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Sample records for cesium radioisotopes

  1. Estimation of the contribution of gamma-emission of incorporated cesium radioisotopes in interpretation of the results of the public survey to assess the thyroidal iodine content following a radiation accident at the nuclear power plant

    Directory of Open Access Journals (Sweden)

    Shinkarev S.M.

    2014-12-01

    Full Text Available Aim. A detail consideration has been done to assess an importance of the contribution of gamma-emission of incorporated cesium radioisotopes to the exposure rate measured near the thyroid by the public survey for following the Chernobyl accident. Empirical ratios have been derived to take into account that contribution under interpretation of the results of survey meter monitoring of the public. Materials and methods. Model calculations for typical radionuclide intake by the residents living in contaminated territories after the Chernobyl accident have been carried out in order to assess the contribution of gamma-emission of incorporated cesium radioisotopes to the exposure rate measured near the thyroid by the survey. Under such calculations two the most important modes of intake have been considered: 1 inhalation and 2 ingestion with cow milk. Results. According to the estimates received the contribution of gamma-emission of incorporated cesium radioisotopes to the exposure rate measured near the thyroid during the first 20 days does not exceed 20% for the residents of southern areas of Gomel region and 30% for the residents of Mogil'yov region. During 60 days following the accident that contribution is estimated to be within (50-80 % for the residents of southern areas of Gomel region and (80-95 % for the residents of Mogil'yov region. Conclusion. For the period of intensive thyroid measuring in the southern areas of Gomel region (the second part of May account of the contribution of gamma-emission of incorporated cesium radioisotopes is relatively unimportant, but for Mogil'yov region (the end of May — it is important to account for. For the thyroid measurements conducted in June of 1986 it is important for all residents living in Belarus to take into account the contribution of gamma-emission of incorporated cesium radioisotopes.

  2. Radioisotopes in industry

    International Nuclear Information System (INIS)

    The author explains clearly what is radiography, enumerates four major factors in considering a practical source to use namely half-life, penetrating power, half value layer and specific activity and also the advantages and disadvantages in using isotopes. Common radioisotopes used in industrial radiography are iridium, cesium, cobalt and thulium. Main uses of the radioisotopes are for radiographic testing like welding castings, forgoings etc.; thickness, level or density measurement and tracing. (RTD)

  3. Decorporation of cesium-137

    International Nuclear Information System (INIS)

    Cesium radio-isotopes, especially cesium-137 (137Cs) are among the radionuclides of main importance produced by a fission reaction in reactor or a nuclear weapon explosion. In the environment, 137Cs is a major contaminant which can cause severe β, γirradiations and contaminations. 137Cs is distributed widely and relatively uniformly throughout the body with the highest concentration in skeletal muscles. A treatment becomes difficult afterwards. The purposes of this report are Firstly to compare the Prussian blue verses cobalt and potassium ferrocyanide (D.I. blue) efficiency for the 137Cs decorporation and secondly to assess a chronological treatment with D.I. blue. (author)

  4. Radioisotope instruments

    CERN Document Server

    Cameron, J F; Silverleaf, D J

    1971-01-01

    International Series of Monographs in Nuclear Energy, Volume 107: Radioisotope Instruments, Part 1 focuses on the design and applications of instruments based on the radiation released by radioactive substances. The book first offers information on the physical basis of radioisotope instruments; technical and economic advantages of radioisotope instruments; and radiation hazard. The manuscript then discusses commercial radioisotope instruments, including radiation sources and detectors, computing and control units, and measuring heads. The text describes the applications of radioisotop

  5. Decorporation of cesium-137; Decorporation du cesium-137

    Energy Technology Data Exchange (ETDEWEB)

    Le Fleche, Ph.; Destombe, C.; Grasseau, A.; Mathieu, J.; Chancerelle, Y.; Mestries, J.C. [GMR, Direction des Recherches, Etudes et Techniques, 94 - Arcueil (France)

