Functional requirements document for measuring emissions of airborne radioactive materials

International Nuclear Information System (INIS)

Glissmeyer, J.A.; Alvarez, J.L.; Hoover, M.D.; Newton, G.C.; McFarland, A.R.; Rodgers, J.C.

1994-11-01

This document states the general functional requirements for systems and procedures for measuring emissions of airborne radioactive materials from facilities administered by the Westinghouse Hanford Company (WHC). The following issues are addressed in this document: lg-bullet definition of the program objectives lg-bullet selection of the overall approach to collecting the samples lg-bullet sampling equipment design lg-bullet sampling equipment maintenance and quality assurance issues. The following issues are not addressed in this document: lg-bullet air sampling in work areas or containments lg-bullet selection of specific on-line sample monitoring instrumentation lg-bullet analyzing collected samples lg-bullet reporting and interpreting results. The document provides equipment design guidance that is performance based rather than prescriptive. Locations from which samples are obtained should exhibit mixing of the contaminants with the airstream and acceptable air flow characteristics. Sample collection equipment and effluent and sample flow elements should meet defined performance standards. Quality control and assurance requirements specific to sample collection, equipment inspection, and calibration are presented. Key sample collection performance requirements are summarized in Section 5.4. The intent of this document is to assist WHC in demonstrating a high quality of air emission measurements with verified system performance based on documented system design, testing, inspection, and maintenance

Experiences in monitoring airborne radioactive contamination in JAERI

International Nuclear Information System (INIS)

Ikezawa, Y.; Okamoto, T.; Yabe, A.

1980-01-01

The following results were obtained at the Japan Atomic Energy Research Institute (JAERI) from experience in air monitoring at the hot cells for handling highly radioactive materials, the glove box containing plutonium and the cell for producing 99 Mo. (1) The ratios of activities of airborne dust to those of whole dust were of the order of 10 -2 for the semi-volatile form of 125 Sb, and 10 -3 to 10 -4 for the particulate form of 137 Cs, 144 Ce and 144 Pr, when irradiated fuels were cut in the hot cells. (2) The activity median aerodynamic diameter (AMAD) of airborne particle size distributions varied from O.4 to 15 μm with changing geometric standard deviation (sigmasub(g)) 1.7 to 7, depending on types of metallurgical treatment of fuels and on kinds of work in the cells. (3) A resuspension factor (the ratio of the concentration of airborne contamination to the surface contamination) was found to be 4x10 -8 to approximately 2x10 -7 cm -1 for plutonium oxide deposited on the floor surface. (4) The collection efficiency of the charcoal-loaded filter paper for airborne radioiodine, consisting of 60% inorganic and 40% organic iodide, was over 95% under conditions of relative humidity 40 to approximately 80% and face velocity 50 cm/sec, during the production of 99 Mo. (H.K.)

Radioactive airborne species formed in the air in high energy accelerator tunnels

International Nuclear Information System (INIS)

Kondo, K.

2005-01-01

Many radioactive airborne species have been observed in the air of high energy accelerator tunnels during machine operation. Radiation protection against these induced airborne radioactivities is one of the key issues for radiation safety, especially at high-energy and high-intense proton accelerators such as the J-PARC (Japan Proton Accelerator Research Complex, Joint project of KEK and JAERI), which is now under construction at the TOKAI site of JAERI. Information on the chemical forms and particle sizes of airborne radioactivities is essential for the estimation of internal doses. For that purpose, the study on radioactive airborne species formed in the air of beam-line tunnels at high-energy accelerators have been extensively conducted by our group. For Be-7, Na-24, S-38, Cl-38,-39, C-11, and N-13, formed by various types of nuclear reactions including nuclear spallation reactions, their aerosol and gaseous fractions are determined by a filter technique. A parallel plate diffusion battery is used for the measurement of aerosol size distributions, and the formation of radioactive aerosols is explained by the attachment of radionuclides to ambient non-radioactive aerosols which are formed through radiation induced reactions. The chemical forms of gaseous species are also determined by using a selective collection method based on a filter technique. A review is given of the physico-chemical properties of these airborne radionuclides produced in the air of accelerator beam-line tunnels.

Optimization of the retention of radioactive material from the airborne effluents of reprocessing plants

International Nuclear Information System (INIS)

Bonka, H.; Horn, H.-G.

1984-01-01

The radiation-protection ordinance of the Federal Republic of Germany does not know the expression 'optimization in radiological protection'. In order to gain experiences with the cost-benefit analysis for the retention of radioactive material from nuclear facilities as proposed in ICRP 26, this method has been applied on the emission of radioactive material with the airborne effluents of reprocessing plants. The reference plant has an annual throughput of 1500 t of spent LWR-fuel. Basing on this plant, two smaller plants (350 t/a, 700 t/a) are also analysed. The cost-benefit-analysis is carried-out for H3, C14, Kr85, J129 and aerosols. For these nuclides as well as for the three plant-sizes, the methods of retention, the estimated annual costs of retention, the emission rates for the different retention measures and the resulting collective-dose commitments are shown. Based on an α-value of 8000 $/man-Sv (20,000 DM/Man-Sv) the cost-benefit analysis shows no optimum for H3 and Kr 85. The optimum C14 as well as iodine retention is a high-efficiency scrubber and an iodine filter, respectively for the dissolver off-gas. For aerosols the cost-benefit analysis shows an optimum for the filtration of the dissolver off-gas by means of HEPA filters. For the other aerosol-sources, condensation, scrubbing and additional droplet separation from the off-gas is optimum. Reasons differing from cost-benefit analysis require HEPA filters for all major aerosol-sources. (author)

Assessment of inhalation dose sensitivity by physicochemical properties of airborne particulates containing naturally occurring radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Kim, Si Young; Choi, Cheol Kyu; Kim, Yong Geon; Choi, Won Chul; Kim, Kwang Pyo [Kyung Hee University, Seoul (Korea, Republic of)

2015-12-15

Facilities processing raw materials containing naturally occurring radioactive materials (NORM) may give rise to enhanced radiation dose to workers due to chronic inhalation of airborne particulates. Internal radiation dose due to particulate inhalation varies depending on particulate properties, including size, shape, density, and absorption type. The objective of the present study was to assess inhalation dose sensitivity to physicochemical properties of airborne particulates. Committed effective doses to workers resulting from inhalation of airborne particulates were calculated based on International Commission on Radiological Protection 66 human respiratory tract model. Inhalation dose generally increased with decreasing particulate size. Committed effective doses due to inhalation of 0.01μm sized particulates were higher than doses due to 100μm sized particulates by factors of about 100 and 50 for {sup 238}U and {sup 230}Th, respectively. Inhalation dose increased with decreasing shape factor. Shape factors of 1 and 2 resulted in dose difference by about 18 %. Inhalation dose increased with particulate mass density. Particulate mass densities of 11 g·cm{sup -3} and 0.7 g·cm{sup -3} resulted in dose difference by about 60 %. For {sup 238}U, inhalation doses were higher for absorption type of S, M, and F in that sequence. Committed effective dose for absorption type S of {sup 238}U was about 9 times higher than dose for absorption F. For {sup 230}Th, inhalation doses were higher for absorption type of F, M, and S in that sequence. Committed effective dose for absorption type F of {sup 230}Th was about 16 times higher than dose for absorption S. Consequently, use of default values for particulate properties without consideration of site specific physiochemical properties may potentially skew radiation dose estimates to unrealistic values up to 1-2 orders of magnitude. For this reason, it is highly recommended to consider site specific working materials and

Occupational exposure of phosphate mine workers: airborne radioactivity measurements and dose assessment

International Nuclear Information System (INIS)

Khater, Ashraf E.; Hussein, M.A.; Hussein, Mohamed I.

2004-01-01

Under the Egyptian program for radiation safety and control, airborne radioactivity measurements and radiological dose assessment were conducted in some phosphate and uranium mines. Abu-Tartor mine is one of the biggest underground phosphate mines in Egypt. Airborne radioactivity, radon ( 222 Rn) and its short-lived decay products (progenies) and thoron ( 220 Rn), were measured in selected locations along the mine. The environmental gamma and workers dose equivalent rate (mSv/y) were measured inside and outside the mine using thermo-luminescence dosimeters (TLD). The results were presented and discussed. The calculated annual effective dose due to airborne radioactivity is the main source of occupational exposure and exceeding the maximum recommended level by ICRP-60 inside the mine tunnels. A number of recommendations are suggested to control the occupational exposures

Airborne radioactive effluents: releases and processing

International Nuclear Information System (INIS)

Grissom, M.C.

1982-10-01

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

The Periodic Measurement of the Airborne Radioactivity In Controlled Area of KOMAC

Energy Technology Data Exchange (ETDEWEB)

Park, Jeong-Min; Park, Sung-Kyun; Min, Yi-Sub; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Korea Multipurpose Accelerator Complex (KOMAC) to start the performance operation in the second half of 2013, is currently operated in each beamline 20-MeV and 100-MeV. The accelerator operation period is simply divided by three operation cycles which are the maintenance checks period for accelerator device, the performance test period before driving accelerator and the operation period. During this operation period, beam is irradiated to target. At this time, the proton beams collide with the target material and a high dose of radiations such as gamma ray and neutron occurred. Radiation controlled area at the accelerator facility is divided into accelerator tunnel and beam utilization zone. As a result of measuring the airborne radioactivity in the controlled area in accordance with the operating cycle of the proton accelerator KOMAC, It was confirmed that the value of the airborne radioactivity does not significantly differ according to each accelerator operating cycles. And alpha and beta values measured inside the area that workers primarily work is very low indoor radon level than the value of the recommendations in multiple facilities.

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)

Krypton-85 and other airborne radioactivity measurements throughout Ireland

International Nuclear Information System (INIS)

Smith, K.J.; Murray, M.; Wong, J.; Sequeira, S.; Long, S.C.; Rafferty, B.

