-01-01

    A device for filtering radioactive liquids loaded with solids is described, which has a pressure-resistant housing with a lid and an incomer for the turbid liquid and a collecting space and drain for the filtrate at the bottom of the housing. A filter cartridge is present in this housing. Such a filtering device must be suitable for use in nuclear plants, must be easy to replace by remote control and must minimise the carrying over of radioactive particles. This problem should be solved by the filter cartridge consisting of a large number of horizontal filter plates stacked above one another, which carry a deep layer filter material acting in the sub-micron range. The turbid liquid runs into the centre of the stack of filter plates via a vertical central duct. The intermediate spaces between the filter places are connected to this central duct via the layer of filter material. The filter plates are sealed against one another on the outer circumference and have radial drain openings for the filtrate on the outside. The central duct is sealed at the lower end by a plate. When the filter cartridge is replaced, the radioactive waste in the filter cartridge remains safely enclosed and can be conditioned in suitable containers. (orig.) [de

  4. State legislative developments in radioactive materials transportation, July 1, 1994--June 30, 1995

    International Nuclear Information System (INIS)

    Goehring, J.B.; Reed, J.B.

    1995-08-01

    Each year, the National Conference of State Legislatures (NCSL) prepares an update on state developments in radioactive materials transportation. The 1995 Report on State Legislative Developments in Radioactive Materials Transportation describes activities between July 1, 1994 and June 30, 1995. Forty-six bills were introduced and are arranged in this report by state according to their status--enacted, pending or failed. The bills address nuclear materials transportation as well as the broader areas of hazardous materials transportation, waste storage and emergency responsiveness. Also included are state legislative resolutions and Federal Register notices and rule changes related to radioactive waste and hazardous materials transportation that affect states

  5. State legislative developments in radioactive materials transportation, July 1, 1996--June 6, 1997

    International Nuclear Information System (INIS)

    Kim, M.H.; Reed, J.B.

    1997-06-01

    The National Conference of State Legislatures (NCSL) prepares an update on state developments in radioactive materials transportation each year. The 1997 Report on State Legislative Developments in Radioactive Materials Transportation describes activities between July 1, 1996 and June 6, 1997. Fifty bills were introduced and are arranged in this report by state according to their status--enacted, pending or failed. The bills address nuclear materials transportation as well as the broader areas of hazardous materials transportation, waste, storage and emergency response. Also summarized are state legislative resolutions and Federal Register notices and rule changes related to radioactive waste and hazardous materials transportation that affect states

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

    International Nuclear Information System (INIS)

    2013-02-01

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

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

    International Nuclear Information System (INIS)

    Akatsuka, Hiroshi

    2003-01-01

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

  8. Radioactive waste - a select list of material

    International Nuclear Information System (INIS)

    Lambert, C.M.

    1982-01-01

    A chronological bibliography is presented of literature relating to radioactive waste management in the United Kingdom concentrating on material published since 1978. The main sections include Dept. of Environ. and Official publications, administrative and environmental concerns, technological and scientific considerations, including publications on geological aspects, deep-sea bed and ocean-dumping and salt domes, with general background material and further sources of information listed at the end. (U.K.)

  9. Treatment of radioactive silts and soils with organic materials

    International Nuclear Information System (INIS)

    Sobolev, I.A.; Barinov, A.S.; Dmitriev, S.A.; Lifanov, F.A.; Varlakov, A.P.; Karlin, S.V.

    1997-01-01

    Moscow SIA RADON is developing the ''Clinker'' method to treat radioactive silts and grounds. The ''Clinker'' method consists of radioactive silt (ground) mixed with lime and other components. This mixture is calcined at 800 to 1000 o C. The product is ground to a surface area size of 2500 to 4500 cm 2 /g, mixed with water at a water-to-cement ratio not less than 0.25, and aged to form a solid monolith. The ''Clinker'' method was compared to the traditional cementation methods. The ''Clinker'' method reduces the final volume and enhance the strength characteristics of the final product. The ''Clinker'' cement compound has higher hardening rate. Preliminary data show that it has higher cold resistance, sulfate and leaching corrosion durability in comparison to one prepared by the traditional cementation method. The range of applicability of the ''Clinker'' method is increased by the possibility of treating materials containing up to 80% (mass) of organic materials, such as turf, flora and fauna decomposition products, and manmade material, including natural materials, such as petroleum products and polymers. In addition, the ''Clinker'' method does not require expensive waste binders, i.e., cement. The ''Clinker'' cement can be used for cementation of other radioactive waste. (author)

  10. Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

    International Nuclear Information System (INIS)

    1993-10-01

    This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

  11. Low radioactivity material for use in mounting radiation detectors

    Science.gov (United States)

    Fong, Marshall; Metzger, Albert E.; Fox, Richard L.

    1988-01-01

    Two materials, sapphire and synthetic quartz, have been found for use in Ge detector mounting assemblies. These materials combine desirable mechanical, thermal, and electrical properties with the radioactive cleanliness required to detect minimal amounts of K, Th, and U.

  12. RESRAD, Residual Radioactive Material Guideline Implementation

    International Nuclear Information System (INIS)

    1998-01-01

    This code system is designed to calculate site-specific residual radioactive material guidelines, and radiation dose and excess cancer risk to an on-site resident (maximally exposed individual). A guideline is a radionuclide concentration or level of radioactivity that is acceptable if a site is to be used without radiological restrictions. Guidelines are expressed as concentrations of residual radionuclides in soil. Soil is unconsolidated earth material, including rubble and debris that may be present. The guidelines are based on the following principles: (1) the total effective dose equivalent should not exceed 100 mrem/yr for all plausible land uses and 30 mrem/yr for current and likely future land uses and (2) doses should be kept as low as reasonably achievable (ALARA). Nine environmental pathways are considered: direct exposure, inhalation of dust and radon, and ingestion of plant foods, meat, milk, aquatic foods, soil, and water. CCC-0552/04: A - Description of program or function: RESRAD-BUILD Version 2.36 is a pathway analysis model designed to evaluate the potential radiological dose incurred by an individual who works or lives in a building contaminated with radioactive material. The radioactive material in the building structure can be released into the indoor air by mechanisms such as diffusion (radon gas), mechanical removal (decontamination activities), or erosion (removable surface contamination). In the June 1998 update, RESRAD was updated to Version 5.82 and RESRAD-BUILD was updated to version 2.36. The following notes highlight new features: RESRAD5.82 (4/30/98): - Allow plot data to be exported to tab-delimited text file - Corrected Installation problem to Windows 3.1 - Corrected plotting problem for soil guidelines RESRAD-BUILD2.36 (4/9/98): - Corrected problem with simultaneously changing number of wall regions and their parameters - Added OK button to uncertainty window - Made sure first uncertainty variable in added on first try See the

  13. Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

    International Nuclear Information System (INIS)

    Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

    2007-01-01

    Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

  14. The rapid identification for the unaware radioactive material

    International Nuclear Information System (INIS)

    Jin Yuren; Cheng Zhiwei; Xu Hui; Wang Jiang; Han Xiaoyuan; Long Bin

    2010-01-01

    The unaware radioactive material(URM) appeared in the society may induce serious deterministic effect, even result in havoc and instability of the society. The rapid and accurate identification for URM is the premise for its reasonable treatment. In this paper, an identification procedure for URM was developed and which was successfully implemented in the identification of an URM. The In-situ HPGe gamma spectrometry etc was employed for the rapid preliminary identification, and the laboratory HPGe gamma spectrometry and ICP-MS as well as the density measurement were used for its final identification. One unaware radioactive material was assayed, and the results indicate that it is a kind of high pure depleted uranium metal with the 235 U/ 238 U atomic ratio of 0.454%. (authors)

  15. 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

  16. Radioactive material (RAM) accident/incident data analysis program

    International Nuclear Information System (INIS)

    Emerson, E.L.; McClure, J.D.

    1985-03-01

    This report describes the development of the Radioactive Material Transportation Accident/Incident Data Base (RAM-AIDB), which contains information on the occurrences of transportation accidents and incidents, for radioactive materials (RAM) that are involved in the process of transportation, loading and unloading operation, or temporary storage. These transportation operations are in support of the nuclear fuel cycle for electrical energy generation. This study analyzes in some detail basic accident/incident statistical data, RAM packaging accident response data, and the health effects associated with RAM transport accidents/incidents. This report presents a summary of US RAM transport accident/incident experience for the period 1971 through December 1981. In addition, a sample annual summary of accident/incident experience is presented for the calendar year 1981

  17. Radiolysis in cement-based materials ; application to radioactive waste-forms

    International Nuclear Information System (INIS)

    Bouniol, P.

    2014-01-01

    Cement-based materials appear to be an original environment with respect to radiolysis, due to their intrinsic complexity (porous, multiphasic and evolutional medium) or their very specific physico-chemical conditions (hyper-alkaline medium with pH ≥ 13, high content in calcium) or by the fact of numerous couplings existing between different phenomenologies. At the level of a radioactive cemented wasteform, a high degree of complexity is reached, in particular if the system communicates with the atmosphere (open system allowing regulation of the pressures but also the admission of O 2 , strong reactive with regards to radiolysis). Then, the radiolysis description exceeds widely the only one aspect of the decomposition of alkaline water under irradiation and makes necessary a global phenomenological approach. In this context, some 'outlying' phenomena, highly coupled with radiation chemistry, have to be taken into account because they contribute to deeply modify the net result of the radiolysis: radioactive decay of multiple αβγ emitters with filiation, phase changes (for example H 2 aq → H 2 gas) within the pores, gas transport by convection (Darcy law) and by diffusion (Fick law), precipitation/dissolution of solid phases, effect of the ionic strength and the temperature, disturbances connected to the presence of some solutes with redox potentialities (iron, sulphur). The integration work carried out on the previous points leads to an operational model (DOREMI) allowing the estimate of H 2 amounts produced by radiolysis in different cemented radioactive waste-forms. As the final expression of the model, numerical simulations constitute a relevant tool of expertise and prospecting, contributing to accompany the thought on radiolysis in cement matrices in general and in cemented waste-forms in particular. Starting from different examples, simulations can be so used in order to test some hypotheses or illustrate the greatest influence of gas transport, dose

  18. Occupational radiation exposure in work with radioactive materials

    International Nuclear Information System (INIS)

    Georgiev, G.V.