    1997-12-31

    Cesium radio-isotopes, especially cesium-137 ({sup 137}Cs) are among the radionuclides of main importance produced by a fission reaction in reactor or a nuclear weapon explosion. In the environment, {sup 137}Cs is a major contaminant which can cause severe {beta}, {gamma}irradiations and contaminations. {sup 137}Cs is distributed widely and relatively uniformly throughout the body with the highest concentration in skeletal muscles. A treatment becomes difficult afterwards. The purposes of this report are Firstly to compare the Prussian blue verses cobalt and potassium ferrocyanide (D.I. blue) efficiency for the {sup 137}Cs decorporation and secondly to assess a chronological treatment with D.I. blue. (author)

  6. Cesium-137

    International Nuclear Information System (INIS)

    This sheet belongs to a collection which relates to the use of radionuclides essentially in unsealed sources. Its goal is to gather on a single document the most relevant information as well as the best prevention practices to be implemented. These sheets are made for the persons in charge of radiation protection: users, radioprotection-skill persons, labor physicians. Each sheet treats of: 1 - the radio-physical and biological properties; 2 - the main uses; 3 - the dosimetric parameters; 4 - the measurement; 5 - the protection means; 6 - the areas delimitation and monitoring; 7 - the personnel classification, training and monitoring; 8 - the effluents and wastes; 9 - the authorization and declaration administrative procedures; 10 - the transport; and 11 - the right conduct to adopt in case of incident or accident. This sheet deals specifically with Cesium-137

  7. Radioisotope Power Supply Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Between 1998 and 2003, Hi-Z Technology developed and built a 40 mW radioisotope power supply (RPS) that used a 1 watt radioisotope heater unit (RHU) as the energy...

  8. Power from Radioisotopes (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Corliss, William R; Mead, Robert L

    1971-01-01

    This booklet discusses Systems for Nuclear Auxiliary Power (SNAP), called isotope power generators, that are based on using heat from the decay of radioisotopes to produce electricity. These are the SNAP systems with odd-numbered designators. The basics of radioisotope thermoelectric generators (RTGs) are discussed and their uses as power sources in space exploration and on earth are described. Various radioisotope heat sources are discussed and a table of RTGs built under the SNAP program listing their uses, electrical power, weight, the radioisotope used, the radioisotope's half-life, and the generator life is given.

  9. Biological effects of cesium-137 injected in beagle dogs of different ages

    Energy Technology Data Exchange (ETDEWEB)

    Nikula, K.J.; Muggenburg, B.A.; Griffith, W.C. [and others

    1995-12-01

    The toxicity of cesium-137 ({sup 137}Cs) in the Beagle dog was investigated at the Argonne National Laboratory (ANL) as part of a program to evaluate the biological effects of internally deposited radionuclides. The toxicity and health effects of {sup 137}Cs are important to understand because {sup 137}Cs is produced in large amounts in light-water nuclear reactors. Large quantities of cesium radioisotopes have entered the human food chain as a result of atmospheric nuclear weapons test, and additional cesium radioisotopes were released during the Chernobyl accident. Although the final analyses are not complete, three findings are significant: older dogs dies significantly earlier than juvenile and young adult dogs; greater occurrence of sarcomas in the cesium-137 injected dogs; the major nonneoplastic effect in dogs surviving beyond 52 d appears to be testicular atrophy.

  10. Economical Radioisotope Power Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Almost all robotic space exploration missions and all Apollo missions to the moon used Radioisotopic Thermoelectric Generators (RTGs) to provide electrical power...

  11. Radioisotope measurement system

    International Nuclear Information System (INIS)

    A radioisotope measurement system installed at L.M.R. (Ezeiza Atomic Center of CNEA) allows the measurement of nuclear activity from a wide range of radioisotopes. It permits to characterize a broad range of radioisotopes at several activity levels. The measurement hardware as well as the driving software have been developed and constructed at the Dept. of Instrumentation and Control. The work outlines the system's conformation and its operating concept, describes design characteristics, construction and the error treatment, comments assay results and supplies use advices. Measuring tests carried out employing different radionuclides confirmed the system performing satisfactorily and with friendly operation. (author)

  12. Leachability of cobalt and cesium from natural and chemically treated zeolites

    International Nuclear Information System (INIS)

    The determination of leachability of radioisotopes of cesium and cobalt from preloaded zeolites in distilled water, base solution and acid solution has been studied. For the experiment, we used natural and chemically treated zeolites. The zeolites before leaching were calcined at different temperatures. (author). 8 refs., 5 figs., 2 tabs

  13. Radioisotope Power Sources

    International Nuclear Information System (INIS)