2004-01-01

In compliance with articles 35 and 36 of the EURATOM Treaty, the Radiological Protection Institute of Ireland (RPII) undertakes a comprehensive programme of radioactivity monitoring in the Irish terrestrial environment. Radioactivity is present in the terrestrial environment due to natural processes, the testing of nuclear weapons in the atmosphere, accidents such as the Chernobyl accident and the routine discharge of radionuclides from nuclear installations. The RPII monitors airborne radioactivity concentrations at ten stations throughout Ireland, of which, nine are equipped with low volume particulate samplers and one, in Dublin, with a high volume particulate sampler. The low volume particulate samples are assessed for total beta activity and high volume samples for gamma emitting radionuclides such as caesium-137 and beryllium-7. In addition, air sampled at the RPII laboratory in Dublin, is monitored for krypton-85, a radioactive noble gas, released into the environment primarily as a result of the reprocessing of nuclear fuel at installations such as Sellafield in the UK and La Hague in France. Since the inception of the krypton measurements in 1993 a trend of increasing atmospheric concentrations has been observed. The results of the krypton-85 monitoring, as well as the airborne radioactivity concentration measurements, will be presented and discussed in this paper. (author)

Radioactive materials released from nuclear power plants

International Nuclear Information System (INIS)

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

1991-05-01

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

Changing methodology for measuring airborne radioactive discharges from nuclear facilities

International Nuclear Information System (INIS)

Glissmeyer, J.A.; Ligotke, M.W.

1995-05-01

The US Environmental Protection Agency (USEPA) requires that measurements of airborne radioactive discharges from nuclear facilities be performed following outdated methods contained in the American National Standards Institute (ANSI) N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities. Improved methods are being introduced via two paths. First, the ANSI standard is being revised, and second, EPA's equivalency granting process is being used to implement new technology on a case-by-case or broad basis. The ANSI standard is being revised by a working group under the auspices of the Health Physics Society Standards Committee. The revised standard includes updated methods based on current technology and a performance-based approach to design. The performance-based standard will present new challenges, especially in the area of performance validation. Progress in revising the standard is discussed. The US Department of Energy recently received approval from the USEPA for an alternate approach to complying with air-sampling regulations. The alternate approach is similar to the revised ANSI standard. New design tools include new types of sample extraction probes and a model for estimating line-losses for particles and radioiodine. Wind tunnel tests are being performed on various sample extraction probes for use at small stacks. The data show that single-point sampling probes are superior to ANSI-Nl3.1-1969 style multiple-point sample extraction probes

Airborne radionuclide waste-management reference document

International Nuclear Information System (INIS)

Brown, R.A.; Christian, J.D.; Thomas, T.R.

1983-07-01

This report provides the detailed data required to develop a strategy for airborne radioactive waste management by the Department of Energy (DOE). The airborne radioactive materials of primary concern are tritium (H-3), carbon-14 (C-14), krypton-85 (Kr-85), iodine-129 (I-129), and radioactive particulate matter. The introductory section of the report describes the nature and broad objectives of airborne waste management. The relationship of airborne waste management to other waste management programs is described. The scope of the strategy is defined by considering all potential sources of airborne radionuclides and technologies available for their management. Responsibilities of the regulatory agencies are discussed. Section 2 of this document deals primarily with projected inventories, potential releases, and dose commitments of the principal airborne wastes from the light water reactor (LWR) fuel cycle. In Section 3, dose commitments, technologies, costs, regulations, and waste management criteria are analyzed. Section 4 defines goals and objectives for airborne waste management

Airborne and truck-borne ``radiation footprints`` of areas producing, storing, using or being exposed to nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Pavlik, B; Bottos, F [Picodas Group Inc., Richmond Hill, ON (Canada); Cuneen, P J [World Geoscience Corp. Ltd., Perth (Australia); Jurza, P; Hoeschl, V [Picodas Prague s.r.o., Prague (Czech Republic)

1997-11-01

The paper discusses the use of advanced Airborne Gamma Ray Spectrometer for environmental assessment of nuclear radiation in areas exposed to radioactive materials. The use of high capacity real time processors operating in parallel mode packaged into one mechanical enclosure together with navigation, allows implementation of highly sophisticated proprietary algorithms to produce results in absolute physical units. Airborne footprinting provides rapid, well defined spatial images of natural and manmade radioactive contamination. Integrated GPS guidance systems provides instant position information related to the internal geographical data base. Short time span of data acquisition provides consistent data. Airborne acquisition of data guarantees good spatial resolution. Airborne measurements are calculated via special algorithms in absolute units and related to the individual radioactive nuclei on the ground in real time. Full raw and calculated data recording is provided including the position coordinates. More precise results may be achieved via post flight processing. Principles of ground contamination estimates measured from the air and the sensitivities for different radioactive nuclei are also discussed. Results from an Ontario Hydro (Canada) test over a nuclear power plant, an Atom bomb blast measurements in Maralinga (Australia), after 40 years, and a Nuclear power plant in Slovakia and Uranium mining area in Germany are presented and discussed. (author). 6 refs, 1 fig.

Airborne and truck-borne ''radiation footprints'' of areas producing, storing, using or being exposed to nuclear materials

International Nuclear Information System (INIS)

Pavlik, B.; Bottos, F.; Cuneen, P.J.; Jurza, P.; Hoeschl, V.

1997-01-01

The paper discusses the use of advanced Airborne Gamma Ray Spectrometer for environmental assessment of nuclear radiation in areas exposed to radioactive materials. The use of high capacity real time processors operating in parallel mode packaged into one mechanical enclosure together with navigation, allows implementation of highly sophisticated proprietary algorithms to produce results in absolute physical units. Airborne footprinting provides rapid, well defined spatial images of natural and manmade radioactive contamination. Integrated GPS guidance systems provides instant position information related to the internal geographical data base. Short time span of data acquisition provides consistent data. Airborne acquisition of data guarantees good spatial resolution. Airborne measurements are calculated via special algorithms in absolute units and related to the individual radioactive nuclei on the ground in real time. Full raw and calculated data recording is provided including the position coordinates. More precise results may be achieved via post flight processing. Principles of ground contamination estimates measured from the air and the sensitivities for different radioactive nuclei are also discussed. Results from an Ontario Hydro (Canada) test over a nuclear power plant, an Atom bomb blast measurements in Maralinga (Australia), after 40 years, and a Nuclear power plant in Slovakia and Uranium mining area in Germany are presented and discussed. (author)

Dispersion model for airborne radioactive particulates inside a process building

International Nuclear Information System (INIS)

Perkins, W.C.; Stoddard, D.H.

1984-02-01

An empirical model, predicting the spread of airborne radioactive particles after they are released inside a building, has been developed. The basis for this model is a composite of data for dispersion of airborne activity recorded during 12 case incidents. These incidents occurred at the Savannah River Plant (SRP) during approximately 90 plant-years of experience with the chemical and metallurgical processing of purified neptunium and plutonium. The model illustrates that the multiple-air-zone concept, used in the designs of many nuclear facilities, can be an efficient safety feature to limit the spread of airborne activity from a release. This study also provides some insight into an apparently anomalous behavior of airborne particulates, namely, their migration against the prevailing flow of ventilation air. 2 references, 12 figures, 4 tables

Radioactive materials released from nuclear power plants (1976)

International Nuclear Information System (INIS)

Decker, T.R.

1978-11-01

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

41 CFR 50-204.22 - Exposure to airborne radioactive material.

Science.gov (United States)

2010-07-01

... employer shall possess, use or transport radioactive material in such a manner as to cause any employee... excess of the limits specified in Table I of Appendix B to 10 CFR Part 20. The limits given in Table I... table may be increased proportionately. In any such period where the number of hours of exposure is...

New approach to airborne monitoring of radioactive pollution

International Nuclear Information System (INIS)

Hoeschl, V.; Jurza, P.; Pavlik, B.

1997-01-01

The use of remote sensing methods in the monitoring of an environment is increasing. The best results are obtained when various types of exploration methods are available. This paper presents the use of airborne gamma ray methods, which can be included in a wide scope of works related to environmental problems. It may concern uranium mining areas, areas surrounding various nuclear facilities or areas of Chernobyl fallout. Gamma ray spectrometry data can be combined with airborne magnetic, surface gravity and satellite imagery data to obtain maximum information in data output. Airborne geophysics is able to detect and delineate radioactive contamination and to find important geological trends defining the geological structure of the monitored area. Our company PICODAS Prague Ltd. introduces new sophisticated airborne instrumentation as well as up-to-date data processing and data presentation techniques. In the Czech Cretaceous, a long term project, ''The Structurally-tectonic Survey of the South-West Foreland of the Straz Deposit'' has been undertaken, concerning the ecological load on the environment, especially the pollution of the underground water level horizons due to uranium mining in that area. The major interest is the complicated tectonic structure which interferes heavily with the hydrogeological situation of the region. The paper presents the results of airborne surveys and the interpretation of other geophysical data from the surroundings of Straz pod Ralskem and from Karlovy Vary. (author)

Airborne radionuclides in the proglacial environment as indicators of sources and transfers of soil material.

Science.gov (United States)

Łokas, Edyta; Wachniew, Przemysław; Jodłowski, Paweł; Gąsiorek, Michał

2017-11-01

A survey of artificial ( 137 Cs, 238 Pu, 239+240 Pu, 241 Am) and natural ( 226 Ra, 232 Th, 40 K, 210 Pb) radioactive isotopes in proglacial soils of an Arctic glacier have revealed high spatial variability of activity concentrations and inventories of the airborne radionuclides. Soil column 137 Cs inventories range from below the detection limit to nearly 120 kBq m -2 , this value significantly exceeding direct atmospheric deposition. This variability may result from the mixing of materials characterised by different contents of airborne radionuclides. The highest activity concentrations observed in the proglacial soils may result from the deposition of cryoconites, which have been shown to accumulate airborne radionuclides on the surface of glaciers. The role of cryoconites in radionuclide accumulation is supported by the concordant enrichment of the naturally occurring airborne 210 Pb in proglacial soil cores showing elevated levels of artificial radionuclides. The lithogenic radionuclides show less variability than the airborne radionuclides because their activity concentrations are controlled only by the mixing of material derived from the weathering of different parent rocks. Soil properties vary little within and between the profiles and there is no unequivocal relationship between them and the radionuclide contents. The inventories reflect the pathways and time variable inputs of soil material to particular sites of the proglacial zone. Lack of the airborne radionuclides reflects no deposition of material exposed to the atmosphere after the 1950s or its removal by erosion. Inventories above the direct atmospheric deposition indicate secondary deposition of radionuclide-bearing material. Very high inventories indicate sites where transport pathways of cryoconite material terminated. Copyright © 2017 Elsevier Ltd. All rights reserved.

Effluent monitoring Quality Assurance Project Plan for radioactive airborne emissions data. Revision 2

International Nuclear Information System (INIS)

Frazier, T.P.