    1975-01-01

    Radiation exposure to personnel dealing with radioactive materials is studied on a national scale. The survey covers any type of radiation work except for mining and milling of radioactive ore, fuel production, and nuclear reactor operation. Assessments are based on a decade's collection of personnel monitoring data obtained by film dosimetry techniques, as well as on data from systematic operational site monitoring. Statistical analysis indicated exposures based on personal records to follow a normal distribution pattern and, hence, arithmetic averages to be representative. Airborne concontrations of radioactive materials and aerosols in working areas are shown to follow a logarithmic normal distribution pattern, so that geometric means are representative. Radiation exposures are generally found to be well below annual maximum permissible doses for radiation workers. However, their distribution among employee groups is nonuniform. Group A, comprising about 700 subjects, received mean annual gonad doses of more than 1000 mrem; group B, about 670 subjects, had doses ranging from 100 to 500 mrem per year; and group C, 1610 subjects, received less than 100 mrem per year. Most of the radiation dose is accounted for by external radiation, which contributed 0.327 mrem to the genetically significant population dose (0.227 from exposure to males, and 0.025 mrem from exposure to females). Analysis of accidental exposures occurring over the period 1963-1973 indicated that the contribution of this source is substantial as compared to routine work (1.0:0.3). Based on the results obtained, a number of preventive measures are developed and introduced into practice to improve radiological safety in work with radioactive materials. (A.B.)

  19. Methodology for safety and security of radioactive sources and materials. The Israeli approach

    International Nuclear Information System (INIS)

    Keren, M.

    1998-01-01

    About 10 Radioactive incidents occurred in Israel during 1996-1997. Some of them were theft or lost of Radioactive equipment or sources, some happened because misuse of Radioactive equipment and some of other reasons. Part of them could be eliminated if a better methodological attitude to the subject existed. A new methodology for notification, registration and licensing is described. Hopefully this methodology will increase defense in depth and the Safety and Security of Radioactive sources and materials. Information on the inventory of Radioactive sources and materials is essential. Where they are situated, what is the supply rate or all history from berth to grave. Persons involved are important: Who are the Radiation Safety Officers (RSO), what is their training and updating programs. As much as possible information on the site and places where those Radioactive sources and materials are used. Procedures for security of sources and materials is part of site information, beside safety precautions. Users are obliged to inform on any changes and to ask for confirmation to those changes. The same is when high activity sources are moved across the country. (author)

  20. International regulatory control of the transport of radioactive materials

    International Nuclear Information System (INIS)

    Swindell, G.E.

    1979-01-01

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

  1. Impact assessment at the submergence of radioactive materials during sea transport

    International Nuclear Information System (INIS)

    Tsumune, Daisuke; Tsubono, Takaki; Saegusa, Toshiari; Ito, Chihiro

    2009-01-01

    Radioactive materials in Type B package have been transported safely on the sea under INF code and IAEA standard. Environmental and dose impact assessments have been made by assuming that a Type B package might be sunk into the sea since 1970s to enhance public understanding on safety of these transport. A method of the impact assessment consists of the estimation of release rates of radionuclide from a package, simulation of radionuclide concentration both in the coastal and global areas, and estimation of dose assessment for the public. We summarized the radiological impact at the submergence of Type B packages. The evaluated results of the dose equivalents by radiation exposure to the public for all materials were far below the dose equivalent limit of the ICRP recommendation (1mSv year -1 ). These assessments had a lot of uncertainties especially in the simulation of radionuclide concentration therefore the results might be overestimated. Estimations of ocean circulation and diffusion are important in this assessment. Ocean circulation model have been improved to simulate the material transport with higher resolutions. We developed more realistic methods to simulate both in the coastal and global areas to explain the evaluated results of the impacts to the public in an efficient manner. General circulation models around Japan and an ocean general circulation model were employed at the coastal and global areas respectively. It is impossible to validate the method directly because no accidents with release of radionuclide in the ocean have occurred since first sea transport of Type B packages. Therefore we simulated background radionuclide concentrations by fallouts ( 137 Cs) to validate the methods. Fallouts were input into ocean by nuclear weapon test since 1945 and mainly in 1960s. And their concentrations in the ocean have been measured to keep monitoring the artificial contaminations now. Observed database is useful to compare with simulated results in both

  2. Packaging and transportation of radioactive materials: summary program

    International Nuclear Information System (INIS)

    1978-01-01

    This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference

  3. Response to events involving the inadvertent movement or illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2002-09-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  4. Response to events involving the inadvertent movement or illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2004-08-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  5. Response to events involving the inadvertent movement or illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2002-08-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  6. Response to events involving the inadvertent movement or illicit trafficking of radioactive materials

    International Nuclear Information System (INIS)

    2003-08-01

    By international agreements, the movement of all radioactive materials within and between States should be subject to high standards of regulatory, administrative, safety and engineering controls to ensure that such movements are conducted in a safe and secure manner. In the case of nuclear materials, there are additional requirements for physical protection and accountability to ensure against threats of nuclear proliferation and to safeguard against any attempts at diversion. The results of the terrorist attacks of September 2001 emphasized the requirement for enhanced control and security of nuclear and radioactive materials. In this regard, measures are being taken to increase the global levels of physical protection and security for nuclear materials. Experience in many parts of the world continues to prove that movements of radioactive materials outside of the regulatory and legal frameworks continue to occur. Such movements may be either deliberate or inadvertent. Deliberate, illegal movements of radioactive materials, including nuclear material, for terrorist, political or illegal profit is generally understood to be illicit trafficking. The more common movements outside of regulatory control are inadvertent in nature. An example of an inadvertent movement might be the transport of steel contaminated by a melted radioactive source that was lost from proper controls. Such a shipment may present health and safety threats to the personnel involved as well as to the general public. States have the responsibility for combating illicit trafficking and inadvertent movements of radioactive materials. The IAEA co-operates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by the provision of relevant advice through technical assistance and documents. As an example, the IAEA and the World Customs Organization (WCO) maintain a Memorandum

  7. 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.

  8. Packaging and transportation of radioactive materials: summary program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference. (DC)

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

    International Nuclear Information System (INIS)

    Pallier, Lucien

    1961-01-01

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

  10. Experimental Study on the Interaction Between Contacting Barrier Materials for Containment of Radioactive Wastes

    Science.gov (United States)

    Huang, W. H.; Chang, H. C.

    2017-12-01

    The disposal of low- and intermediate-level radioactive wastes requires use of multi-barriers for isolation of the wastes from the biosphere. Typically, the engineered barriers are composed of a concrete vault, buffer and backfill materials. Zhishin clay and Black Hill bentonite were used as raw clay material in making buffer and backfill materials in this study. These clays were compacted to make buffer material, or mixed with Taitung area argillite to produce backfill material for potential application as barriers for the disposal of low- and intermediate-level radioactive wastes. The interaction between concrete barrier and the buffer/backfill material is simulated by an accelerated migration test to investigate the effect of contacting concrete on the expected functions of buffer/backfill material. The results show buffer material close to the contact with concrete exhibits significant change in the ratio of calcium/sodium exchange capacity, due to the move of calcium ions released from the concrete. The shorter the distance from the contacting interface, the ratio of the calcium/sodium concentration in buffer/backfill materials increases. The longer the distance from the interface, the effect of the contact on alteration in clays become less significant. Also, some decreases in swelling capacity in the buffer/backfill material near the concrete-backfill interface are noted. Finally, a comparison is made between Zhisin clay and Balck Hill bentonite on the interaction between concrete and the two clays. Black Hill bentonite was found to be influenced more by the interaction, because of the higher content of montmorillonite. On the other hand, being a mixture of clay and sand, backfill material is less affected by the decalsification of concrete at the contact than buffer material.

  11. Data about shipping of radioactive material for medical use; Datos sobre los envios de material radioactivo para uso medico

    Energy Technology Data Exchange (ETDEWEB)

    Sanches, M.P.; Rodrigues, D.L. [Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN, Comissao Nacional de Energia Nuclear - CNEN/SP, Av.Professor Lineu Prestes No. 2242, Zip Code 05508-000, Sao Paulo (Brazil)]. e-mail: msanches@ipen.br

    2006-07-01

    The transport of radioactive materials implies a risk for the personnel of the team, those members of the public and the environment. While the safety in the transports is based on the designs of the bulks, the programs of radiological protection are important to assure the radiological control to the workers, the public and the environment during the transport of these materials. Although the biggest interest in the transport of radioactive materials it spreads to be centered in the nuclear industry, the transport in great measure it happens for the materials of medical use. These are mainly transported in bulks of the A Type and excepted bulks. The transport ones are forced, by national regulations, to send to the competent authority, in our case the National Comissao of Nuclear Energy (CNEN), all the data of the transported materials. This work has by objective to aim the efforts made to settle down and to manage the data regarding the transported radioactive materials. The existent data in the Radiopharmaceuticals Center, of the Institute of Energy and Nuclear Investigations 'IPEN/CNEN' it contains the information on all the radioactive materials consigned for the transport during every year. A statistic of the number of deliveries of the radioactive material for the period from 2001 to 2005 is provided. Based on this statistic its are presented the number of bulks, the quantity of activity and the ways of the transport for the period in study. (Author)

  12. Radiological dose assessment of naturally occurring radioactive materials in concrete building materials

    International Nuclear Information System (INIS)

    Amran AB Majid; Aznan Fazli Ismail; Muhamad Samudi Yasir; Redzuwan Yahaya; Ismail Bahari

    2013-01-01

    Previous studies have shown that the natural radioactivity contained in building materials have significantly influenced the dose rates in dwelling. Exposure to natural radiation in building has been of concerned since almost 80 % of our daily live are spend indoor. Thus, the aim of the study is to assess the radiological risk associated by natural radioactivity in soil based building materials to dwellers. A total of 13 Portland cement, 46 sand and 43 gravel samples obtained from manufacturers or bought directly from local hardware stores in Peninsular of Malaysia were analysed for their radioactivity concentrations. The activity concentrations of 226 Ra, 232 Th and 40 K in the studied building materials samples were found to be in the range of 3.7-359.3, 2.0-370.8 and 10.3-1,949.5 Bq kg -1 respectively. The annual radiation dose rates (μSv year -1 ) received by dwellers were evaluated for 1 to 50 years of exposure using Resrad-Build Computer Code based on the activity concentration of 226 Ra, 232 Th and 40 K found in the studied building material samples. The rooms modelling were based on the changing parameters of concrete wall thickness and the room dimensions. The annual radiation dose rates to dwellers were found to increase annually over a period of 50 years. The concrete thicknesses were found to have significantly influenced the dose rates in building. The self-absorption occurred when the concrete thickness was thicker than 0.4 m. Results of this study shows that the dose rates received by the dwellers of the building are proportional to the size of the room. In general the study concludes that concrete building materials; Portland cements, sands, and gravels in Peninsular of Malaysia does not pose radiological hazard to the building dwellers. (author)

  13. Incineration of Non-radioactive Simulated Waste

    International Nuclear Information System (INIS)

    Ahmed, A.Z.; Abdelrazek, I.D.