    The radioisotope power programme of the US Atomic Energy Commission has brought forth a whole new technology of the use of radioisotopes as energy sources in electric power generators. Radioisotope power systems are particularly suited for remote applications where long-lived, compact, reliable power is needed. Able to perform satisfactorily under extreme environmental conditions of temperature, sunlight and electromagnetic radiations, these ''atomic batteries'' are attractive power sources for remote data collecting devices, monitoring systems, satellites and other space missions. Radioisotopes used as fuels generally are either alpha or beta emitters. Alpha emitters are the preferable fuels but are more expensive and less available than beta fuels and are generally reserved for space applications. Beta fuels separated from reactor fission wastes are being used exclusively in land and sea applications at the present. It can be expected, however, that beta emitters such as stiontium-90 eventually will be used in space. Development work is being carried out on generators which will use mixed fission products as fuel. This fuel will be less expensive than the pure radioisotopes since the costs of isotope separation and purification are eliminated. Prototype thermoelectric generators, fuelled with strontium-90 and caesium-137, are now in operation or being developed for use in weather stations, marine navigation aids and deep sea monitoring devices. A plutonium-238 thermoelectric generator is in orbit operating as electric power source in a US Navy TRANSIT satellite. Generators are under development for use on US National Aeronautics and Space Administration missions. The large quantities of radioactivity involved in radioisotope power sources require that special attention be given to safety aspects of the units. Rigid safety requirements have been established and extensive tests have been conducted to insure that these systems can be employed without creating undue

  14. Radioisotopes in Industry

    Energy Technology Data Exchange (ETDEWEB)

    Baker, Philip S. [Oak Ridge National Laboratory; Fuccillo, Jr., Domenic A. [Oak Ridge National Laboratory; Gerrard, Martha W. [Oak Ridge National Laboratory; Lafferty, Jr., Robert H. [Oak Ridge National Laboratory

    1967-05-01

    Radioisotopes, man-made radioactive elements, are used in industry primarily for measuring, testing and processing. How and why they are useful is the subject of this booklet. The booklet discusses their origin, their properties, their uses, and how they may be used in the future.

  15. Radioisotopic heat source

    International Nuclear Information System (INIS)

    Disclosed is a radioisotopic heat source and method for a long life electrical generator. The source includes plutonium dioxide shards and yttrium or hafnium in a container of tantalum-tungsten-hafnium alloy, all being in a nickel alloy outer container, and subjected to heat treatment of from about 15700F to about 17200F for about one h

  16. Manual of radioisotope production

    International Nuclear Information System (INIS)

    The Manual of Radioisotope Production has been compiled primarily to help small reactor establishments which need a modest programme of radioisotope production for local requirements. It is not comprehensive, but gives guidance on essential preliminary considerations and problems that may be met in the early stages of production. References are included as an aid to the reader who wishes to seek further in the extensive literature on the subject. In preparing the Manual, which is in two parts, the Agency consulted several Member States which already have long experience in radioisotope production. An attempt has been made to condense this experience, firstly, by setting out the technical and economic considerations which govern the planning and execution of an isotope programme and, secondly, by providing experimental details of isotope production processes. Part I covers topics common to all radioisotope processing, namely, laboratory design, handling and dispensing of radioactive solutions, quality control, measurement and radiological safety. Part II contains information on the fifteen radioisotopes in most common use. These are bromine-82, cobalt-58, chromium-51, copper-64, fluorine-18, gold-198, iodine-131, iron-59, magnesium-28, potassium-42, sodium-24, phosphorus-32, sulphur-35, yttrium-90 and zinc-65. Their nuclear properties are described, references to typical applications are given and published methods of production are reviewed; also included are descriptions in detail of the production processes used at several national atomic energy organizations. No attempt has been made to distinguish the best values for nuclear data or to comment on the relative merits of production processes. Each process is presented essentially as it was described by the contributor on the understanding that critical comparisons are not necessary for processes which have been well tried in practical production for many years. The information is presented as a guide to enable

  17. Radioisotopes and rice

    International Nuclear Information System (INIS)