1995-12-01

This Quality Assurance Project Plan addresses the quality assurance requirements for compiling Hanford Site radioactive airborne emissions data. These data will be reported to the U.S. Environmental Protection Agency, the US Department of Energy, and the Washington State Department of Health. Effluent Monitoring performs compliance assessments on radioactive airborne sampling and monitoring systems. This Quality Assurance Project Plan is prepared in compliance with interim guidelines and specifications. Topics include: project description; project organization and management; quality assurance objectives; sampling procedures; sample custody; calibration procedures; analytical procedures; monitoring and reporting criteria; data reduction, verification, and reporting; internal quality control; performance and system audits; corrective actions; and quality assurance reports

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

Energy Technology Data Exchange (ETDEWEB)

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

1987-08-01

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

Airborne radioactive emission control technology. Volume II

International Nuclear Information System (INIS)

Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

1980-03-01

This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, including uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking, a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

Airborne radioactive emission control technology. Volume III

International Nuclear Information System (INIS)

Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

1980-03-01

This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, including uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking, a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

Airborne radioactive emission control technology. Volume I

International Nuclear Information System (INIS)

Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

1980-03-01

This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, includimg uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases

Energy Technology Data Exchange (ETDEWEB)

Vincent, A.W. III

2001-01-03

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

Radioactive materials released from nuclear power plants. Annual report 1977

International Nuclear Information System (INIS)

Decker, T.R.

1978-11-01

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

Monitoring and evaluation techniques for airborne contamination

Energy Technology Data Exchange (ETDEWEB)

Yihua, Xia [China Inst. of Atomic Energy, Beijing (China)

1997-06-01

Monitoring and evaluation of airborne contamination are of great importance for the purpose of protection of health and safety of workers in nuclear installations. Because airborne contamination is one of the key sources to cause exposure to individuals by inhalation and digestion, and to cause diffusion of contaminants in the environment. The main objectives of monitoring and evaluation of airborne contamination are: to detect promptly a loss of control of airborne material, to help identify those individuals and predict exposure levels, to assess the intake and dose commitment to the individuals, and to provide sufficient documentation of airborne radioactivity. From the viewpoint of radiation protection, the radioactive contaminants in air can be classified into the following types: airborne aerosol, gas and noble gas, and volatile gas. In this paper, the following items are described: sampling methods and techniques, measurement and evaluation, and particle size analysis. (G.K.)

Monitoring and evaluation techniques for airborne contamination

International Nuclear Information System (INIS)

Xia Yihua

1997-01-01

Monitoring and evaluation of airborne contamination are of great importance for the purpose of protection of health and safety of workers in nuclear installations. Because airborne contamination is one of the key sources to cause exposure to individuals by inhalation and digestion, and to cause diffusion of contaminants in the environment. The main objectives of monitoring and evaluation of airborne contamination are: to detect promptly a loss of control of airborne material, to help identify those individuals and predict exposure levels, to assess the intake and dose commitment to the individuals, and to provide sufficient documentation of airborne radioactivity. From the viewpoint of radiation protection, the radioactive contaminants in air can be classified into the following types: airborne aerosol, gas and noble gas, and volatile gas. In this paper, the following items are described: sampling methods and techniques, measurement and evaluation, and particle size analysis. (G.K.)

Studies of environmental radioactivity in Cumbria: Part 3. Measurements of radionuclides in airborne and deposited material

International Nuclear Information System (INIS)

Pattenden, N.J.; Cambray, R.S.; Playford, K.; Eakins, J.D.; Fisher, E.M.R.

1980-09-01

Six stations sampling airborne particulate and deposited material were established in the Cumbrian coastal region. The measurements were undertaken to study current atmospheric levels and to discriminate between material from nuclear weapon tests, routine atmospheric discharges from the nuclear reprocessing works at Windscale and other sources, e.g. the sea. The results show that samples of both airborne and deposited material contain radionuclide concentrations in excess of those expected from nuclear weapon fallout. For Pu and 241 Am isotopes, the excess material comes mainly from a seaward direction. The transfer mechanism is probably resuspension, but the actinide levels are much greater than would be expected from the simple transfer of bulk seawater. For 137 Cs, the material in excess of amounts expected from nuclear weapon fallout can be attributed largely to Windscale discharges to air and seaspray containing the bulk seawater concentration of 137 Cs. Other fission products present in amounts exceeding nuclear weapon fallout were 106 Ru, 125 Sb, 134 Cs and 144 Ce. Tritium was also observed in amounts slightly in excess of nuclear weapon fallout. The highest observed annual average concentration in air for Pu isotopes was 0.2% of the derived air concentration, modified for members of the public, of 2.3 mBq/m 3 . (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-02-15

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

Regulatory review of releases from HIFAR of radioactive airborne effluent

International Nuclear Information System (INIS)

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

1996-01-01

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

A review of methods for sampling large airborne particles and associated radioactivity

International Nuclear Information System (INIS)

Garland, J.A.; Nicholson, K.W.

1990-01-01

Radioactive particles, tens of μm or more in diameter, are unlikely to be emitted directly from nuclear facilities with exhaust gas cleansing systems, but may arise in the case of an accident or where resuspension from contaminated surfaces is significant. Such particles may dominate deposition and, according to some workers, may contribute to inhalation doses. Quantitative sampling of large airborne particles is difficult because of their inertia and large sedimentation velocities. The literature describes conditions for unbiased sampling and the magnitude of sampling errors for idealised sampling inlets in steady winds. However, few air samplers for outdoor use have been assessed for adequacy of sampling. Many size selective sampling methods are found in the literature but few are suitable at the low concentrations that are often encountered in the environment. A number of approaches for unbiased sampling of large particles have been found in the literature. Some are identified as meriting further study, for application in the measurement of airborne radioactivity. (author)

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

International Nuclear Information System (INIS)

Tichler, J.; Norden, K.

1986-02-01

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

Radioactivity survey data in Japan. Pt. 2. Dietary materials

International Nuclear Information System (INIS)

1998-08-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on August, 1998. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water, freshwater, soil, sea water and sea sediments and some dietary materials such as rice, milk, vegetables, tea, fish, shellfish, and seaweeds, which were collected from April to September, 1995. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium 90 and Cesium 137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan, Part 2. Dietary materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on March, 1999. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water, freshwater, soil, sea water and sea sediments and some dietary materials such as rice, milk, vegetables, sea fish, freshwater fish, shellfish, and seaweeds, which were collected from October, 1996 to March, 1997. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan. Pt. 2. Dietary materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on September, 1998. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water, freshwater, soil, sea water and sea sediments and some dietary materials such as rice, milk, vegetables, tea, fish, shellfish, and seaweeds, which were collected from Oct. 1995 to Mar. 1996. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium 90 and Cesium 137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Sampling airborne radioactivity

International Nuclear Information System (INIS)

Cohen, B.S.

1988-01-01

Radioactive contaminants have historically been considered apart from chemical contaminants because it is their radiological properties that determine their biological and environmental impact. Additionally they have been regulated by special government agencies concerned with radiological protection. Radioactive contaminants are also distinguished by the specialized and very sensitive methods available for the detection of radioactivity. Measurements of a few thousand atoms per liter are not uncommon. Radiation detectors in common use are gas filled chambers, scintillation and semiconductor detectors, and the more recently developed thermoluminescent and etched track detectors. Solid-state nuclear track detectors consist of a large group of inorganic and organic dielectrics which register tracks when traversed by heavy charged particles. They do not respond to light, beta particles or gamma ray photons and thus provide a very low background system for the detection of extremely low levels of radioactivity. In addition, no power source or electronic equipment is required. Cellulose nitrate detectors are currently in use for long term integrated sampling of environmental radon. Thermoluminescent dosimeters (TID's) are crystalline materials, in which electrons which have been displaced by an interaction with ionizing radiation become trapped at an elevated energy level and emit visible light when released from that energy level. As which etched-track detectors no power or electronic equipment is needed for the TID's at a measurement site, but they respond to alpha, beta and gamma radiation. Thermoluminescent dosimeters are useful for long term environmental monitoring, and have also been newly incorporated into integrating radon detection systems

Measurements of airborne short-lived radioactivity concentration in a PET facility at a national University hospital

International Nuclear Information System (INIS)

Saito, Tadashi

2006-01-01

National universities in Japan became under regulation of Industrial Safety and Health Law since 2004FY. One of the legal obligations is working environment measurements such as airborne radioactivity concentration in the rooms where employees handle unsealed radiation sources. Both in 2004FY and in 2005FY, measurements of airborne radioactivity concentration were carried out by two different agencies. The most prominent difference among them is the measurement for short-lived PET nuclides. In 2004FY, one agency measured the radioactivity with a Ge spectrometer at its own laboratory, whereas, in 2005FY, the other agency brought a NaI scintillation counter for gross gamma counting to the Hospital. It can be shown that detection limits for short-lived PET nuclides are in principle almost the same in both methods. It is also found that, in the actual case, gamma spectrometry with a Ge spectrometer is superior in judgement of detection of the radioactivity. (author)

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.)

Dispersion model for airborne particulates inside a building

International Nuclear Information System (INIS)

Perkins, W.C.; Stoddard, D.H.

1985-01-01

An empirical model has been developed for the spread of airborne radioactive particles after they are released inside a building. The model has been useful in performing safety analyses of actinide materials facilities at the Savannah River Plant (SRP). These facilities employ the multiple-air-zone concept; that is, ventilation air flows from rooms or areas of least radioactive material hazard, through zones of increasing hazard, to a treatment system. A composite of the data for dispersion of airborne activity during 12 actual case incidents at SRP forms the basis for this model. These incidents occurred during approximately 90 plant-years of experience at SRP with the chemical and metallurgical processing of purified neptunium and plutonium after their recovery from irradiated uranium. The model gives ratios of the airborne activity concentrations in rooms and corridors near the site of the release. The multiple-air-zone concept has been applied to many designs of nuclear facilities as a safety feature to limit the spread of airborne activity from a release. The model illustrates the limitations of this concept: it predicts an apparently anomalous behavior of airborne particulates; namely, a small migration against the flow of the ventilation air

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

Vectorization of nuclear codes for atmospheric transport and exposure calculation of radioactive materials

International Nuclear Information System (INIS)

Asai, Kiyoshi; Shinozawa, Naohisa; Ishikawa, Hirohiko; Chino, Masamichi; Hayashi, Takashi

1983-02-01

Three computer codes MATHEW, ADPIC of LLNL and GAMPUL of JAERI for prediction of wind field, concentration and external exposure rate of airborne radioactive materials are vectorized and the results are presented. Using the continuous equation of incompressible flow as a constraint, the MATHEW calculates the three dimensional wind field by a variational method. Using the particle-in -cell method, the ADPIC calculates the advection and diffusion of radioactive materials in three dimensional wind field and terrain, and gives the concentration of the materials in each cell of the domain. The GAMPUL calculates the external exposure rate assuming Gaussian plume type distribution of concentration. The vectorized code MATHEW attained 7.8 times speedup by a vector processor FACOM230-75 APU. The ADPIC and GAMPUL are estimated to attain 1.5 and 4 times speedup respectively on CRAY-1 type vector processor. (author)

Fixed-wing gamma measurement for the detection of radioactive materials

International Nuclear Information System (INIS)

Kettunen, M.J.; Nikkinen, M.T.