    1999-01-01

    An advanced controlled air incinerator has been investigated, developed and put into successful operation for both non radioactive simulated and other combustible solid wastes. Engineering efforts concentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced minimum amounts of secondary waste. Feed material is fed by gravity into the gas reactor without shredding or other pretreatment. The temperature of the waste is gradually increased in a reduced oxygen atmosphere as the resulting products are introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gas then passing through a simple dry cleaning-up system. Experimental studies showed that, at lower temperature, CO 2 , and CH 4 contents in gas reactor effluent increase by the increase of glowing bed temperature, while H 2 O, H 2 and CO decrease . It was proved that, a burn-out efficiency (for ash residues) and a volume reduction factor appeared to be better than 95.5% and 98% respectively. Moreover, high temperature permits increased volumes of incinerated material and results in increased gasification products. It was also found that 8% by weight of ashes are separated by flue gas cleaning system as it has chemical and size uniformity. This high incineration efficiency has been obtained through automated control and optimization of process variables like temperature of the glowing bed and the oxygen feed rate to the gas reactor

  14. ASN: regional day of information and exchange on transport of radioactive materials - 4 February 2010

    International Nuclear Information System (INIS)

    2010-01-01

    This document gathers Power Point presentations made during a meeting on the transport of radioactive materials. The contributions addressed the following topics: results of a survey based on questionnaires sent to actors of this sector, regulatory framework and radioprotection plan, case of parcels not submitted to the authority concerned, declaration of transport interesting or significant events, ASN inspections, the transport of radioactive products by the IBt Bebig company in France, the activities of the Institut de Soudure Industrie (industry welding institute), the activities of the ISO Life company specialized in health product transportation, the activities of the Securidis company (a consulting company for activities related to hazardous materials transportation, and notably radioactive materials), the activities a the ACE Environnement company (specialized in building diagnosis), the point of view of an academic research unit on radioactive material transportation, the experience of the hospital sector in radioactive source transportation, the experience of the Advanced Accelerator Applications company in radioactive material transportation, and a discussion on regulation application

  15. The radioactive materials packaging handbook: Design, operations, and maintenance

    International Nuclear Information System (INIS)

    Shappert, L.B.; Bowman, S.M.; Arnold, E.D.

    1998-01-01

    As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE's cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials

  16. The radioactive materials packaging handbook: Design, operations, and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

    1998-08-01

    As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

  17. Methods and apparatus for determining the spatial distribution of a radioactive material

    International Nuclear Information System (INIS)

    Todd, R.W.

    1975-01-01

    The spatial distribution of a radioactive material is determined by locating the positions of and energy losses resulting from Compton interactions which occur in a detector as a result of gamma photons emitted by the radioactive material, which may, for example, have been administered to a patient for medical diagnostic investigation. (auth)

  18. Technical considerations for detection of and response to illicit trafficking in radioactive materials

    International Nuclear Information System (INIS)

    Duftschmid, K.E.; Arlt, R.; Cunningham, J.; Gayral, J.P.; Kravchenko, N.; Smith, D.; York, R.

    2001-01-01

    Full text: The need for guidance and recommendations explicitly directed to the problem of illicit trafficking in nuclear materials and other radioactive sources was raised by the IAEA Director General at the IAEA General Conference in December 1994, and measures were agreed by the IAEA Board of Governors in March 1995. Measures that might be taken to prevent, detect, and respond to illicit trafficking will be common for all radioactive materials, including nuclear materials. However, nuclear materials are, or should be, subject also to safeguards for nuclear non-proliferation purposes and to physical protection to prevent diversion. The IAEA has established close co-operation with intergovernmental and non-governmental organizations, in particular the World Customs Organization (WCO) and INTERPOL to conduct joint studies, meetings and training programs to support Member States in their border control activities. Within this programme technical information has been derived on requirements and methods to detect and respond to events involving inadvertent movement of and illicit trafficking in radioactive materials. The paper summarises the most important results and the experience obtained in this field. Concerning 'detection' information on strategy of detection, selection of an investigation level, techniques for radiation monitoring at borders, verification of alarms, search techniques and identification of radionuclides has been developed. This includes recommended minimum requirements for monitoring equipment, derived from the results of an extended international pilot study on border monitoring equipment ITRAP, conducted by IAEA in co-operation with the Austrian government. In order to discover illicit trafficking or inadvertent movement in radioactive materials, the following steps are required: detection of any abnormal radiation level, verification of such detection, localisation of the origin of the radiation, radiation safety measurement, and

  19. Regulations for the safe transport of radioactive material

    International Nuclear Information System (INIS)

    1995-01-01

    Regulations and rules for the safe transport of radioactive materials by all kinds of conveyance are offered. Different types of packages and the conditions associated with the methods of safe packaging are given

  20. Nuclear reactor structural material forming less radioactive corrosion product

    International Nuclear Information System (INIS)

    Nakazawa, Hiroshi.

    1988-01-01

    Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

  1. Sea transport of radioactive materials in Egypt (invited paper)

    International Nuclear Information System (INIS)

    El-Shinawy, R.M.K.; Gomaa, M.A.

    1998-01-01

    In Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the International Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the experience gained. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the Canal from 1963 to 1996 and their nationalities are also discussed. The protective measures are mentioned. (author)

  2. Impact assessment at a hypothetical submergence of a transport package of radioactive materials

    International Nuclear Information System (INIS)

    Tsumune, Daisuke; Saegusa, Toshiari; Ito, Chihiro

    2007-01-01

    Under INF code and IAEA standard, radioactive materials are transported safety on the sea. To gain the public acceptance for these transports additionally, impact assessments have been made by assuming that a radioactive material package might be sunk into the sea. A method of the impact assessment consists of the calculation of release rate of radionuclide from a package, calculation of radionuclide concentration in the ocean, and estimation of dose assessment for the public. An ocean general circulation model was used to calculate the radionuclide concentration in the ocean. Background radionuclide concentration by fallout was simulated by the ocean general circulation model in this method for the verification. Agreement between calculation and observation suggests that this method is appropriate for the assessment. In the both cases for a package sunk at the coastal region at the depth of two hundreds meters and for that sunk at the ocean at the depth of several thousands meters, the evaluated result of the dose equivalent by radiation exposure to the public are far below the dose equivalent limit of the ICRP recommendation (1 mSv/year). (author)

  3. Air conditioner for radioactive material handling facility

    International Nuclear Information System (INIS)

    Tanaka, Takeaki.

    1991-01-01

    An air conditioner intakes open-air from an open-air intake port to remove sands and sea salt particles by air filters. Then, natural and artificial radioactive particles of less than 1 μm are removed by high performance particulate filters. After controlling the temperature by an air heater or an air cooler, air is sent to each of chambers in a facility under pressure elevation by a blower. In this case, glass fibers are used as the filter material for the high performance particulate filter, which has a performance of more than 99.97% for the particles of 0.3 μm grain size. Since this can sufficiently remove the natural radioactive materials intruded from the outside, a detection limit value in each of the chambers of the facility can be set 10 -13 to 10 -14 μci/cm 3 in respect of radiation control. Accordingly, radiation control can be conducted smoothly and appropriately. (I.N.)

  4. Environmental monitoring of low-level radioactive materials

    International Nuclear Information System (INIS)

    Jester, W.A.; Yu, C.

    1985-01-01

    The authors discuss some of the current rationale behind the environmental monitoring of low-level radioactive materials are as follows: Committee 4 of the International commission on Radiological Protection (ICRP) defined three broad objectives for environmental monitoring: 1) assessment of the actual or potential exposure of humans to radioactive materials or radiation present in their environment or the estimation of the probable upper limits of such exposure; 2) scientific investigation, sometimes related to the assessment of exposures, sometimes to other objectives; 3) improved public relations. Various regulations have been written requiring environmental monitoring to ensure that the public is not being exposed to excessive amounts of radiation from natural sources or from human activities. An example of the monitoring of natural sources of radiation is a requirement of the Environmental Protection Agency's (EPA) National Interim Primary Drinking Water Regulations whereby U.S. water supply companies must have drinking water monitored at least once every four years for radionuclides, primarily the naturally occurring radium-226

  5. Aspects of safety in the transport of radioactive materials

    International Nuclear Information System (INIS)

    Ruiz C, M.A.

    1991-01-01

    The transport of radioactive materials behaves to the equal that other chemical products, certain risks that its are necessary to know how to evaluate and to minimize, adopting all kinds of measures technician-administrative, with object of being able to guarantee that this risks stay in an acceptable level for the population potentially affected for the workers of the one sector and for the environment. To be able to evaluate the risk acceptable it is a difficult task, for that, national and international organizations have established a commitment to develop standards of radiological protection, to make every day but sure the transport of radioactive materials

  6. Directory of certificates of compliance for radioactive materials packages

    International Nuclear Information System (INIS)

    1991-10-01

    This directory contains Certificates of Compliance (Volume 2) for Radioactive Materials Packages. The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

  7. State perspective on how clean is clean enough when radioactive materials are involved

    International Nuclear Information System (INIS)

    Bailey, E.D.

    1992-01-01

    The question of how much radioactive material can be left behind by a user of radioactive materials or how much radioactive material can be taken to a local sanitary landfill is not so much a scientific or technical question as it is a societal, philosophical, and, therefore, political issue. The issues are mired in the debates about nuclear power, nuclear weapons, big business, and distrust of government. Scientific and regulatory bodies add to the general public's true fears, concerns, uncertainties, and mistrust of radiation and things radioactive when they fail to act in a concise, logical, and at least coordinated manner. The bifurcation of standard setting responsibility at the federal level between the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental Protection Agency and the agreement state system of regulating radioactive materials all add to the public's confusion and anxiety. The purpose of this paper is to point out from the viewpoint of a state regulatory agency problems that are seen as stumbling blocks to the implementation and acceptance of a below-regulatory-concern (BRC) policy

  8. Statistical treatment of hazards result from radioactive material in metal scrap

    International Nuclear Information System (INIS)

    Salem, E.F.; Rashad, S.M.

    2013-01-01

    Radioactive sources have a wide range of uses in medicine and industry. Radioactive materials entering the public domain in an uncontrolled manner may creating a serious risk of radiation exposure for workers and the public as well as excessive costs for plant decontamination and waste of product to be borne by the metal industry. This paper describes the major accidents that had happened in the last decades due to radioactive material in metal scrap, provides assessment of associated hazards and lessons learned. This will help Regulatory Authority to introduce measures capable to avoid the recurrence of similar events. The study highlights the situation for metal scrap incidents in Egypt.

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

    International Nuclear Information System (INIS)

    Yin Zhenyu; Yang Guangli; Xu Guang

    2012-01-01

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

  10. Probability and severity of fires on board ships carrying radioactive materials. Annex 6

    International Nuclear Information System (INIS)

    Young, C.N.

    2001-01-01

    This paper summarises the five UK contributions to the International Atomic Energy Agency's Co-ordinated Research Programme (CRP) on Accident Severity at Sea During Transport of Radioactive Material (CRP) on Accident Severity at Sea During Transport of Radioactive Material. (author)

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

    International Nuclear Information System (INIS)

    Fasten, Ch.