    To stimulate research into problems of rice cultivation, the International Atomic Energy Agency has placed several research contracts with agricultural institutes in some of its Member States. Some of these research projects deal with problems of soil-plant relations and fertilization, and rice is one of the main crops on which studies are being made. A panel of experts convened by the Agency met in Vienna in May this year to discuss some of the outstanding problems in the uses of radioisotopes in soil-plant relations and fertilization studies, and problems concerning rice were among the principal subjects considered. In a paper presented at the panel meeting. Professor S. Mitsui, of the University of Tokyo, reviewed some of the main uses of radioisotopes in studying problems of rice soils and rice cultivation and suggested several specific topics in this field which could be investigated by isotope techniques

  18. Radioisotope analyzer of barium

    International Nuclear Information System (INIS)

    Principle of operation and construction of radioisotope barium sulphate analyzer type MZB-2 for fast determination of barium sulphate content in barite ores and enrichment products are described. The gauge equipped with Am-241 and a scintillation detector enables measurement of barium sulphate content in prepared samples of barite ores in the range 60% - 100% with the accuracy of 1%. The gauge is used in laboratories of barite mine and ore processing plant. 2 refs., 2 figs., 1 tab. (author)

  19. Radioisotopes for medical applications

    International Nuclear Information System (INIS)

    For more than 3 decades, the Australian Nuclear Science and Technology Organisation has been the country's main supplier of radioisotopes for medical applications. The use of radioisotopes in medicine has revolutionised the diagnosis, management and treatment of many serious diseases such as cancer, heart disease and stroke. It is also beginning to play a key role in neurological disorders such as Parkinson and Alzheimers disease and epilepsy. More recently there has been considerable growth in the application of nuclear medicine to treat sport-related injuries - especially wrist, ankle and knees where more common techniques do not always enable accurate diagnosis. Australia is a recognised leader in nuclear medicine. This can be partially attributed to the close relationship between ANSTO and the medical community in providing opportunities to develop and evaluate new agents to support more effective patient care. A list of commercial isotopes produced in the reactor or the cyclotron and used in medical applications is given. Nuclear medicine plays an important role in the clinical environment and the timely supply of radioisotopes is a key element. ANSTO will continue to be the premier supplier of currently available and developing isotopes to support the health and well being of the Australian community

  20. Radioisotopes for medical applications

    Energy Technology Data Exchange (ETDEWEB)

    Carr, S. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia). Radiopharmaceuticals Division

    1998-03-01

    For more than 3 decades, the Australian Nuclear Science and Technology Organisation has been the country`s main supplier of radioisotopes for medical applications. The use of radioisotopes in medicine has revolutionised the diagnosis, management and treatment of many serious diseases such as cancer, heart disease and stroke. It is also beginning to play a key role in neurological disorders such as Parkinson and Alzheimers disease and epilepsy. More recently there has been considerable growth in the application of nuclear medicine to treat sport-related injuries - especially wrist, ankle and knees where more common techniques do not always enable accurate diagnosis. Australia is a recognised leader in nuclear medicine. This can be partially attributed to the close relationship between ANSTO and the medical community in providing opportunities to develop and evaluate new agents to support more effective patient care. A list of commercial isotopes produced in the reactor or the cyclotron and used in medical applications is given. Nuclear medicine plays an important role in the clinical environment and the timely supply of radioisotopes is a key element. ANSTO will continue to be the premier supplier of currently available and developing isotopes to support the health and well being of the Australian community 2 tabs., 1 fig.

  1. A radioisotope production facility using 70-120 MeV protons

    International Nuclear Information System (INIS)

    A facility with five target stations for the production of radioisotopes is now available for use by research groups. Four production systems can accept beam intensities from 10 to 100 microamps, with the fifth being under development for proton therapy. The first target is molten LiBr, the second is molten NaI, the third system is for irradiating solid target materials, and the fourth target is molten cesium

  2. Radioisotopes in medicine

    Energy Technology Data Exchange (ETDEWEB)

    Pedrosa de Lima, Joao Jose [Servico de Biofisica/Biomatematica, Faculdade de Medicina, Universidade de Coimbra, Coimbra (Portugal)