2005-01-01

Finland has the operational capability to take airborne gamma-ray measurements in emergency situations. The original purpose of airborne radiation mapping in Finland was to identify hazardous areas containing radioactive fall-out after a nuclear accident or use of nuclear weapons. Regular exercises are held annually to keep the operational functionality at a high level. The achieved capability has been well demonstrated in international INEX-2-FIN 1997 and Barents Rescue 2001 exercises. The knowledge and competence achieved can easily be applied in international radiation monitoring campaigns designed to expose undeclared nuclear materials or other clandestine nuclear activities. The essential improvements in the detection system are linked to the ability to locate point-like radiation sources rather than large areas of fall-out. Aerial gamma-ray measurement method and its usability for the detection of nuclear material production chains and trails of fission or activation products is described. The ability of airborne detection systems in revealing the use of undeclared nuclear materials has been tested. Various scenarios for exposing clandestine nuclear material production, enrichment and nuclear waste trails have been considered. Based on detection capability calculations and testing in practice, it was found that the detection of one un-shielded significant quantity of natural uranium (10 tons of yellow cake in storage barrels) is possible through the daughter products, using one single 6' x 4' NaI detector on the airplane. The developed fixed wing gamma measurement technique is now able to detect significant amounts of nuclear material conveniently and cost-effectively. Large areas can be screened to identify suspicious sub-areas for more detailed ground-based inspection. (author)

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

International Nuclear Information System (INIS)

Geryes, Tony

2009-01-01

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

Airborne anthropogenic radioactivity measurements from an international radionuclide monitoring system

International Nuclear Information System (INIS)

Mason, L.R.; Bohner, J.D.; Williams, D.L.

1998-01-01

Anthropogenic radioactivity is being measured in near-real time by an international monitoring system designed to verify the Comprehensive Nuclear Test Ban Treaty. Airborne radioactivity measurements are conducted in-situ by stations that are linked to a central data processing and analysis facility. Aerosols are separated by high-volume air sampling with high-efficiency particulate filters. Radio-xenon is separated from other gases through cryogenic methods. Gamma-spectrometry is performed by high purity germanium detectors and the raw spectral data is immediately transmitted to the central facility via Internet, satellite, or modem. These highly sensitive sensors, combined with the automated data processing at the central facility, result in a system capable of measuring environmental radioactivity on the microbecquerel scale where the data is available to scientists within minutes of the field measurement. During the past year, anthropogenic radioactivity has been measured at approximately half of the stations in the current network. Sources of these measured radionuclides include nuclear power plant emissions, Chernobyl resuspension, and isotope production facilities. The ability to thoroughly characterize site-specific radionuclides, which contribute to the radioactivity of the ambient environment, will be necessary to reduce the number of false positive events. This is especially true of anthropogenic radionuclides that could lead to ambiguous analysis. (author)

Radioactivity survey data in Japan, Part 2. Dietary materials

International Nuclear Information System (INIS)

1999-09-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on September, 1999. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water and freshwater, soil, sea water sea sediments, total diet, rice, milk, vegetables, tea, fish, shellfish and seaweeds, which were collected from October, 1997 to March, 1998. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan, Part 2. Dietary materials

International Nuclear Information System (INIS)

2002-02-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on September, 2001. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water and freshwater, soil, sea water sea sediments, total diet, rice, milk, vegetables, tea, fish, shellfish and seaweeds, which were collected from October, 1999 to March, 2000. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan, Part 2. Dietary materials

International Nuclear Information System (INIS)

2000-08-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on August, 2000. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water and freshwater, soil, sea water sea sediments, total diet, rice, milk, vegetables, tea, fish, shellfish and seaweeds, which were collected from April to September, 1998. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan, Part 2. Dietary materials

International Nuclear Information System (INIS)

2000-09-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on September, 2000. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water and freshwater, soil, sea water sea sediments, total diet, rice, milk, vegetables, tea, fish, shellfish and seaweeds, which were collected from October, 1998 to March, 1999. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan, Part 2. Dietary materials

International Nuclear Information System (INIS)

2002-01-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on August, 2001. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water and freshwater, soil, sea water sea sediments, total diet, rice, milk, vegetables, tea, fish, shellfish and seaweeds, which were collected from April to September, 1999. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

Radioactivity survey data in Japan, Part 2. Dietary materials

International Nuclear Information System (INIS)

1999-08-01

This is a report on radioactivity in Japan issued by National Institute of Radiological Sciences, Chiba on August, 1999. This data relates to some environmental materials such as rain and dry fallout, airborne dust, service water and freshwater, soil, sea water sea sediments, total diet, rice, milk, vegetables, tea, fish, shellfish and seaweeds, which were collected from April to September, 1997. In the survey data, followings are contained: 1) Collection and pretreatment of samples, 2) Preparation of samples for analysis, 3) Separation of Strontium-90 and Cesium-137, 4) Determination of stable Strontium, Calcium, and Potassium, 5) Counting, 6) Results, and 7) Contents of Figure. (J.P.N.)

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.)

Spotting Radioactive Sources Buried Underground Using an Airborne Radiation Monitoring System

International Nuclear Information System (INIS)

Sheinfeld, M.; Wengrowicz, U.; Beck, A.; Marcus, E.; Tirosh, D.

2002-01-01

This article provides theoretical background concerning the capability of the Airborne Radiation Monitoring System [1]to detect fission products buried at 1-meter depth under the ground surface,at a flight altitude of 100 meters above ground.The 137 Cs source was used as a typical fission product. The System monitors radioactive contamination in the air or on the ground using two 2 inch NaI(Tl) scintillation detectors and computerized accessories for analysis purposes

A study of production of radioactive environmental reference materials used for proficiency testing program in Taiwan

International Nuclear Information System (INIS)

Peng, En-Chi; Wang, Jeng-Jong

2013-01-01

To realise radioactive environmental reference materials in Taiwan, seven environmental materials of soil, water, vegetation, meat, airborne particles (filter paper), milk and mushroom samples that are frequently encountered were used to establish the preparation of the reference materials. These seven environmental materials were collected, checked for freedom from radioactivity and prepared according to their properties. The preparation was carried out by using activity about 10–100 times that of the minimum detectable activity (MDA) in routine measurements in the radioactive standard used to spike the inactive material and this standard is traceable to national ionising radioactivity standards (TAF, 2004). To demonstrate sample traceability to the added standard, each sample was carefully measured and its uncertainty evaluated. Based on the recommendations of ISO Guide 35 for evaluation of reference materials and with the above assessment and verification procedures, the uncertainties (k=1) of the spike activity used in making reference materials were: 60 Co≤4.6%, 134 Cs≤4.7%, 137 Cs≤5.0%, total β≤0.6% and 3 H≤1.3%. - Highlights: • Seven kinds environmental materials were used to establish the production of the RMs. • Spiking the traceable standard radioactive source to the blank substance. • Each sample was carefully evaluated for its uncertainty. • The performance of the RMs was estimated with the Proficiency Testing program report. • The ability of the environment RMs in the configuration is quite good

Hydrological dispersion of radioactive material in relation to nuclear power plant siting

International Nuclear Information System (INIS)

1985-01-01

This Guide discusses the dispersion of normal and accidental releases of radioactive materials from nuclear power plants into surface water, including the washout of airborne radionuclides, and gives recommendations on information to be collected during the various stages of the siting procedure, a minimum measurement programme and the selection and validation of appropriate mathematical models for predicting dispersion. Guidelines are also provided for the optimal use of models for a specific site situation and for defining the necessary input parameters. Results of existing validation studies are given

Radioactive airborne effluent discharged from Tokai reprocessing plant. 1998-2007

International Nuclear Information System (INIS)

Nakada, Akira; Miyauchi, Toru; Akiyama, Kiyomitsu; Momose, Takumaro; Kozawa, Tomoyasu; Yokota, Tomokazu; Ohtomo, Hiroyuki

2008-10-01

This report provides the data set of atmospheric discharges from Tokai reprocessing plant in Tokai-mura, Japan over the period from 1998 to 2007. Daily and weekly data are shown for 85 Kr that is continuously monitored and for the other nuclides (alpha emitters, beta emitters, 3 H, 14 C, 129 I and 131 I) whose activities are evaluated based on weekly samplings (Weekly sampling is continuous for 1 week). The data contained in this report are expected to apply for studying the behavior of the radioactive airborne effluent in the environment. (author)

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

RESRAD-BUILD: A computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material

International Nuclear Information System (INIS)

Yu, C.; LePoire, D.J.; Jones, L.G.

1994-11-01

The RESRAD-BUILD computer code 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 transport of radioactive material inside the building from one compartment to another is calculated with an indoor air quality model. The air quality model considers the transport of radioactive dust particulates and radon progeny due to air exchange, deposition and resuspension, and radioactive decay and ingrowth. A single run of the RESRAD-BUILD code can model a building with up to: three compartments, 10 distinct source geometries, and 10 receptor locations. A shielding material can be specified between each source-receptor pair for external gamma dose calculations. Six exposure pathways are considered in the RESRAD-BUILD code: (1) external exposure directly from the source; (2) external exposure to materials deposited on the floor; (3) external exposure due to air submersion; (4) inhalation of airborne radioactive particulates; (5) inhalation of aerosol indoor radon progeny; and (6) inadvertent ingestion of radioactive material, either directly from the sources or from materials deposited on the surfaces of the building compartments

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

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

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.)