    1997-01-01

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

  12. Placarding of road vehicles carrying radioactive materials

    International Nuclear Information System (INIS)

    1977-09-01

    The purpose of this Code is to give guidance on the placarding requirements for vehicles carrying radioactive materials by road in Great Britain and on the continent of Europe. Additional placards may be required regarding dangerous properties other than radioactivity. The labelling of packages for transport is dealt with in AECP 1030. This Code deals with two aspects of road vehicle placarding:-(a) placarding on the outside of road vehicles in Great Britain and on the continent of Europe, (b) a fireproof placard fixed in the driver's cab. Responsibility for placarding the vehicle rests with the carrier, but in practice the consignor may need to provide the placards. (U.K.)

  13. Temperature simulation of thermal plasma melting furnace for disposal of radioactive waste and preliminary research of vitrification formula

    International Nuclear Information System (INIS)

    Lin Peng; Lu Yonghong; Xiang Wenyuan; Chen Mingzhou; Liu Xiajie; Qin Yuxin

    2013-01-01

    Radioactive waste treatment techniques currently used in nuclear power plant increase the volume greatly and bring much pressure on final disposal; Thermal plasma treatment as a crucial technique to reduce the waste volume is introduced. How to improve the efficiency of the plasma energy is the limiting factor of concern. In this paper, the temperature field of thermal plasma melting furnace is simulated, the maximal temperature of fixed bed melting furnace is calculated (about 1445 ℃). According to the optional fire-resistant materials, the feasibility of furnace fabrication is discussed. Vitrification formulas for three typical radioactive wastes are tested with their feasibilities being analyzed then. Finally, the prospect of thermal plasma techniques of radioactive waste is discussed, and issues for future study are raised. (authors)

  14. Biochemical process of low level radioactive liquid simulation waste containing detergent

    International Nuclear Information System (INIS)

    Kundari, Noor Anis; Putra, Sugili; Mukaromah, Umi

    2015-01-01

    Research of biochemical process of low level radioactive liquid waste containing detergent has been done. Thse organic liquid wastes are generated in nuclear facilities such as from laundry. The wastes that are cotegorized as hazard and poison materials are also radioactive. It must be treated properly by detoxification of the hazard and decontamination of the radionuclides to ensure that the disposal of the waste meets the requirement of standard quality of water. This research was intended to determine decontamination factor and separation efficiensies, its kinetics law, and to produce a supernatant that ensured the environmental quality standard. The radioactive element in the waste was thorium with activity of 5.10 −5 Ci/m 3 . The radioactive liquid waste which were generated in simulation plant contains detergents that was further processed by aerobic biochemical process using SGB 103 bacteria in a batch reactor equipped with aerators. Two different concentration of samples were processed and analyzed for 212 hours and 183 hours respectively at a room temperature. The product of this process is a liquid phase called as supernatant and solid phase material called sludge. The chemical oxygen demand (COD), biological oxygen demand (BOD), suspended solid (SS), and its alpha activity were analyzed. The results show that the decontamination factor and the separation efficiency of the lower concentration samples are higher compared to the samples with high concentration. Regarding the decontamination factor, the result for 212 hours processing of waste with detergent concentration of 1.496 g/L was 3.496 times, whereas at the detergent concentration of 0.748 g/L was 15.305 times for 183 hours processing. In case of the separation efficiency, the results for both samples were 71.396% and 93.465% respectively. The Bacterial growth kinetics equation follow Monod’s model and the decreasing of COD and BOD were first order with the rate constant of 0.01 hour −1

  15. Biochemical process of low level radioactive liquid simulation waste containing detergent

    Energy Technology Data Exchange (ETDEWEB)

    Kundari, Noor Anis, E-mail: nooranis@batan.go.id; Putra, Sugili; Mukaromah, Umi [Sekolah Tinggi Teknologi Nuklir – Badan Tenaga Nuklir Nasional Jl. Babarsari P.O. BOX 6101 YKBB Yogyakarta 55281 Telp : (0274) 48085, 489716, Fax : (0274) 489715 (Indonesia)

    2015-12-29

    Research of biochemical process of low level radioactive liquid waste containing detergent has been done. Thse organic liquid wastes are generated in nuclear facilities such as from laundry. The wastes that are cotegorized as hazard and poison materials are also radioactive. It must be treated properly by detoxification of the hazard and decontamination of the radionuclides to ensure that the disposal of the waste meets the requirement of standard quality of water. This research was intended to determine decontamination factor and separation efficiensies, its kinetics law, and to produce a supernatant that ensured the environmental quality standard. The radioactive element in the waste was thorium with activity of 5.10{sup −5} Ci/m{sup 3}. The radioactive liquid waste which were generated in simulation plant contains detergents that was further processed by aerobic biochemical process using SGB 103 bacteria in a batch reactor equipped with aerators. Two different concentration of samples were processed and analyzed for 212 hours and 183 hours respectively at a room temperature. The product of this process is a liquid phase called as supernatant and solid phase material called sludge. The chemical oxygen demand (COD), biological oxygen demand (BOD), suspended solid (SS), and its alpha activity were analyzed. The results show that the decontamination factor and the separation efficiency of the lower concentration samples are higher compared to the samples with high concentration. Regarding the decontamination factor, the result for 212 hours processing of waste with detergent concentration of 1.496 g/L was 3.496 times, whereas at the detergent concentration of 0.748 g/L was 15.305 times for 183 hours processing. In case of the separation efficiency, the results for both samples were 71.396% and 93.465% respectively. The Bacterial growth kinetics equation follow Monod’s model and the decreasing of COD and BOD were first order with the rate constant of 0

  16. Biochemical process of low level radioactive liquid simulation waste containing detergent

    Science.gov (United States)

    Kundari, Noor Anis; Putra, Sugili; Mukaromah, Umi

    2015-12-01

    Research of biochemical process of low level radioactive liquid waste containing detergent has been done. Thse organic liquid wastes are generated in nuclear facilities such as from laundry. The wastes that are cotegorized as hazard and poison materials are also radioactive. It must be treated properly by detoxification of the hazard and decontamination of the radionuclides to ensure that the disposal of the waste meets the requirement of standard quality of water. This research was intended to determine decontamination factor and separation efficiensies, its kinetics law, and to produce a supernatant that ensured the environmental quality standard. The radioactive element in the waste was thorium with activity of 5.10-5 Ci/m3. The radioactive liquid waste which were generated in simulation plant contains detergents that was further processed by aerobic biochemical process using SGB 103 bacteria in a batch reactor equipped with aerators. Two different concentration of samples were processed and analyzed for 212 hours and 183 hours respectively at a room temperature. The product of this process is a liquid phase called as supernatant and solid phase material called sludge. The chemical oxygen demand (COD), biological oxygen demand (BOD), suspended solid (SS), and its alpha activity were analyzed. The results show that the decontamination factor and the separation efficiency of the lower concentration samples are higher compared to the samples with high concentration. Regarding the decontamination factor, the result for 212 hours processing of waste with detergent concentration of 1.496 g/L was 3.496 times, whereas at the detergent concentration of 0.748 g/L was 15.305 times for 183 hours processing. In case of the separation efficiency, the results for both samples were 71.396% and 93.465% respectively. The Bacterial growth kinetics equation follow Monod's model and the decreasing of COD and BOD were first order with the rate constant of 0.01 hour-1.

  17. Border Control of Nuclear and Other Radioactive Materials

    International Nuclear Information System (INIS)

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

    2007-01-01

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

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

    International Nuclear Information System (INIS)

    Anne, C.; Galtier, J.

    2002-01-01

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

  19. Expert systems for the transportation of hazardous and radioactive materials

    International Nuclear Information System (INIS)

    Luce, C.E.; Clover, J.C.; Ferrada, J.J.

    1994-01-01

    Under the supervision of the Transportation Technologies Group which is in the Chemical Technology Division at Oak Ridge National Laboratory, an expert system prototype for the transportation and packaging of hazardous and radioactive materials has been designed and developed. The development of the expert system prototype focused on using the combination of hypermedia elements and the Visual Basic trademark programming language. Hypermedia technology uses software that allows the user to interact with the computing environment through many formats: text, graphics, audio, and full-motion video. With the use of hypermedia, a user-friendly prototype has been developed to sort through numerous transportation regulations, thereby leading to the proper packaging for the materials. The expert system performs the analysis of regulations that an expert in shipping information would do; only the expert system performs the work more quickly. Currently, enhancements in a variety of categories are being made to the prototype. These include further expansion of non-radioactive materials, which includes any material that is hazardous but not radioactive; and the addition of full-motion video, which will depict regulations in terms that are easy to understand and which will show examples of how to handle the materials when packaging them

  20. Safety of radiation sources and security of radioactive materials. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    The International Atomic Energy Agency (IAEA) in co-operation with the European Commission (EC), International Criminal Police Organization (INTERPOL) and the World Customs Organization (WCO) organized an International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, in Dijon, France, from 14 to 18 September 1998. The Government of France hosted this Conference through the Commissariat a l`energie atomique, Direction des applications militaires (CEA/DAM). This TECDOC contains the contributed papers dealing with the topics of this Conference which were accepted by the Conference Programme Committee for presentation. The papers written in one of the two working languages of the Conference, English or French are presented here each by a separate abstract. Ten technical sessions covered the following subjects: the regulatory control of radiation sources, including systems for notification, authorization and inspection; safety assessment techniques applied to radiation sources and design and technological measures including defense in depth and good engineering practice; managerial measures, including safety culture, human factors, quality assurance, qualified experts, training and education; learning from operational experience; international co-operation, including reporting systems and databases; verification of compliance, monitoring of compliance and assessment of the effectiveness of national programmes for the safety of sources; measures to prevent breaches in the security of radioactive materials, experience with criminal acts involving radioactive materials; detection and identification technologies for illicitly trafficked radioactive materials; response to detected cases and seized radioactive materials, strengthening of the awareness, training and exchange of information. The IAEA plans to issue the proceedings of this Conference containing the invited presentations, rapporteurs and Chairpersons overviews and summaries

  1. Safety of radiation sources and security of radioactive materials. Contributed papers

    International Nuclear Information System (INIS)

    1998-09-01

    The International Atomic Energy Agency (IAEA) in co-operation with the European Commission (EC), International Criminal Police Organization (INTERPOL) and the World Customs Organization (WCO) organized an International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, in Dijon, France, from 14 to 18 September 1998. The Government of France hosted this Conference through the Commissariat a l'energie atomique, Direction des applications militaires (CEA/DAM). This TECDOC contains the contributed papers dealing with the topics of this Conference which were accepted by the Conference Programme Committee for presentation. The papers written in one of the two working languages of the Conference, English or French are presented here each by a separate abstract. Ten technical sessions covered the following subjects: the regulatory control of radiation sources, including systems for notification, authorization and inspection; safety assessment techniques applied to radiation sources and design and technological measures including defense in depth and good engineering practice; managerial measures, including safety culture, human factors, quality assurance, qualified experts, training and education; learning from operational experience; international co-operation, including reporting systems and databases; verification of compliance, monitoring of compliance and assessment of the effectiveness of national programmes for the safety of sources; measures to prevent breaches in the security of radioactive materials, experience with criminal acts involving radioactive materials; detection and identification technologies for illicitly trafficked radioactive materials; response to detected cases and seized radioactive materials, strengthening of the awareness, training and exchange of information. The IAEA plans to issue the proceedings of this Conference containing the invited presentations, rapporteurs and Chairpersons overviews and summaries

  2. State legislative developments in radioactive materials transportation, July 1, 1995--June 30, 1996

    International Nuclear Information System (INIS)

    Goehring, J.B.; Reed, J.B.