Novel method for estimation of the indoor-to-outdoor airborne radioactivity ratio following the Fukushima Daiichi Nuclear Power Plant accident

Energy Technology Data Exchange (ETDEWEB)

Tan, Yanliang, E-mail: hytyl@163.com [College of Physics and Electronic Engineering, Hengyang Normal University, Hengyang, Hunan Province (China); Ishikawa, Tetsuo [Fukushima Medical University, 1 Hikariga-oka, Fukushima (Japan); Janik, Miroslaw [Regulatory Science Research Program, National Institute of Radiological Sciences, Chiba (Japan); Tokonami, Shinji [Department of Radiation Physics, Institute of Radiation Emergency Medicine, Hirosaki University, Hirosaki, Aomori (Japan); Hosoda, Masahiro [Hirosaki University Graduate School of Health Science, Hirosaki, Aomori (Japan); Sorimachi, Atsuyuki [Fukushima Medical University, 1 Hikariga-oka, Fukushima (Japan); Kearfott, Kimberlee [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI (United States)

2015-12-01

The accident at the Fukushima Daiichi Nuclear Power Plant (FDNPP) in Japan resulted in significant releases of fission products. While substantial data exist concerning outdoor air radioactivity following the accident, the resulting indoor radioactivity remains pure speculation without a proper method for estimating the ratio of the indoor to outdoor airborne radioactivity, termed the airborne sheltering factor (ASF). Lacking a meaningful value of the ASF, it is difficult to assess the inhalation doses to residents and evacuees even when outdoor radionuclide concentrations are available. A simple model was developed and the key parameters needed to estimate the ASF were obtained through data fitting of selected indoor and outdoor airborne radioactivity measurement data obtained following the accident at a single location. Using the new model with values of the air exchange rate, interior air volume, and the inner surface area of the dwellings, the ASF can be estimated for a variety of dwelling types. Assessment of the inhalation dose to individuals readily follows from the value of the ASF, the person's indoor occupancy factor, and the measured outdoor radioactivity concentration. - Highlights: • Actual ASF of the dwells is very important to estimate the inhalation dose. • A simple model is developed to describe ASF. • The key parameter of ASF is obtained from the measurement of NIRS. • The ASF of any dwellings can be obtained by our model and relatively parameters.

Radioactive Contamination Estimation from micro-copters or helicopter Airborne survey: Simulation and real measurements

International Nuclear Information System (INIS)

Halevy, I.; Ghelman, M.; Yehuda-Zada, Y.; Manor, A.; Dadon, S.; Sharon, A.; Yaar, I.

2014-01-01

One of the main advantages of acquiring aero-radiometric measurements lies in the high collection rate of data over large areas and rough terrain. Typical aero-radiometric system records and saves gamma ray spectrum, correlated with the GPS derived location information in regular time intervals of one to two seconds. Such data can be used to locate radiation anomalies on the ground, map ground contamination or track a radioactive airborne plume. Acquiring spectral data of this type allows separation of natural radioactivity from that of man-made sources and identification of specific isotopes, natural or man-made

Radioactive Contamination Estimation from Micro-Copters or Helicopter Airborne Survey: Simulation and Real Measurements

International Nuclear Information System (INIS)

Halevy, I.; Ghelman, M.; Yehuda-Zada, Y.; Manor, A.; Sharon, A.; Yaar, I.

2014-01-01

One of the main advantages of acquiring aero-radiometric measurements lies in the high collection rate of data over large areas and rough terrain. Typical aero-radiometric system records and saves gamma ray spectrum, correlated with the GPS derived location information in regular time intervals of one to two seconds. Such data can be used to locate radiation anomalies on the ground, map ground contamination or track a radioactive airborne plume. Acquiring spectral data of this type allows separation of natural radioactivity from that of man-made sources and identification of specific isotopes, natural or man-made

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-12-15

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

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, ...

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

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

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

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

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.

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

Estimation of Airborne Radioactivity Induced by 8-GeV-Class Electron LINAC Accelerator.

Science.gov (United States)

Asano, Yoshihiro

2017-10-01

Airborne radioactivity induced by high-energy electrons from 6 to 10 GeV is estimated by using analytical methods and the Monte Carlo codes PHITS and FLUKA. Measurements using a gas monitor with a NaI(Tl) scintillator are carried out in air from a dump room at SACLA, an x-ray free-electron laser facility with 7.8-GeV electrons and are compared to the simulations.

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

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

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

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)

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).

Recommended parameters for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities

International Nuclear Information System (INIS)

Li Hong; Fang Dong; Sun Chengzhi; Xiao Naihong

2003-01-01

A set of models and default parameters are recommended for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities in order to standardize the environmental effect assessment of nuclear facilities, and to simplify the observation and investigation in early phase. The paper introduces the input data and default parameters used in the model

Potential airborne release from soil-working operations in a contaminated area

International Nuclear Information System (INIS)

Sutter, S.L.

1980-08-01

Experiments were performed to provide an indication of how much material could be made airborne during soil-working operations in a contaminated area. Approximately 50 kg of contaminated soil were collected, dried, and mixed, and particle size distribution and 137 Cs content were characterized. In four experiments performed in a 2 ft x 2 ft wind tunnel at the Radioactive Aerosol Release Test Facility, soil was pumped into an airstream moving at 3.2, 10.4, 15.2, and 20 mph. These experiments were designed to maximize airborne releases by fluidizing the soil as it was pumped into the wind tunnel. Thus the airborne releases should represent upper limit values for soil-working operations. Airborne concentration and particle size samples were collected and all of the material deposited downstream was collected to calculate a mass balance. The fraction airborne was calculated using these measurements

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)

Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

International Nuclear Information System (INIS)

Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo; Koo, Bon Cheol; Chang, Byung Uck

2016-01-01

It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries

Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo [College of Engineering, Kyung Hee University, Yongin (Korea, Republic of); Koo, Bon Cheol; Chang, Byung Uck [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2016-09-15

It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

Environmental assessments for the existing radioactive materials in the Weldon Spring raffinate pits

International Nuclear Information System (INIS)

Yang, J.Y.; Wang, J.

1985-01-01

Various radioactive residues (raffinates) and wastes from the processing of uranium and thorium between 1957 and 1966 are stored in four pits at Weldon Spring, Missouri. The US Department of Energy (DOE) plans to stabilize all the contaminated materials on a long-term (more than 1000-year) basis. The effectiveness of stabilization measures are evaluated by estimating radioactive releases under two options: (1) no action, and (2) improved containment using the existing raffinate pits. Two major pathways of radiation exposure are examined: (1) airborne radioactive gases and particulates, and (2) seepage into near-surface groundwater. The relative reductions of releases into the air and groundwater for a reference stabilization option (improved containment) are analyzed using mathematical models for radioactive and particulate gas fluxes and atmospheric dispersion, as well as groundwaterr transport and dispersion. The consequent health risks for nearby individuals and the general public are also evaluated. This study focuses on the migration of radionuclides under existing conditions and evaluates the effectiveness of proposed stabilization measures at the pits. Results indicate that the potential effects to the general public would be insignificant. 22 refs., 2 figs., 6 tabs

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)

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)

Experimental study of radioactive aerosols emission during the thermal degradation of organic materials in nuclear facilities

International Nuclear Information System (INIS)

Fernandez, Yvette

1993-01-01

Radioactive products may be released during a fire in nuclear fuel cycles facilities. These products must be confined to avoid a contamination spread in the environment. It is therefore necessary to be able to predict the amount and the physico-chemical forms of radioactive material that may be airborne. The aim of this study is to determine experimentally the release of contamination aerosols in a typical fire scenario involving plutonium oxide in a glove box. Firstly, this phenomenon has been studied in a small scale test chamber where samples of polymethylmethacrylate (Plexiglas) contaminated by cerium oxide (used as a substitute for plutonium oxide) were submitted to thermal degradation (pyrolysis and combustion). The release of radioactive material is determined by the quantity of contaminant emitted, the kinetics of the release and the particle size distribution of aerosols. Secondly, the development of an experimental procedure allowed to realize large scale fires in more realistic conditions. The experimental tools developed in the course of this study allow to consider application to other scenarios. (author) [fr

Radiological surveillance of airborne contaminants in the working environment

International Nuclear Information System (INIS)

1979-01-01

Contamination of the air of the working environment may result from incidental or accidental releases during the handling of radioactive materials. Representative sampling and measurement are complicated by a variety of factors, arising mainly from the physical and chemical properties of radioactive aerosols. The following topics are presented in detail: sources and types of airborne contaminants, sampling techniques and instruments, measurement techniques and instruments, interpretation of measurements, examples of air monitoring programmes

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.)

Derivation of guidelines for uranium residual radioactive material in soil at the Colonie Site, Colonie, New York

International Nuclear Information System (INIS)

Dunning, D.

1996-05-01

Residual radioactive material guidelines for uranium in soil were derived for the Colonie site located in Colonie, New York. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the U.S. Department of Energy (DOE). The site became contaminated with radioactive material as a result of operations conducted by National Lead (NL) Industries from 1958 to 1984; these activities included brass foundry operations, electroplating of metal products, machining of various components using depleted uranium, and limited work with small amounts of enriched uranium and thorium. The Colonie site comprises the former NL Industries property, now designated the Colonie Interim Storage Site (CISS), and 56 vicinity properties contaminated by fallout from airborne emissions; 53 of the vicinity properties were previously remediated between 1984 and 1988. In 1984, DOE accepted ownership of the CISS property from NL Industries. Residual radioactive material guidelines for individual radionuclides and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the site should not exceed a dose of 30 mrem/yr following remedial action for the current use and likely future use scenarios or a dose of 100 mrem/yr for less likely future use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines

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)

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.

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

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

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

The role of the health physicist in the control of airborne radioactive hazards

International Nuclear Information System (INIS)

Basson, J.K.

1978-01-01

Health physics is based on the ease and sensitivity with which ionising radiations can be measured, as well as on the extensive medical knowledge of its long-term effects. Such studies have led to fundamental contributions to scientific health protection as well as practical occupational hygiene. The first aspect is illustrated with aerosol biophysics as example, while the practical control of airborne radioactive hazards in South Africa is described inside uranium plants as well as in the environment of nuclear installations [af

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)

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

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)

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)

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

International Nuclear Information System (INIS)

Morgenstern, M.Y.; Hueske, K.

1995-01-01

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

Software for airborne radiation monitoring system

International Nuclear Information System (INIS)

Sheinfeld, M.; Kadmon, Y.; Tirosh, D.; Elhanany, I.; Gabovitch, A.; Barak, D.

1997-01-01

The Airborne Radiation Monitoring System monitors radioactive contamination in the air or on the ground. The contamination source can be a radioactive plume or an area contaminated with radionuclides. This system is composed of two major parts: Airborne Unit carried by a helicopter, and Ground Station carried by a truck. The Airborne software is intended to be the core of a computerized airborne station. The software is written in C++ under MS-Windows with object-oriented methodology. It has been designed to be user-friendly: function keys and other accelerators are used for vital operations, a help file and help subjects are available, the Human-Machine-Interface is plain and obvious. (authors)

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

Airborne radioactive contamination following aerosol ventilation studies

International Nuclear Information System (INIS)

Mackie, A.; Hart, G.C.; Ibbett, D.A.; Whitehead, R.J.S.

1994-01-01

Lung aerosol ventilation studies may be accompanied by airborne contamination, with subsequent surface contamination. Airborne contamination has been measured prior to, during and following 59 consecutive 99 Tc m -diethylenetriamine pentaacetate (DTPA) aerosol studies using a personal air sampler. Airborne contamination ranging between 0 and 20 330 kBq m -3 has been measured. Airborne contamination increases with degree of patient breathing difficulty. The effective dose equivalent (EDE) to staff from ingested activity has been calculated to be 0.3 μSv per study. This figure is supported by data from gamma camera images of a contaminated staff member. However, surface contamination measurements reveal that 60% of studies exceed maximum permissible contamination limits for the hands; 16% of studies exceed limits for controlled area surfaces. (author)

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

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)

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

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

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)

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)

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.)

Air concentration and ground deposition following radioactive airborne releases

International Nuclear Information System (INIS)

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

1985-01-01

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

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)

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

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)

Various consequences regarding hypothetical dispersion of airborne radioactivity in a city center

International Nuclear Information System (INIS)

Jonsson, Lage; Plamboeck, Agneta H.; Johansson, Erik; Waldenvik, Mattias

2013-01-01

In case of dispersion of airborne radioactive material in a city center a number of questions will prompt for an answer. While many questions can get their answers in due course of time based on results of tests and sampling, a good understanding of the quantitative effect of dispersion will be very helpful to rescue staff, in particular in the early stage. In the following dose and dose rate estimates are presented for three scenarios including dispersion of radioactivity in a city center. In one case the activity is released in an open place, in another from a roof and in the third case from a source on a street where the wind is blowing along the street. In each case, at specific positions, estimates are made of dose from inhalation, and dose rates for contamination on skin as well as from radioactive particles deposited onto ground, walls and roofs (external exposure) in the city center. It should be noted that the deposition pattern in urban areas varies greatly which means that the consequences are difficult to predict. The dispersion is influenced by recirculation behind tall buildings and diverted flow close to street-ends, which have significant effects on the deposit pattern. Regarding the relative importance of contributions to total dose it is found that inhalation could play a major role for long term effects while dose to skin might dominate acute effects. - Highlights: ► Consequences of dispersion and deposition of 137 Cs in a city center are modeled. ► External exposure from local deposition patterns on walls, roofs and ground is estimated. ► Estimates are made of dose from inhalation, skin dos rates and external dose rates. ► Skin dose was the most serious acute dose while inhalation dominates long term effects. ► Among the investigated scenarios a release near a street end is most serious.

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)

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

International Nuclear Information System (INIS)

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

2015-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-11

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

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)

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.)

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

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

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

Differences in in vitro dissolution properties of settled and airborne uranium material

International Nuclear Information System (INIS)

Scripsick, R.C.; Crist, K.C.; Tillery, M.I.; Soderholm, S.C.

1984-01-01

The dissolution behavior of settled and airborne uranium material produced by firing of depleted uranium munitions was studied using an in vitro dissolution technique. Differences in the composition of bulk and respirable fraction samples of these materials were observed. Dissolution analysis results suggest that under some conditions a rapidly dissolving uranium fraction may be formed. This fraction may play an important role in determining hazard potential associated with inhalation exposure to uranium materials. The fact that a larger rapidly dissolving fraction was observed in the airborne material than in the settled material indicates that dissolution analysis should be performed on appropriate size fraction samples. 20 references, 3 figures, 4 tables

Active airborne contamination control using electrophoresis

International Nuclear Information System (INIS)

Veatch, B.D.

1994-01-01

In spite of our best efforts, radioactive airborne contamination continues to be a formidable problem at many of the Department of Energy (DOE) weapons complex sites. For workers that must enter areas with high levels of airborne contamination, personnel protective equipment (PPE) can become highly restrictive, greatly diminishing productivity. Rather than require even more restrictive PPE for personnel in some situations, the Rocky Flats Plant (RFP) is actively researching and developing methods to aggressively combat airborne contamination hazards using electrophoretic technology. With appropriate equipment, airborne particulates can be effectively removed and collected for disposal in one simple process. The equipment needed to implement electrophoresis is relatively inexpensive, highly reliable, and very compact. Once airborne contamination levels are reduced, less PPE is required and a significant cost savings may be realized through decreased waste and maximized productivity. Preliminary ''cold,'' or non-radioactive, testing results at the RFP have shown the technology to be effective on a reasonable scale, with several potential benefits and an abundance of applications

Atmospheric dispersion of radioactive releases: Computer code DIASPORA

International Nuclear Information System (INIS)

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

1982-05-01

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

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

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

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

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

Evaluation of radioactive environmental hazards in Area-3, Northern Palmyrides, Central Syria using airborne spectrometric gamma technique

International Nuclear Information System (INIS)

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

2016-01-01

Airborne spectrometric gamma data are used in this paper to estimate the degree of radioactive hazard on humanity in Area-3, Northern Palmyrides, Central Syria. Exposure Rate (ER), Absorbed Dose Rate (ADR), Annual Effective Dose Rate (AEDR), and Heat Production (HP) of the eleven radiometric units included in the established lithological scored map in the study area have been computed to evaluate the radiation background influence in humans. The results obtained indicate that a human body in Area-3 is subjected to radiation hazards in the acceptable limits for long duration exposure. The highest radiogenetic heat production values in Area-3 correspond to the phosphatic locations characterized by relatively high values of uranium and thorium. - Highlights: • Degree of radioactive hazard has been estimated by using airborne spectrometric gamma data. • ER, ADR, AEDR, and HP of the eleven radiometric units have been computed. • Comparison of AEDR of Area-3 with the AEDR of Area-1. • Human body in Area-3 is subjected to radiation hazards in the acceptable limits for long duration exposure. • The highest heat production in Area-3 correspond to the phosphatic locations.

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

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

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.

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

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.)

Airborne effluent control at uranium mills

International Nuclear Information System (INIS)

Sears, M.B.

1976-01-01

The Oak Ridge National Laboratory has made an engineering cost--environmental benefit study of radioactive waste treatment systems for decreasing the amount of radioactive materials released from uranium ore processing mills. This paper summarizes the results of the study which pertain to the control and/or abatement of airborne radioactive materials from the mill processes. The tailings area is not included. Present practices in the uranium milling industry, with particular emphasis on effluent control and waste management, have been surveyed. A questionnaire was distributed to each active mill in the United States. Replies were received from about 75 percent of the mill operators. Visits were made to six operating uranium mills that were selected because they represented the different processes in use today and the newest, most modern in mill designs. Discussions were held with members of the Region IV Office of NRC and the Grand Junction Office of ERDA. Nuclear Science Abstracts, as well as other sources, were searched for literature pertinent to uranium mill processes, effluent control, and waste management

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)

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

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

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)

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)

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)

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

Source terms for airborne radioactivity arising from uranium mill wastes

International Nuclear Information System (INIS)

O'Riordan, M.C.; Downing, A.L.

1978-01-01

One of the problems in assessing the radiological impact of uranium milling is to determine the rates of release to the air of material from the various sources of radioactivity. Such source terms are required for modelling the transport of radioactive material in the atmosphere. Activity arises from various point and area sources in the mill itself and from the mill tailings. The state of the tailings changes in time from slurry to solid. A layer of water may be maintained over the solids during the life of the mine, and the tailings may be covered with inert material on abandonment. Releases may be both gaseous and particulate. This paper indicates ways in which radon emanation and the suspension of long-lived particulate activity might be quantified, and areas requiring further exploration are identified

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)

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)

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)

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)

Radiological impact of airborne effluents of coal-fired and nuclear power plants

International Nuclear Information System (INIS)

McBride, J.P.; Moore, R.E.; Witherspoon, J.P.; Blanco, R.E.

1977-06-01

Radiological impact of naturally occurring radionuclides in airborne effluents of a model coal-fired steam plant is evaluated assuming a release to the atmosphere of 1 percent of the ash in the coal burned and compared with the impact of radioactive materials in the airborne effluents of model light-water reactors. The principal exposure pathway for radioactive materials released from both types of plants is ingestion of contaminated foodstuffs. For nuclear plants immersion in the airborne effluents is also a significant factor in the dose commitment. Assuming that the coal burned contains 1 ppM uranium and 2 ppM thorium together with their decay products and using the same impact analysis methods used in evaluating nuclear facilities, the maximum individual dose commitments from the coal plant for the whole body and most organs (except the thyroid) are shown to be greater than those from a pressurized-water reactor (PWR) and, with the exception of the bone and kidney doses, less than those from a boiling-water reactor (BWR). With the exception of the bone dose, the maximum individual dose commitments from the coal plant are less than the numerical design guideline limits listed for light-water reactors (LWRs). Population dose commitments from the coal plant are higher than those from either nuclear plant

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...

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

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)

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.

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)

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

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

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...

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)

Correlation between Asian Dust and Specific Radioactivities of Fission Products Included in Airborne Samples in Tokushima, Shikoku Island, Japan, Due to the Fukushima Nuclear Accident

International Nuclear Information System (INIS)

Sakama, M.; Nagano, Y.; Kitade, T.; Shikino, O.; Nakayama, S.

2014-01-01

Radioactive fission product 131 I released from the Fukushima Daiichi Nuclear Power Plants (FD-NPP) was first detected on March 23, 2011 in an airborne aerosol sample collected at Tokushima, Shikoku Island, located in western Japan. Two other radioactive fission products, 134 Cs and 137 Cs were also observed in a sample collected from April 2 to 4, 2011. The maximum specific radioactivities observed in this work were about 2.5 to 3.5 mBq×m -3 in a airborne aerosol sample collected on April 6. During the course of the continuous monitoring, we also made our first observation of seasonal Asian Dust and those fission products associated with the FDNPP accident concurrently from May 2 to 5, 2011. We found that the specific radioactivities of 134 Cs and 137 Cs decreased drastically only during the period of Asian Dust. And also, it was found that this trend was very similar to the atmospheric elemental concentration (ng×m -3 ) variation of stable cesium ( 133 Cs) quantified by elemental analyses using our developed ICP-DRC-MS instrument

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

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.

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.)