    1996-09-01

    The National Conference of State Legislatures (NCSL) prepares an update on state developments in radioactive materials transportation each year. The 1996 Report on State Legislative Developments in Radioactive Materials Transportation describes activities between July 1, 1995, and June 30, 1996. Thirteen bills were introduced and are arranged in this report by state according to their status--enacted, pending or failed. The report also includes 10 New York bills introduced in 1995 that remained pending during this review period. The bills address nuclear materials transportation as well as the broader areas of hazardous materials transportation, waste storage and emergency response. Also summarized are a state legislative resolution and Federal Register notices and rule changes related to radioactive waste and hazardous materials transportation that affect states

  3. Safety of radiation sources and other radioactive materials in Jordan

    International Nuclear Information System (INIS)

    Majali, M.M.

    2001-01-01

    Since joining the IAEA Model Project for upgrading radiation protection infrastructure in countries of West Asia, Jordan has amended its radiation safety legislation. The Regulatory Authority is improving its inventory system for radiation sources and other radioactive materials and also its notification, registration, licensing, inspection and enforcement systems. It has established national provisions for the management of orphan sources after they have been found. The system for the control of the radiation sources and other radioactive materials entering the country has been improved by the Regulatory Authority. (author)

  4. Consequences of Illicit Trafficking of Nuclear or Other Radioactive Materials

    International Nuclear Information System (INIS)

    Moore, G.M.

    2010-01-01

    Explosion of a nuclear yield device is probably the worst consequence of Illicit Trafficking of nuclear or other radioactive materials.The nuclear yield device might be a stolen nuclear weapon, or an improvised nuclear device. An improvised nuclear device requires nuclear material design, and construction ability. Use of a radioactive dispersal device probably would not result in large numbers of casualties.However economic losses can be enormous. Non-Technical effects of nuclear trafficking (e.g. public panic, work disruption, etc.) and political and psychological consequences can far exceed technical consequences

  5. ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

    International Nuclear Information System (INIS)

    Romano, Stephen; Welling, Steven; Bell, Simon

    2003-01-01

    The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

  6. Training and improvement of professional person: multimedia training for radioactive material transport

    International Nuclear Information System (INIS)

    Sahyun, A.; Sordi, G.M.; Ghobril, C.N.

    2013-01-01

    The international transport of radioactive materials depends on national regulations of different countries, through which they pass. Therefore, it is necessary to learn the international recommendations in order to avoid contradictions among each country own regulations that can make radioactive materials transport impracticable. Information Technology and Communication has grown in Brazil and abroad, increasing demand for long distance learning, since it allows simultaneous training and education of a large number of geographically distant people in short time. The development of this first web-based course of transport for radioactive materials considered many advantages when compared to traditional courses, such as: agility in developing, translating and updating courses; facility of access and compatibility with various educational platforms all over the world. The course covers five topics. It presents regulations for transportation of dangerous materials and categorizes radioactive materials; it discusses the requirements and classification of radioactive material packing; ir discusses different risk labels and when they should be used; it presents responsibility and administrative requirements. Furthermore, considering the increasing use of mobile computing, the content is supposed to be automatically adjusted to different devices, allowing the user to make use of multiple access points without losing the sequence of the course. Initially developed in Portuguese and Spanish, this technology allows the dissemination of knowledge in Portuguese and Spanish spoken countries. It is our target to expand this Project, translating the course to other languages. The monitoring of access profiles and users feedback will guide the development of the next courses for the sector. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

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

  8. The role of the central registry in the safety and security of radioactive materials in Hungary

    International Nuclear Information System (INIS)

    Petoe, A.; Safar, J.; Turi, G.; Abonyi, T.

    2001-01-01

    After a brief overview of the Hungarian legislation and regulatory infrastructure the report provides information on the number of companies and licensees using radioactive materials and explains also the role of the established central registry of radiation sources and radioactive materials in Hungary for improving the safety and security of radioactive materials in the country. It concludes that a reliable nationwide central registry can be a very useful tool for increasing the safety and security of radiation sources and radioactive materials. (author)

  9. Compliance assurance in the field of radioactive material transport in Russia

    International Nuclear Information System (INIS)

    Ershov, V.; Syssoev, M.

    1999-01-01

    The main provisions of the system of compliance assurance, as understood in the IAEA Safety Regulations, are presented in this article as they are applied in Russia in the field of transport of radioactive materials. The urgency of the development and enactment of the uniform programme of compliance assurance in this area is underlined since it is foreseen by the new national regulations for the safety of radioactive material transport in Russia. (author)

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  12. System and Experiences in the Area of Radioactive Material Seizure Assurance

    International Nuclear Information System (INIS)

    Svoboda, K.; Podlaha, K.; Sir, D.

    2005-01-01

    In recent years, a number of radioactive seizures have been increased (i.e. the materials that contain one or more radionuclides and their activities from the point of view of radiation protection are not negligible). This is mainly due to newly installed technical equipment that monitors metal scrap resp. communal waste during its entry to metallurgical plants and iron works resp. incinerators or waste dumps. In the Nuclear research Institute Rez plc. (NRI Rez) was established a working group which provides, among other activities, full system of radioactive material seizure assurance. Part of this service contents also transport, storage, treatment, conditioning and disposal of the seizured radioactive source. This service was firstly established for communal waste dump, but other organizations can take advantage of this service not only for the seizures in communal waste dumps. The system of radioactive material seizure assurance is consisted of the following parts: (1) seizure on stationary detection system; (2) 24 hours emergency service of the working group; (3) event classification, detailed counting a tracking of radioactive source; (4) found radioactive source transport to NRI Rez for storage; (5) radioactive source characterization; (6) seizure evaluation and protocol providing; (7) State Office for Nuclear Safety (SONS) decree about next procedure. Stationary detection system ( detection gate ) is usually installed at the entry to dumps area, metallurgical plants, iron works etc. The detection gate traces changes of vehicle dose rate comparing to the average background by vehicle measurement. If the vehicle dose rate is significantly higher then the average background (usual alarm level is 10-30% above background), the vehicle is postponed by the gate operator and put aside on the determined place. Seizure is announced to the police of the Czech republic and to the SONS. Typical examples of the seizured radionuclide sources are: military, devices coated

  13. Natural radioactivity of building materials coming from a volcanic region

    International Nuclear Information System (INIS)

    Roca, V.; Pugliese, M.; Sabbarese, C.; D'Onofrio, A.; Lubritto, C.; Terrasi, F.; Ermice, A.; Inglima, I.; Migliore, G.

    2004-01-01

    Radioactivity was found to be very high in tuff and other materials originating from volcanic lava. Emanation of radon from such materials is appreciably higher than from materials of other origin. This work allowed us to obtain a first complete database of natural radioactivity concentrations in building materials from this region. Measurements were carried out by means of a gamma spectrometry system. Gamma emitting daughter products of 222 Rn were measured to determine 226 Ra. The samples, after a routine treatment, were accommodated in sealed metallic containers for a time sufficient for the equilibrium to establish. The determination of the radon emanation power was carried out by using an electrostatic monitor. Alpha spectroscopy of radon daughters was used to evaluate the content of radon coming from the sample

  14. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1994 ed

    International Nuclear Information System (INIS)

    1994-08-01

    This is the fifth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

  15. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

    International Nuclear Information System (INIS)

    1995-09-01

    This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

  16. Illicit trafficking of nuclear material and other radioactive sources

    International Nuclear Information System (INIS)

    Yilmazer, A.; Yuecel, A.; Yavuz, U.

    2001-01-01

    As it is known, for the fact that the illicit trafficking and trading of nuclear materials are being increased over the past few years because of the huge demand of third world states. Nuclear materials like uranium, plutonium, and thorium are used in nuclear explosives that have very attractive features for crime groups, terrorist groups and, the states that are willing to have this power. Crime groups that make illegal trade of nuclear material are also trying to market strategic radioactive sources like red mercury and Osmium. This kind of illegal trade threats public safety, human health, environment also it brings significant threat on world peace and world public health. For these reasons, both states and international organizations should take a role in dealing with illicit trafficking. An important precondition for preventing this kind of incidents is the existence of a strengthened national system for control of all nuclear materials and other radioactive sources. Further, Governments are responsible for law enforcement within their borders for prevention of illegal trading and trafficking of nuclear materials and radiation sources

  17. Directory of certificates of compliance for radioactive materials packages

    International Nuclear Information System (INIS)

    1991-10-01

    This directory contains a Report of NRC Approved Packages (Volume 1) for Radioactive Materials Packages. The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

  18. Calculations on safe storage and transportation of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

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

  19. Management System for Regulating Transport of Radioactive Material

    International Nuclear Information System (INIS)

    Lopez Vietri, J.R.; Capadona, N.M.; Barenghi, L.G.

    2011-01-01

    The objective of this paper is to describe the main characteristics of the Nuclear Regulatory Authority (Autoridad Regulatoria Nuclear - ARN) management system applied to the 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 TMR from now on. ARN's management system is integrally based on ISO 9000 system addressed to help organizations in designing and implementing their quality management systems. TMR process was split into five sub processes in order to facilitate the implementation of the system. Such sub processes were defined taking into account of the main functions developed by ARN in the branch of safe transport of radioactive materials. For each of this processes were specified their objectives, inputs, activities and outputs, clients and stakeholders, responsibilities, supporting documents, control of documents and records, control of non-conformances, monitoring and measurements, audits, feedback and improvement. Supporting documents for sub processes were issued, validated, reviewed and improved as an essential point to achieve continuous improving. Simultaneously, some indexes were defined to monitor and measures sub processes as a way to show objective evidence of conformity with objectives. Finally, as conclusions of this paper, they will be showed the main obstacles and troubleshooting found in the design and implementation of management system as well as their solutions and state of advance. (authors)

  20. Transport of radioactive materials and equipment. Requirements. (Provisional)

    International Nuclear Information System (INIS)

    1983-01-01

    This standard is aimed at establishing the procedures that must be followed when transporting radioactive materials and equipment in Venezuelan Territory. The ''Consejo Nacional para el Desarrollo de la Industria Nuclear'' is responsible for their fulfillment and control

  1. Regulatory control of radiation sources and radioactive materials: The UK position

    International Nuclear Information System (INIS)

    Englefield, C.; Holyoak, B.; Ledgerwood, K.; Littlewood, K.