A review of airborne particle sampling with special reference to long-lived radioactive dust

International Nuclear Information System (INIS)

Bigu, J.

1990-03-01

This report reviews some basic aspects related to the sampling of airborne particles with special reference to Long-Lived Radioactive Dust (LLRD). The report covers a number of areas of practical interest such as the production of aerosols, the dynamics of suspended particles, the physical and chemical characteristics and properties of dust clouds, and the inhalation and measurement of dust. It is followed with a brief review of dust sampling instrumentation, and with a short account of the work done on LLRD in Canada with a few references to work done outside this country. (34 figs., 7 tabs., 117 refs.)

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

A review of the disposal of miscellaneous radioactive wastes in the United Kingdom

International Nuclear Information System (INIS)

Hookway, B.

1980-01-01

Current practices in the United Kingdom for waste disposal from ''minor users'' of radioactive materials are reviewed. The regulation of the disposal of solid, liquid and airborne wastes is discussed. (H.K.)

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.

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)

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)

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)

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)

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

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...

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

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

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.

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

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.)

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

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

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

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.

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

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

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

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

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

Correlation between Asian Dust and Specific Radioactivities of Fission Products Included in Airborne Samples in Tokushima, Shikoku Island, Japan, Due to the Fukushima Nuclear Accident

Energy Technology Data Exchange (ETDEWEB)

Sakama, M., E-mail: minorusakama@tokushima-u.ac.jp [Department of Radiological Science, Division of Biomedical Information Sciences, Institute of Health Biosciences, The University of Tokushima, Tokushima 770-8509 (Japan); Nagano, Y. [Department of Radiological Science, Division of Biomedical Information Sciences, Institute of Health Biosciences, The University of Tokushima, Tokushima 770-8509 (Japan); Kitade, T. [Department of Laboratory, M and S Instruments Inc., Osaka 532-0005 (Japan); Shikino, O. [Department of Inorganic Analysis, PerkinElmer Japan Co. Ltd., Yokohama 240-0005 (Japan); Nakayama, S. [Department of Nuclear Science, Institute of Socio-Arts and Sciences, The University of Tokushima, Tokushima 770-8502 (Japan)

2014-06-15

Radioactive fission product {sup 131}I released from the Fukushima Daiichi Nuclear Power Plants (FD-NPP) was first detected on March 23, 2011 in an airborne aerosol sample collected at Tokushima, Shikoku Island, located in western Japan. Two other radioactive fission products, {sup 134}Cs and {sup 137}Cs were also observed in a sample collected from April 2 to 4, 2011. The maximum specific radioactivities observed in this work were about 2.5 to 3.5 mBq×m{sup -3} in a airborne aerosol sample collected on April 6. During the course of the continuous monitoring, we also made our first observation of seasonal Asian Dust and those fission products associated with the FDNPP accident concurrently from May 2 to 5, 2011. We found that the specific radioactivities of {sup 134}Cs and {sup 137}Cs decreased drastically only during the period of Asian Dust. And also, it was found that this trend was very similar to the atmospheric elemental concentration (ng×m{sup -3}) variation of stable cesium ({sup 133}Cs) quantified by elemental analyses using our developed ICP-DRC-MS instrument.

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

Report on airborne radioactivity surveys and the uranium deposits in the Red River region of Texas and Oklahoma

International Nuclear Information System (INIS)

Blair, R.G.; Stehle, F.T.; Levich, R.A.

1973-11-01

The U. S. Atomic Energy Commission conducted an airborne radioactivity survey of the Red River region of Texas and Oklahoma beginning in December 1955 and ending in May 1956. All or parts of Archer, Clay, and Montague Counties in northern Texas and Carter, Cotton, Jefferson, and Stephens Counties in southern Oklahoma were surveyed. Particular attention was paid to those areas where exposures are found of red beds of the Permian Wichita Group. Field examinations were conducted of anomalies discovered by airborne reconnaissance as well as those reported by private individuals. Forty localities were examined, the majority in sandstones, siltstones, or conglomerates. Uranium and copper minerals were identified at several localities. Ferruginous staining, bleaching of the sandstone color, calcium carbonate cement, and carbonized plant remains are common to the deposits

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)

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)

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

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)

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

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

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.

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)

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)

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

International Nuclear Information System (INIS)

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

1998-02-01

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

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)

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.)

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)

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.)

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

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)

Simulated minimum detectable activity concentration (MDAC) for a real-time UAV airborne radioactivity monitoring system with HPGe and LaBr_3 detectors

International Nuclear Information System (INIS)

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

2016-01-01

An automatic real-time UAV airborne radioactivity monitoring system with high-purity germanium (HPGe) and lanthanum bromide (LaBr_3) detectors (NH-UAV) was developed to precisely obtain small-scope nuclide information in major nuclear accidents. The specific minimum detectable activity concentration (MDAC) calculation method for NH-UAV in the atmospheric environment was deduced in this study for a priori evaluation and quantification of the suitability of NH-UAV in the Fukushima nuclear accident, where the MDAC values of this new equipment were calculated based on Monte Carlo simulation. The effects of radioactive source term size and activity concentration on the MDAC values were analyzed to assess the detection performance of NH-UAV in more realistic environments. Finally, the MDAC values were calculated at different shielding thicknesses of the HPGe detector to improve the detection capabilities of the HPGe detector, and the relationship between the MDAC and the acquisition time of the system was deduced. The MDAC calculation method and data results in this study may be used as a reference for in-situ radioactivity measurement of NH-UAV. - Highlights: • A real-time UAV airborne radioactivity monitoring system (NH-UAV) was developed. • The efficiency calculations and MDAC values are given. • NH-UAV is able to monitor major nuclear accidents, such as the Fukushima accident. • The source term size can influence the detection sensitivity of the system. • The HPGe detector possesses measurement thresholds on activity concentration.

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.)

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

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

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.)

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.

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

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

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)

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

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

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

Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

International Nuclear Information System (INIS)

Brits, R.J.N; Prinsloo, L.; De Jesus, A.S.M.

1981-07-01

The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1980. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartbeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 0 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborn activity from nuclear-bomb tests are reported. Due to the absence of fresh fallout, the levels for most fission products have fallen below the limit of detection. No environmental radioactivity resulting from NNRC releases could be detected above the natural background or accumulated fallout levels [af

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.)

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.)

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

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

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

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

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

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

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.

Environmental hazards and distribution of radioactive black sand along the Rosetta coastal zone in Egypt using airborne spectrometric and remote sensing data

International Nuclear Information System (INIS)

Kaiser, M.F.; Aziz, A.M.; Ghieth, B.M.

2014-01-01

High-resolution airborne gamma ray spectrometry, conducted in 2003, was used to estimate radioactive elements spatial abundance along the Rosetta coastal zone area. It was noticed that both Uranium and Thorium are concentrated in the black sand deposits along the beach. In contrary, Potassium was observed in high level abundance at the cultivated Nile Delta lands due to the accumulated usage of fertilizers. Exposure Rate (ER), Absorbed Dose Rate (ADR) and Annual Effective Dose Rate (AEDR) were calculated to evaluate the radiation background influence in human. Results indicated that the human body in the study sites is subjected to radiation hazards exceeds the accepted limit for long duration exposure. In addition, the areas covered by the highest concentration of Uranium and Thorium show the highest level of radiogenic heat production. Detection the environmental hazards of the radioactive black sands in the study site encouraged this research to monitor the spatial and temporal distribution of these sediments. The Landsat Thematic Mapper images acquired in 1990, 2003 and 2013 were analyzed using remote sensing image processing techniques. Image enhancements, classification and changes detection indicated a positive significant relationship between the patterns of coastline changes and distribution of the radioactive black sand in the study sites. The radioactive black sands are usually concentrated in the eroded areas. Therefore, in 1990 high concentration of the radioactive black sands were observed along the eastern and western flanks of the Rosetta promontory. Distribution of these sediments decreased due to the construction of the protective sea walls. Most of the radioactive black sands are transported toward the east in Abu Khashaba bay under the effect of the longshore currents and toward the west in Alexandria and Abu Quir bay under the action of the seasonal reverse currents. - Highlights: • Spatial and temporal distributions of the black sand were

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

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

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)

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

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.

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)

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

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

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.)

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

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.)

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.)

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

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

Analysis of γ spectra in airborne radioactivity measurements using multiple linear regressions

International Nuclear Information System (INIS)

Bao Min; Shi Quanlin; Zhang Jiamei

2004-01-01

This paper describes the net peak counts calculating of nuclide 137 Cs at 662 keV of γ spectra in airborne radioactivity measurements using multiple linear regressions. Mathematic model is founded by analyzing every factor that has contribution to Cs peak counts in spectra, and multiple linear regression function is established. Calculating process adopts stepwise regression, and the indistinctive factors are eliminated by F check. The regression results and its uncertainty are calculated using Least Square Estimation, then the Cs peak net counts and its uncertainty can be gotten. The analysis results for experimental spectrum are displayed. The influence of energy shift and energy resolution on the analyzing result is discussed. In comparison with the stripping spectra method, multiple linear regression method needn't stripping radios, and the calculating result has relation with the counts in Cs peak only, and the calculating uncertainty is reduced. (authors)

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

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

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)

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).

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

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.)

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.

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

Radioactive and geological analysis of airborne gamma spectrometric data for locating favorable traps for uranium prospecting in the Syrian desert (Area-1), Syria

International Nuclear Information System (INIS)

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

2012-01-01

Statistical analysis has been applied to the airborne spectrometric data for the Syrian desert (Area-1), Syria in order to characterize and isolate the anomalous uranium radioactive zones. Equivalent uranium eU values vary between a minimum of 0.01 and a maximum of 32.74 ppm. Uranium prospecting methodology recently proposed is successfully applied in order to explain the origin of the radioactive anomalies related to Area-1. The dominant geological conditions effectively contributing to the uranium radioactive anomalies in the study area have been determined through the analysis of five radioactive-geological profiles. Different favorable traps have been identified and localized for uranium prospecting. Those uranium traps merit further detailed exploration for determining their uranium potential with depth. - Highlights: ► Determine the radioactive characteristics of Area-1. ► Apply a uranium prospecting methodology for guiding uranium exploration activities in Area-1. ► Explain the origin of the radioactive anomalies in Area-1. ► Relate the structural and geological conditions with the anomalous radioactive occurrences.

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

Geophex Airborne Unmanned Survey System

International Nuclear Information System (INIS)

Won, I.L.; Keiswetter, D.

1995-01-01

Ground-based surveys place personnel at risk due to the proximity of buried unexploded ordnance (UXO) items or by exposure to radioactive materials and hazardous chemicals. The purpose of this effort is to design, construct, and evaluate a portable, remotely-piloted, airborne, geophysical survey system. This non-intrusive system will provide stand-off capability to conduct surveys and detect buried objects, structures, and conditions of interest at hazardous locations. During a survey, the operators remain remote from, but within visual distance of, the site. The sensor system never contacts the Earth, but can be positioned near the ground so that weak geophysical anomalies can be detected. The Geophex Airborne Unmanned Survey System (GAUSS) is designed to detect and locate small-scale anomalies at hazardous sites using magnetic and electromagnetic survey techniques. The system consists of a remotely-piloted, radio-controlled, model helicopter (RCH) with flight computer, light-weight geophysical sensors, an electronic positioning system, a data telemetry system, and a computer base-station. The report describes GAUSS and its test results

Geophex Airborne Unmanned Survey System

Energy Technology Data Exchange (ETDEWEB)

Won, I.L.; Keiswetter, D.

1995-12-31

Ground-based surveys place personnel at risk due to the proximity of buried unexploded ordnance (UXO) items or by exposure to radioactive materials and hazardous chemicals. The purpose of this effort is to design, construct, and evaluate a portable, remotely-piloted, airborne, geophysical survey system. This non-intrusive system will provide stand-off capability to conduct surveys and detect buried objects, structures, and conditions of interest at hazardous locations. During a survey, the operators remain remote from, but within visual distance of, the site. The sensor system never contacts the Earth, but can be positioned near the ground so that weak geophysical anomalies can be detected. The Geophex Airborne Unmanned Survey System (GAUSS) is designed to detect and locate small-scale anomalies at hazardous sites using magnetic and electromagnetic survey techniques. The system consists of a remotely-piloted, radio-controlled, model helicopter (RCH) with flight computer, light-weight geophysical sensors, an electronic positioning system, a data telemetry system, and a computer base-station. The report describes GAUSS and its test results.

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

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.)

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)

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.)

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.)

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

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)

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)

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

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.

Environmental risk assessment of airborne emission from chinese coal-fired power plants with public health detriment criteria

International Nuclear Information System (INIS)

He Huimin; Pan Ziqiang; Zhang Yongxing; Xia Yihua

1997-01-01

On the basis of investigation of types of dust removers and their efficiency in Chinese coal-fired power plants, human health detriment of airborne non-radioactive and radioactive emissions from the power plants is assessed with public health detriment assessment method. The results show that the risk is primarily from airborne non-radioactive emission

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)

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

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

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)

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

Continuous monitoring for airborne alpha emitters in a dusty environment

International Nuclear Information System (INIS)

Seiler, F.A.; Newton, G.J.; Guilmette, R.A.

1988-01-01

Disposal of radioactive wastes in underground facilities requires continuous monitoring for airborne radioactive materials, both on the surface and underground. In addition to a natural background of nonradioactive and radioactive aerosols, there may be a sizeable dust contribution from ongoing work such as mining and vehicular traffic. In the monitoring of alpha-emitting radionuclides, these aerosols may lead to self-absorption in the source and a deterioration of the energy spectrum of the detected alpha particles. In this paper, the influence of a realistic background aerosol on the performance of an alpha monitoring system is evaluated theoretically. It is shown that depositing alpha emitters and background aerosol on a surface for counting leads rapidly to a considerable loss of counts, a deterioration of the alpha spectra, an eventual saturation of the count rates, and interference from the natural background of Rn daughters

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.

Airborne systems for emergency radiological monitoring

International Nuclear Information System (INIS)

Jupiter, C.; Boyns, P.

1976-01-01

A variety of aerial radiological monitoring systems are available to respond to a radiological accident or incident affecting large areas. These are operated by EG and G, Inc. for ERDA's Division of Operational Safety. A survey system can be airborne within approximately two hours after notification. Both airborne and terrestrial radioactivity can be measured and mapped. Special analysis procedures allow discrimination between radioactivity from most man-made radioelements and naturally occurring radioelements. A position accuracy of +-54 feet can be maintained over a large area survey. Detection sensitivity for gamma sources employing NaI detector arrays on board an airplane flying at 500 feet altitude is better than 2 μR/hr for surface planar contaminants and approximately 10 mCi for a point gamma source

Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

International Nuclear Information System (INIS)

Brits, R.J.N.; Van der Westhuizen, G.S.H.; Annandale, J.

1983-06-01

The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1982. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartebeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 90 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborne activity from nuclear-bomb tests are reported. Due to absence of fresh fallout material the levels for most fission products have fallen below the limit of detection. No environmental radioactivity due to releases from the Pelindaba site could be detected above the natural background or accumulated fallout levels. Unplanned releases of UF 6 occur sometimes. Accordingly, some of the environmental samples were also analysed for uranium. The results obtained so far do not indicate an increase in uranium levels in the environment

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

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

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.)

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.)

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

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)

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

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

Airborne radiation monitoring using a manned helicopter

International Nuclear Information System (INIS)

Sanada, Yukihisa; Nishizawa, Yukiyasu; Ishizaki, Azusa; Urabe, Yoshimi

2017-01-01

The Great East Japan Earthquake that occurred on 11 March 2011 generated a series of large tsunami waves that caused serious damage to the Fukushima Dai-ichi Nuclear Power Station, following which a large amount of radioactive material was discharged from the nuclear power plant into the environment. Airborne radiation measurements using a manned helicopter were applied to measure the radiation distribution immediately after accident as technique to quickly measure the radiation distribution over a wide area. In Japan, this technique was researched and developed in the 1980s. However, this technique and system were not applied immediately after the accident because standardization of analysis was not established and the Japanese system became deteriorated. This technique is important for post-accident studies at a nuclear facility. We summarized the methods of the airborne radiation measurement using a manned helicopter. In addition, measurement results of the dose rate distribution at the Fukushima Dai-ichi Nuclear Power Station are given in this paper. (author)

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

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

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

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)

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

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.

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

Bulletin of the radioactivity. No. 83. January-December, 1999

International Nuclear Information System (INIS)

2001-01-01

This report contains the result of observations by the Japan Meteorological Agency (JMA) of atmospheric and seawater radioactivity for the year 1999. The sampling, measurement methods and results of gross beta-radioactivity in precipitation, radioactivity in airborne dust, monthly mean 90 Sr concentration in airborne dust, gross beta-radioactivity in seawater, deposition of 89 Sr, 90 Sr and 137 Cs, natural background radioactivity and vertical distribution of atmospheric radioactivity are described. The results of special observations on the criticality accident at an uranium processing plant, Tokai-mura, Japan showed that gamma-ray spectrum analysis in airborne dust indicated Cs-137 ND (lower than detection limit) and I-131 ND in Sendai and Tokyo at sampling at 99/10/1. 09h-99/10/1,14h and in Tsukuba at sampling 99/09/30, 09h-99/10/01, 09h. Gross beta-radioactivity in precipitation showed 40 MBq/km 2 deposition in Hachijo-jima at sampling 99/09/30,09h-99/10/01, 09h, but no precipitation in Sendai, Akita, Tokyo and Wajima. Mean gamma-radiation dose rate in Wajima indicated 9.8 cps at monitoring 99/09/30-99/10/01,15h. (S.Y.)

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

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.)

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)

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

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

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

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.)

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

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)

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.)

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

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

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

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

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)

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

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

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.

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

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)

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.)

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.

Geophysical survey aimed at selecting the radioactive waste repository site (Czech republic

Directory of Open Access Journals (Sweden)

Dušan Dostál

2007-01-01

Full Text Available G IMPULS Praha has been executing a set of geophysical measurements for the Radioactive Waste Repository Authority of the Czech Republic from 2001 (the work continues to be carried out. The measurements are aimed at studying the behaviour of the rock massif, focusing on the Excavation Damaged or Disturbed Zone (EDZ and on selecting an appropriate area for the radioactive material repository site. The geophysical studies use a complex of methods as follows: Airborne geophysical measurement (regional studies, Seismic measurement (detailed studies, G.P.R. (detailed studies, Resistivity tomography (detailed studies, Geoelectric measurement and magnetic survey (stray earth currents. The paper informs about first results and conclusions. The airborne work was executed as a part of the complex study of „GEOBARIERA“ the group and the geophysical measurements of EDZ were executed in co-operation with the Czech Geological Survey.

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

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

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

The fractal nature of the european network for airborne radioactivity monitoring and its implications for the detectability of radioactive clouds

International Nuclear Information System (INIS)

Raes, F.; Graziani, G.

1990-01-01

Both the European Communities (EC) and the International Atomic Energy Agency (IAEA) have agreed upon a rapid exchange of radiological data among their member states, in case of nuclear emergencies. This will happen through an information network operated by the Commission of the European Communities (CEC) and/or through the Global Telecommunications System of WMO. Data coming from nation wide on-line monitoring networks will be among the very first to be exchanged. They will constitute an important source of information for the real-time assessment of the situation after large accidents with national and international impact. In particular when data on airborne radioactivity are availably early after an accidental release, they might be used to update long range transport model predictions for the period to follow. It is therefore important to analyze the national networks in an international context, to see what information they can offer and what limitations exist

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

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

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

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.)

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

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)

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.)

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.)

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

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.)

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)

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)

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

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.)

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

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)

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

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.

Savannah River Plant airborne emissions and controls

International Nuclear Information System (INIS)

Dukes, E.K.; Benjamin, R.W.

1982-12-01

The Savannah River Plant (SRP) was established to produce special nuclear materials, principally plutonium and tritium, for national defense needs. Major operating facilities include three nuclear reactors, two chemical separations plants, a fuel and target fabrication plant, and a heavy-water rework plant. An extensive environmental surveillance program has been maintained continuously since 1951 (before SRP startup) to determine the concentrations of radionuclides in a 1200-square-mile area centered on the plant, and the radiation exposure of the population resulting from SRP operations. This report provides data on SRP emissions, controls systems, and airborne radioactive releases. The report includes descriptions of current measurement technology. 10 references, 14 figures, 9 tables

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

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

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)

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.

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.)

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

International Nuclear Information System (INIS)

2013-01-01

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

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

International Nuclear Information System (INIS)

2012-01-01

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

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

International Nuclear Information System (INIS)

2012-01-01

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

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

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

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

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

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)

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

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.)

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)

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)

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

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

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

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

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

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

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)

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.

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

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

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.

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

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.

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...

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)