    2001-01-01

    The paper presents the organizations involved in the regulation of the safety of radiation sources and the security of radioactive materials across the UK. The safety of radiation sources is within the regulatory remit of the Health and Safety Executive, under the Health and safety of Work Act 1974 and associated regulations. Any employer using radiation sources has a statutory duty to comply with this legislation, thereby protecting workers and the public from undue risk. From a radioactive waste management perspective, the storage and use of radioactive materials and the accumulation and disposal of radioactive waste are regulated by the environment agencies of England and Wales, Scotland, and Northern Ireland, under the Radioactive Substances Act 1993. Special regulatory arrangements apply to nuclear sites, such as power stations and fuel cycle plants, and some additional bodies are involved in the regulation of the security of fissile materials. An explanation is given in the paper as to how these organizations to work together to provide a comprehensive and effective regulatory regime. An overview of how these regulators have recently started to work more closely with other enforcement bodies, such as the Police and Customs and Excise is also given, to illustrate the approach that is being applied in the UK to deal with orphan sources and illicit trafficking. (author)

  2. IAEA regulatory initiatives for the air transport of large quantities of radioactive materials

    International Nuclear Information System (INIS)

    Luna, R.E.; Wangler, M.W.; Selling, H.A.

    1993-01-01

    The International Atomic Energy Agency (IAEA) has been laboring since 1988 over a far reaching change to its model regulations (IAEA, 1990) for the transport of radioactive materials (RAM). This change could impact the manner in which certain classes of radioactive materials are shipped by air and change some of the basic tenets of radioactive material transport regulations around the world. Few technical issues remain in determining the shape of the IAEA's revision of its regulations to accommodate air transport of large quantities of radioactive material. In the next two years the detailed wording of the regulations will be fully worked out and proposed for inclusion in SS6. Considering the breadth of the member state participation in the process, it seems likely that the approved version of the 1995 revision of SS6 will contain air mode revisions that move away from the predominantly mode independent character that characterized their first 30 years. (J.P.N.)

  3. Disposal of radioactive waste material to sea

    International Nuclear Information System (INIS)

    Burton, W.R.

    1985-01-01

    Radioactive waste liquid of a low or intermediate activity level is mixed with a suitable particulate material and discharged under the sea from a pipeline. The particulate material is chosen so that it sorbs radio-nuclides from this waste, has a good retention for these nuclides when immersed in sea water, and has a particle size or density such that transfer of the particles back to the shore by naturally occurring phenomena is reduced. Radio nuclide concentration in the sea water at the end of the pipeline may also be reduced. The particulate material used may be preformed or co-precipitated in the waste. Suitable materials are oxides or hydroxides of iron or manganese or material obtained from the sea-bed. (author)

  4. 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)

  5. Phosphated minerals to be used as radioactive reference materials

    International Nuclear Information System (INIS)

    Braganca, M.J.C.S.; Tauhata, L.; Clain, A.F.; Moreira, I.

    2003-01-01

    The production and the supplying of certified reference materials, or deliberated contaminated materials containing natural radionuclides for laboratories which analyses environmental samples are fundamentals for the correct measurements of their radioactive levels. This analysis quality represents a important step for the safeguards of the population health, and quality control of the imported and exported products, such as minerals, agricultural and raw materials. The phosphate rocks, containing significant concentrations of thorium, and used as raw material and fertilizers justified a study for better characterization and distinction to be used cas certified reference radioactive materials. Therefore, samples from the two carboanalytical-alkaline chimneys (Araxa and Catalao), and one from metasedimentar origin (Patos de Minas), distant 100 km from each other, were collected and chemical and cholecystographic characterized by optical emission, X-ray diffraction and fluorescence. The element concentrations were determined by neutron activation analysis, ICP-MS and ICP-AES. The results, after multivariate statistical analysis and study of correlations among elements, have shown geochemical similarities of the phosphates from Araxa and Catalao, and differences from Patos de Minas, despite of the geographic proximity. The concentration of thorium between 200 and 500 (mg/g) allows to use such minerals as reference materials

  6. Doses to road transport workers from radioactive materials

    International Nuclear Information System (INIS)

    Lawrence, B.E.; van der Vooren, A.

    1988-12-01

    Each year approximately 750,000 packages of radioactive materials are shipped throughout Canada. Regulatory controls on these shipments are designed to keep radiation doses received by transport workers well within acceptable limits. Since many of these workers are not monitored for radiation exposure, however, little factual information has been available in Canada to support theoretical estimates. A study to document actual radiation doses received by a select group of transport workers that is actively involved in the shipment of radioactive materials, was carried out in 1987 and 1988. This study involved the monitoring of 31 candidates from nine transport companies from across the country that handle medical isotopes, industrial isotopes, uranium fuel cycle materials and associated radioactive wastes. Each of the candidates (consisting of driver, dock workers, sorters, and supervisors) was issued personal thermoluminescent dosimeter (TLD) badges that were worn each day during the six month monitoring period. Some of the candidates were also issued cab or area dosimeters that were left in the cabs of the vehicles or in work areas so that the dose received in these areas could be differentiated from total personal exposure. During the monitoring program, the candidates filled out reporting sheets at the end of each working day to document information such as the quantity of materials handled, handling times and vehicle size. This information and the dosimetry data were used in the development of correlations between materials handled and doses reported so that doses for other handling similar materials could be estimated. Based on the results of the study, it was learned that while most of the transport workers receive doses that are at or near background levels, other (particularly those handling medical isotopes) are exposed to levels of radiation that may result in their receiving doses above the 5 mSv per annum limit set for members of the general public. On

  7. Promulgation order no. 546 of the 23rd June 1993. Executive order on transport of radioactive materials

    International Nuclear Information System (INIS)

    1993-01-01

    The Danish executive order no. 546 of June 23rd, 1993, concerning the transport of radioactive materials in pursuance of paragraph 2, section 1 of Law no. 94 of March 21, 1953 on the use etc. of radioactive materials are stipulated by order in accordance with paragraph 4 of the executive order no. 574 of November 20th, 1975, on precautionary measures related to the use etc. of radioactive materials. The 6 paragraphs comprising order no. 546 concern the transport of radioactive materials within Danish boundaries, transport of radioactive materials into Denmark from a country which is not a member of the European Community, transport of radioactive materials within the European Communities, the regulation that complaints with regard to decisions made by the (Danish) National Board of Health may be referred to the Ministry of the Interior within a period of four weeks and the regulation that violation of these regulations will be subject to punishment by fining in accordance with paragraph 5 of the law on use etc. of radioactive materials. The transport of radioactive materials into Denmark from a non-EC country can only take place as far as the National Board of Health (National Institute for Radiation Hygiene) has given authorization in each individual case, and transport of radioactive materials between the countries which are members of the European Community takes place under the regulatives of the Council of the European Communities' statutory order no. 93/1493 Euratom of June 8th, 1993 on transport of radioactive materials between member states. A supplementary text on the Council's statutory order (Euratom) no. 1493/93 is included. (AB)

  8. Tests on 'radio-active' material

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The storage of radio-active waste from nuclear power stations is a well known problem and a subject for extensive investigation. In connection with the use of cement as storage material, tests were carried out on cement-filled 200-litre sheet-steel containers. In order to avoid contamination of the cement core by drilling sludge, any drilling operation must be carried out dry, i.e. without liquid cooling. Air-blast cooling was therefore used for the cooling of a diamond drill and also for the removal of swarf. (H.E.G.)

  9. Material chemistry challenges in vitrification of high level radioactive waste

    International Nuclear Information System (INIS)

    Kaushik, C.P.

    2008-01-01

    Full text: Nuclear technology with an affective environmental management plan and focused attention on safety measures is a much cleaner source of electricity generation as compared to other sources. With this perspective, India has undertaken nuclear energy program to share substantial part of future need of power. Safe containment and isolation of nuclear waste from human environment is an indispensable part of this programme. Majority of radioactivity in the entire nuclear fuel cycle is high level radioactive liquid waste (HLW), which is getting generated during reprocessing of spent nuclear fuels. A three stage strategy for management of HLW has been adopted in India. This involves (i) immobilization of waste oxides in stable and inert solid matrices, (ii) interim retrievable storage of the conditioned waste product under continuous cooling and (iii) disposal in deep geological formation. Borosilicate glass matrix has been adopted in India for immobilization of HLW. Material issue are very important during the entire process of waste immobilization. Performance of the materials used in nuclear waste management determines its safety/hazards. Material chemistry therefore has a significant bearing on immobilization science and its technological development for management of HLW. The choice of suitable waste form to deploy for nuclear waste immobilization is difficult decision and the durability of the conditioned product is not the sole criterion. In any immobilization process, where radioactive materials are involved, the process and operational conditions play an important role in final selection of a suitable glass formulation. In remotely operated vitrification process, study of chemistry of materials like glass, melter, materials of construction of other equipment under high temperature and hostile corrosive condition assume significance for safe and un-interrupted vitrification of radioactive to ensure its isolation waste from human environment. The present

  10. Natural radioactivity in iron and steel materials by low-level gamma spectrometry

    International Nuclear Information System (INIS)

    Tanase, G.; Tanase, Maria

    2003-01-01

    High resolution low-level gamma spectrometry was applied to perform a radioactivity measurement in iron and steel raw materials (coal, coke, iron ore, pellets, manganese ore, limestone, dolomite), auxiliary materials (scorialite, oxide of Ti, bentonite), and some related final products (cast iron, slag, blast-furnace, flue dust) involved in iron making processing. We control the activity of materials in various kinds of samples and we investigate for transfer of radioactivity during the blast-furnace process. Artificial radioisotopes are rarely encountered. (authors)

  11. Status of Philippine regulatory infrastructure for the safe transport of radioactive materials

    International Nuclear Information System (INIS)

    Parami, V.K.; De Jesus, T.G.

    2004-01-01

    This paper presents some regulatory practices and experiences of the Philippine Nuclear Research Institute (PNRI) in ensuring safe transport of radioactive materials. The regulation and licensing the use of radioactive materials started in 1958. The number of packages containing radioactive materials transported into and within the country has increased with the increase number of licensees. During the period 2000-2002, the total number of licensees is 293, 311 and 311 respectively. The PNRI issues certificates of release and certificate of transport/authority to transport. Based on the data of certificates, the topmost sealed source shipments from abroad, mostly in type A package, are 192 Ir and 125 I for brachytherapy. For unsealed sources, also mostly in type A package, the topmost radioactive materials are 99m Tc (generators), 131 I, 201 Tl mainly for medical diagnosis. From the data on certificates of transport, the total number of packages inspected for the period 2000-2002 is 464, 577 and 747 respectively. The experiences in the enforcement of the transport regulations and the implication of issuing certificates of release and transport are discussed and recommendations are presented. (Authors)

  12. A simulation for radioactive decay and the absorption of radiation

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The purpose of this article is to derive and discuss these exponential laws for the benefit of teachers and interested pupils, and to discuss a simulation of the above phenoma should radioactive sources and Geiger-Mueller counters not be available in any particular school laboratory. The simulation can also be done by computer

  13. Guidance on radioactive waste management legislation for application to users of radioactive materials in medicine, research and industry

    International Nuclear Information System (INIS)

    1992-04-01

    This document, addressed primarily to developing countries, is restricted to management of radioactive wastes arising from uses of radionuclides in medicine, industry and research. It does not deal with wastes from the nuclear fuel cycle. Safeguards and physical protection are also outside the scope even though in some special cases it may be relevant; for instance, when fissile material is handled at research establishments. Information on nuclear fuel cycle waste management and waste transport can be found in a number of IAEA publications. The main aim of this document is to give guidance on legislation required for safe handling, treatment, conditioning and release or disposal of radioactive waste. It covers all steps from the production or import of radioactive material, through use, treatment, storage and transport, to the release or disposal of the waste either as exempted material or in special repositories. Management of radioactive wastes as a whole is optimized and kept at acceptable levels in accordance with the basic ICRP recommendations and the IAEA Basic Safety Standards. As a result of the new ICRP recommendations of 1991, the Agency is revising its Basic Safety Standards, the results of which may have some impact on the national regulations and necessitate updating of this document. 16 refs, 1 fig

  14. Compilation of current literature on seals, closures, and leakage for radioactive material packagings

    International Nuclear Information System (INIS)

    Warrant, M.M.; Ottinger, C.A.

    1989-01-01

    This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs

  15. Study on cementation of simulated radioactive borated liquid wastes

    International Nuclear Information System (INIS)

    Sun Qina; Li Junfeng; Wang Jianlong

    2010-01-01

    To compare sulfoaluminate cement with ordinary Portland cement on their cementation of radioactive borated liquid waste and to provide more data for formula optimization, simulated radioactive borated liquid waste were solidified by the two cements. 28 d compressive strength and strength losses after water/freezing/irradiation resistance tests were investigated. Leaching test and X-ray diffraction analysis were also conducted. The results show that it is feasible to solidify borated liquid wastes with sulfoaluminate cement and ordinary Portland cement with formulas used in the study. The 28 d compressive strengths, strength losses after tests and simulated nuclides leaching rates of the solidified waste forms meet the demand of GB 14569.1-93. The sulfoaluminate cement formula show better retention of Cs + than ordinary Portland cement formula. Boron, in form of B (OH) 4 - , incorporate in ettringite as solid solutions. (authors)

  16. 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

  17. Manufacturing method for radioactive material containing vessel

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  18. Terrain and building effects on the transport of radioactive material at a nuclear site

    International Nuclear Information System (INIS)

    Jeong, Hyojoon; Park, Misun; Jeong, Haesun; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

    2014-01-01

    Highlights: • This study is to quantify the building and terrain effects on the atmospheric dispersion. • Statistical methods with AERMOD-PRIME and CFD were used. • To assess the risk in nuclear power plants, terrain and building effects have to be considered. - Abstract: This study identified the terrain and building effects on the atmospheric dispersion of radioactive materials at the Wolsong Nuclear Site. To analyze the atmospheric dispersion of radioactive materials, the AERMOD-PRIME model, CFD model and meteorological data from 2010 were used. The terrain and building effects on the atmospheric dispersion of radioactive materials within a 1 km radius of the site were statistically significant. The maximum concentration of the radioactive material increased by 7 times compared to the concentration when the terrain and building effects were not considered. It was found that the terrain and building influenced the decrease in the concentration of radioactive material in a concentric circle with a 914 m radius from the center of the site. The concentration of radioactive material in a concentric circle with a 350 m radius was two-times higher than the concentration estimated at the backside of the building, which is the downwind side, without any consideration of the terrain and building effects. In consideration of the Korean situation, in which multiple nuclear reactors are built on the same nuclear site, it is necessary to evaluate the risk that may affect workers and nearby residents by reflecting the terrain and building effects

  19. Regulatory requirements for the transport of radioactive materials in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Garg, R. [Canadian Nuclear Safety Commission, Ottawa (Canada)

    2004-07-01

    Canada is a major producer and shipper of radioactive material. Each year more than a million packages are transported in Canada. The safety record with the transport of RAM in Canada has historically been excellent. There have never been any serious injuries, overexposure or fatality or environmental consequences attributable to the radioactive nature of such material being transported or being involved in a transport accident. In Canada, the Canadian Nuclear Safety Commission (CNSC) is the prime agency of the federal government entrusted with regulating all activities related to the use of nuclear energy and nuclear substances including the packaging and transport of nuclear substances. The mission of the CNSC is to regulate the use of nuclear energy and materials to protect health, safety, security of the person and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. The division of responsibility for the regulation of transport of radioactive material has been split between Transport Canada and the CNSC. The governing Transport Canada's regulations are Transport of Dangerous Goods (TDG) Regulations and the CNSC regulations are Packaging and Transport of Nuclear Substances Regulations (PTNSR). Canada has actively participated in the development of the IAEA regulations for the safe transport of radioactive material since 1960. As an IAEA member state, Canada generally follows the requirements of IAEA regulations with few deviations. The Nuclear Safety and Control Act (NSCA) strongly supports Canada's international obligations to ensure safe packaging, transport, storage and disposal of nuclear substances, prescribed equipment and prescribed information. Prescribed equipment and prescribed information are defined in the CNSC General Nuclear Safety and Control Regulations. This paper presents the current CNSC regulatory requirements and initiatives taken by the CNSC to improve its effectiveness and

  20. Regulatory requirements for the transport of radioactive materials in Canada

    International Nuclear Information System (INIS)

    Garg, R.

    2004-01-01

    Canada is a major producer and shipper of radioactive material. Each year more than a million packages are transported in Canada. The safety record with the transport of RAM in Canada has historically been excellent. There have never been any serious injuries, overexposure or fatality or environmental consequences attributable to the radioactive nature of such material being transported or being involved in a transport accident. In Canada, the Canadian Nuclear Safety Commission (CNSC) is the prime agency of the federal government entrusted with regulating all activities related to the use of nuclear energy and nuclear substances including the packaging and transport of nuclear substances. The mission of the CNSC is to regulate the use of nuclear energy and materials to protect health, safety, security of the person and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. The division of responsibility for the regulation of transport of radioactive material has been split between Transport Canada and the CNSC. The governing Transport Canada's regulations are Transport of Dangerous Goods (TDG) Regulations and the CNSC regulations are Packaging and Transport of Nuclear Substances Regulations (PTNSR). Canada has actively participated in the development of the IAEA regulations for the safe transport of radioactive material since 1960. As an IAEA member state, Canada generally follows the requirements of IAEA regulations with few deviations. The Nuclear Safety and Control Act (NSCA) strongly supports Canada's international obligations to ensure safe packaging, transport, storage and disposal of nuclear substances, prescribed equipment and prescribed information. Prescribed equipment and prescribed information are defined in the CNSC General Nuclear Safety and Control Regulations. This paper presents the current CNSC regulatory requirements and initiatives taken by the CNSC to improve its effectiveness and efficiency

  1. Application of ion beams in materials science of radioactive waste forms: focus on the performance of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Garrido, Frederico [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France)]. E-mail: garrido@csnsm.in2p3.fr; Nowicki, Lech [Andrzej Soltan Institute for Nuclear Studies, Hoza 69, 00-681 Warsaw (Poland); Thome, Lionel [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Ba-hat timents 104-108, 91405 Orsay Campus (France)

    2005-10-15

    Ion beam techniques provide unique tools for the qualification of radioactive waste forms. They address three major issues: (i) the simulation by ion irradiation of the stability of a matrix submitted to radiative environment; (ii) the doping of a material with stable or radioactive elements which simulate the species to be confined; (iii) the characterisation of a material via nuclear microanalysis techniques. Among various classes of nuclear matrices the spent nuclear fuel is widely considered as a potential candidate for the stabilisation of radioactive wastes in scenarios of long term interim storage or final geological disposal. Illustrative examples revealing the potentialities of the use of ion beams either as a pure characterisation tool - to investigate the chemical stability of the UO{sub 2} matrix under an oxygen potential - or in a combined way (e.g. irradiation/characterisation, doping/characterisation) - to explore the radiation stability and the behaviour of foreign species - are presented. Transformations (stoichiometry, depth and structure of growing hyperstoichiometric U{sub 4}O{sub 9}/U{sub 3}O{sub 7} oxides) occurring during low-temperature air oxidation of uranium dioxide single crystals are reported. Swift heavy ion irradiation of UO{sub 2} single crystals leads to a peculiar single crystal-polycrystal transformation (i.e. polygonisation of the fluorite-type structure of the material). Irradiation of UO{sub 2} at low energy shows that the damage production is directly linked to the energy deposited in nuclear elastic collisions. The lattice location of helium atoms (generated in large amount during the storage period) in interstitial octahedral positions is discussed.

  2. Reconnaissance for radioactive materials in northeastern United States during 1952

    Science.gov (United States)

    McKeown, Francis A.; Klemic, Harry

    1953-01-01

    Reconnaissance for radioactive materials was made in parts of Maine, New York, New Jersey, and Pennsylvania. The primary objective was to examine the iron ore deposits and associated rocks in the Adirondack Mountains of New York and the Highlands of New Jersey. In addition, several deposits known or reported to contain radioactive minerals were examined to delimit their extent. Most of the deposits examined are not significant as possible sources of radioactive elements and the data pertaining to them are summarized in table form. Deposits that do warrant more description than can be given in table form are: Benson Mines, St. Lawrence County, N. Y.; Rutgers mine, Clinton County, N. Y.; Mineville Mines, Essex County, N. Y.l Canfield phosphate mine, Morris County, N. J.; Mullgan quarry, Hunterdon County, N. J.; and the Chestnut Hill-Marble Mountain area, Pennsylvania and New Jersey. The Old Bed in the Mineville district is the only deposit that may be economically significant. Apatite from Old Bed ore contains as much as 4.9 percent total rare earth. 0.04 percent thorium, and 0.018 percent uranium. Magnetite ore at the Rutgers mine contains radioactive zircon and apatite. Radioactivity measurements of outcrops and dump material show that the ore contains from 0.005 to 0.010 percent equivalent uranium. One sample of lean magnetite ore contains 0.006 percent equivalent uranium. Garnet-rich zones in the Benson Mines magnetite deposit contain as much as 0.017 equivalent uranium. Most of the rock and ore, however, contains about 0.005 percent equivalent uranium. Available data indicate that the garnet-rich zones are enriched in radioactive allanite. A shear zone in the Kittatinny limestone of Cambrian age at the Mulligan quarry contains uraniferous material. Radioactivity anomalies elsewhere in the quarry and in adjacent fields indicate that there may be other uraniferous shear zones. Assays of samples and measurements of outcrop radioactivity indicate that the uranium

  3. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1993 ed

    International Nuclear Information System (INIS)

    1993-10-01

    This is the fourth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose memberships consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

  4. Directory of national competent authorities` approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA`s transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ``Regulations for the Safe Transport of Radioactive Material`` highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs.

  5. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1999 Edition

    International Nuclear Information System (INIS)

    1999-08-01

    This is the tenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Advisory Committee (TRANSSAC), formerly known as the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM and endorsed by TRANSSAC, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  7. 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

  8. Determination of Natural Radioactivity in Building Materials with Gamma Spectrometry

    International Nuclear Information System (INIS)

    Turki, Faten

    2010-01-01

    In the setting of this work, the natural radioactivity of building materials used in Tunisia has been measured by gamma spectrometry. These products have been ground and dried at 100 degree for 12 h. Then, they have been homogenized, weighed and finally conditioned during 23 days in order to reach the radioactive equilibrium. The measures' results proved that all building materials studied except bauxite and the ESC clay, possess doses lower than the acceptable limit (1 mSv.an-1). However, the possibility of reinforcement of the natural radioactivity in some industry of building can exist. To insure that the cement, the most used in the world, don't present any radiological risk on the workers' health, a survey has been made in the factory - les Ciments de Bizerte - about its manufacture's process. The results of this survey showed that this product can be considered like a healthy product.

  9. Regulations for the Safe Transport of Radioactive Material, 2009 ed. Safety Requirements

    International Nuclear Information System (INIS)

    2009-01-01

    This publication establishes the regulations that are applied to the transport of radioactive material by all modes of transport on land, water or in the air, including transport that is incidental to the use of the radioactive material. The objective and scope of the regulations are described in detail as well as the range of their application. The publication provides requirements useful to governments, regulators, operators of nuclear and radiation facilities, carriers, users of radiation sources and cargo handling personnel. Contents: 1. Introduction; 2. Definitions; 3. General provisions; 4. Activity limits and classification; 5. Requirements and controls for transport; 6. Requirements for radioactive materials and for packagings and packages; 7. Test procedures; 8. Approval and administrative requirements; Annex I: Summary of approval and prior notification requirements; Annex II: Conversion factors and prefixes.

  10. Calculation of Airborne Radioactivity Hazard from Machining Volume-Activated Materials

    International Nuclear Information System (INIS)

    E.T. Marshall; S.O. Schwahn

    1997-01-01

    When evaluating a task involving the machining of volume-activated materials, accelerator health physicists must consider more than the surface contamination levels of the equipment and containment of loose shavings, dust or filings. Machining operations such as sawing, routing, welding, and grinding conducted on volume-activated material may pose a significant airborne radioactivity hazard to the worker. This paper presents a computer spreadsheet notebook that conservatively estimates the airborne radioactivity levels generated during machining operations performed on volume-activated materials. By knowing (1) the size and type of materials, (2) the dose rate at a given distances, and (3) limited process knowledge, the Derived Air Concentration (DAC) fraction can be estimated. This tool is flexible, taking into consideration that the process knowledge available for the different materials varies. It addresses the two most common geometries: thick plane and circular cylinder. Once the DAC fraction has been estimated, controls can be implemented to mitigate the hazard to the worker

  11. Calculation of airborne radioactivity hazard from machining volume-activated materials

    International Nuclear Information System (INIS)

    Marshall, E.T.; Schwahn, S.O.

    1996-10-01

    When evaluating a task involving the machining of volume-activated materials, accelerator health physicists must consider more than the surface contamination levels of the equipment and containment of loose shavings, dust or filings. Machining operations such as sawing, routing, welding, and grinding conducted on volume-activated material may pose a significant airborne radioactivity hazard to the worker. This paper presents a computer spreadsheet notebook that conservatively estimates the airborne radioactivity levels generated during machining operations performed on volume-activated materials. By knowing (1) the size and type of materials, (2) the dose rate at a given distances, and (3) limited process knowledge, the Derived Air Concentration (DAC) fraction can be estimated. This tool is flexible, taking into consideration that the process knowledge available for the different materials varies. It addresses the two most common geometries: thick plane and circular cylinder. Once the DAC fraction has been estimated, controls can be implemented to mitigate the hazard to the worker

  12. Environmental impacts of the transportation of radioactive materials in urban areas

    International Nuclear Information System (INIS)

    Finley, N.C.; Taylor, J.M.; Daniel, S.L.; Ericson, D.M. Jr.

    1980-01-01

    Radioactive material transport in urban areas is investigated and the specific urban features which influence environmental impacts are addressed. These features include the geographic and demographic make-up, and vehicular population and transportation patterns in the area. Previous efforts have not identified a most important population exposure pathway or group. This assessment examines several pathways and a number of urban specific population groups to evaluate their relative significance. In addition, because different causative events contribute to the overall environmental impacts, this assessment addresses four of these: incident free transport, vehicular accidents, human errors, and sabotage or malevolent acts. Not only does radioactive material transport produce radiological and economic consequences but also it can have social impacts. The objective of this study is to examine both the quantitative environmental impacts of radioactive material transport in urban areas and the more subjective social effects of this process. The social impacts assessment was performed by Battelle Human Affairs Research Centers, Seattle, Washington and their conclusions are only summarized here

  13. A manual for implementing residual radioactive material guidelines

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Yu, C.; Yuan, Y.C.; Zielen, A.J.; Jusko, M.J.; Wallo, A. III; Argonne National Lab., IL; Dames and Moore, West Valley, NY; Argonne National Lab., IL; USDOE Assistant Secretary for Nuclear Energy, Washington, DC

    1989-06-01

    This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) and the Surplus Facilities Management Program (SFMP). It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. 36 refs., 16 figs, 22 tabs

  14. Securing the Chernobyl exclusion zone against illegal movement of radioactive materials

    International Nuclear Information System (INIS)

    Bondarenko, O. O.; Proskura, M. I.; Duftschmid, K. E.; Kravchencko, N. E.

    2004-01-01

    . Within the framework of the IAEA Nuclear Security Program the technical cooperation project S trengthening Security of Nuclear Materials in Ukraine ( UKR/0/008) is aimed primarily to strengthen protection the entrance/exit checkpoints of the Chernobyl exclusion zone and adjacent State borders of Ukraine against illicit movement of radioactive materials (including nuclear materials). The particular situation of the exclusion zone presents a high risk of uncontrolled movement of radioactive materials from and into the exclusion zone. In view of the future construction of the S helter-2 a nd decommissioning of the three closed reactor blocks it is expected that the traffic through the exclusion zone will considerably increase in the next years and those large amounts of possibly contaminated metal scrap, construction material and equipment will leave the zone. There is also a risk of illegal movement of radioactive waste into the zone, possibly also through the international border, which could make the zone to an illegal dumping ground for radioactive waste. As practice shows theft of nuclear materials cannot be excluded. The general concept of the project is based on modernization of old and deployment of new vehicle (road and railway) and pedestrian monitoring equipment at all checkpoints of the exclusion zone including road checkpoints, train stations and river ports. A central station of data acquisition and management is to be located in Chernobyl. The equipment to be installed has to meet new technical requirements developed by IAEA. This includes, e.g. sensitivity of gamma and neutron detection, identification of innocent alarms caused by NORM materials or medical radioisotopes, accurate indication of the source position in the vehicle, and remote identification of license plate by advanced video systems. The implementation of the project and deployment of the equipment is expected to start in 2003 and should be completed in 2005. (Author)

  15. Safe and secure: transportation of radioactive materials

    International Nuclear Information System (INIS)

    Howe, D.

    2015-01-01

    Western Waste Management Facility is Central Transportation Facility for Low and Intermediate waste materials. Transportation support for Stations: Reactor inspection tools and heavy water between stations and reactor components and single bundles of irradiated fuel to AECL-Chalk River for examination. Safety Track Record: 3.2 million kilometres safely travelled and no transportation accident - resulting in a radioactive release.

  16. French National Plan for the Management of Radioactive Materials and Waste (PNGMDR) - 2010-2012

    International Nuclear Information System (INIS)

    2009-01-01

    Faced with the high diversity of radioactive materials and waste, it may be difficult to grasp the relevance and consistency of the installed management framework. The purpose of the National Plan for the Management of Radioactive Materials and Waste (PNGMDR) is to clarify this management framework and improve it. To this end, it draws up an assessment of the management policy, evaluates the needs and determines the objectives to be attained in the future. The PNGMDR's usefulness was confirmed by Parliament. The evaluation report of the PNGMDR 2007-2009 by the Parliamentary Office for Evaluation of Scientific and Technological Options thus indicates that 'the interest of a summary document exposing all the problems and the solutions related to the management of radioactive waste was underlined a number of times by the Office. Since such a plan can allow achieving exhaustiveness and introducing a consistency in the management of radioactive waste, the Office deemed it necessary that it be linked to the law in one way or another. Conforming to the Office's recommendations, the Act of 28 June 2006 related to the sustainable management of radioactive waste stipulated that such a plan must be elaborated, updated every three years and published, extending its scope to reusable radioactive materials'. Thus, the PNGMDR provides the public with a global vision of the management of radioactive materials and waste, concerning both topics 'in the news' and those less publicised. Some waste, in fact, attracts momentarily particular attention, for example, on the occasion of a search for a disposal site, such as in 2008-2009, for so-called low level and long lived ('LL-LL') waste. The media also broadcast in 2008 and 2009 special enquiries on the management of mining residues and on reprocessed uranium; all these topics are discussed in detail in the PNGMDR. Other waste topics attract less attention, such as sealed radioactive sources, which are more dispersed throughout France

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

    International Nuclear Information System (INIS)

    Hartnett, C.

    1994-01-01

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

  18. Final environmental statement on the transportation of radioactive material by air and other modes

    International Nuclear Information System (INIS)

    1977-12-01

    An assessment is presented of the environmental impact from transportation of shipments of radioactive material into, within, and out of the United States. It is intended to serve as background material for a review by the United States Nuclear Regulatory Commission (NRC) of regulations dealing with transportation of radioactive materials. The impetus for such a review results not only from a general need to examine regulations to ensure their continuing consistency with the goal of limiting radiological impact to a level that is as low as reasonably achievable, but also from a need to respond to current national discussions of the safety and security aspects of nuclear fuel cycle materials. Chapters are included on regulations governing the transportation of radioactive materials, radiological effects, transport impact under normal conditions, impacts of transportation accidents, alternatives, and security and safeguards. A standard shipments model is also included along with a demographic model, excerpts from federal regulations, data on Pu, Population dose formulas, a list of radioactive material incidents, accident analysis methodology, and an analysis of risk assessment sensitivity

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

    International Nuclear Information System (INIS)

    Vahlbruch, Jan-Willem

    2015-01-01

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

  20. Sor/89-426, 24 August 1989, transport packaging of radioactive materials regulations, amendment

    International Nuclear Information System (INIS)

    1989-09-01

    These Regulations of 24 September 1983 were amended mainly to clarify the original text and further specify certain requirements. In particular, the definitions of A 1 , A 2 , Fissile Class III package and special Form Radioactive Material have been revoked and replaced by new definitions. Also, a new condition has been added regarding Special Form Radioactive Material. Henceforth, no such material may be transported without a certificate attesting that the material meets the requirements set out in Schedule XII of the Regulations [fr