    1998-11-01

    Radioisotopes are extensively used in medicine for diagnosis, either in vivo or in vitro, for therapeutics and also for investigation purposes. Nuclear medicine (Nm) studies in vivo are used to detect minimal amounts of radiopharmaceuticals in organs (the morphology) and their course over time (the function), resulting from physico-chemical interactions of the tracers within the body, in the sequence of specific physiological processes. In vitro applications of radioisotopes have become a most important tool in biochemical analysis. Therapeutic uses of radioisotopes cover from external gamma-ray sources in teleradiotherapy to direct cell irradiation in metabolic therapy. The information, which is conveyed by NM, is essentially metabolic and differs from that supplied by the other imaging techniques, which is basically structural. This quality is important in early detection and diagnosis. Efforts have steadily been made to bring NM imaging as close as possible to an ideal medical diagnostic tool: non-invasive and allowing studies yielding functional, morphological, three-dimensional and quantitative information simultaneously. Of the two tomographic techniques available in NM, positron emission tomography (PET) is probably closer to this goal than single-photon emission tomography (SPECT). High-contrast functional images of the dynamics of labelled molecules (native or functionally similar) that are metabolized by the organs under investigation, are obtained with these techniques. Nuclear medicine has progressed as a result of advances in four strategic areas: the development of new radiopharmaceuticals, the technology and reliability of detectors, the capacity for modelling the metabolic fate of the inputs in the biological systems, and finally the ability to extract and process data. (author)

  3. Frontiers in radioisotope application

    International Nuclear Information System (INIS)

    Radioisotopes and radiation are being used in numerous and diverse fields to benefit mankind. A glimpse at the recent advances in terms of usage of new radionuclides or new techniques, in some of the important areas are discussed. Use of radionuclides in medicine, industries, agriculture and water resource management are delineated. The various uses of radiation such as cancer therapy, sterilization of medical products, disinfestation of food products, food preservation, industrial radiography, nucleonic gauges, crop mutation to raise better quality seeds, cross-linking and curing of materials, coatings etc. and treatment of municipal waste are discussed. (author). 56 refs., 4 tabs

  4. Cesium reservoir and interconnective components

    International Nuclear Information System (INIS)

    The program objective is to demonstrate the technology readiness of a TFE (thermionic fuel element) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW range. A thermionic converter must be supplied with cesium vapor for two reasons. Cesium atoms adsorbed on the surface of the emitter cause a reduction of the emitter work function to permit high current densities without excessive heating of the emitter. The second purpose of the cesium vapor is to provide space-charge neutralization in the emitter-collector gap so that the high current densities may flow across the gap unattenuated. The function of the cesium reservoir is to provide a source of cesium atoms, and to provide a reserve in the event that cesium is lost from the plasma by any mechanism. This can be done with a liquid cesium metal reservoir in which case it is heated to the desired temperature with auxiliary heaters. In a TFE, however, it is desirable to have the reservoir passively heated by the nuclear fuel. In this case, the reservoir must operate at a temperature intermediate between the emitter and the collector, ruling out the use of liquid reservoirs. Integral reservoirs contained within the TFE will produce cesium vapor pressures in the desired range at typical electrode temperatures. The reservoir material that appears to be the best able to meet requirements is graphite. Cesium intercalates easily into graphite, and the cesium pressure is insensitive to loading for a given intercalation stage. The goals of the cesium reservoir test program were to verify the performance of Cs-graphite reservoirs in the temperature-pressure range of interest to TFE operation, and to test the operation of these reservoirs after exposure to a fast neutron fluence corresponding to seven year mission lifetime. In addition, other materials were evaluated for possible use in the integral reservoir

  5. Safe Handling of Radioisotopes

    International Nuclear Information System (INIS)

    Under its Statute the International Atomic Energy Agency is empowered to provide for the application of standards of safety for protection against radiation to its own operations and to operations making use of assistance provided by it or with which it is otherwise directly associated. To this end authorities receiving such assistance are required to observe relevant health and safety measures prescribed by the Agency. As a first step, it has been considered an urgent task to provide users of radioisotopes with a manual of practice for the safe handling of these substances. Such a manual is presented here and represents the first of a series of manuals and codes to be issued by the Agency. It has been prepared after careful consideration of existing national and international codes of radiation safety, by a group of international experts and in consultation with other international bodies. At the same time it is recommended that the manual be taken into account as a basic reference document by Member States of the Agency in the preparation of national health and safety documents covering the use of radioisotopes.

  6. Cesium-137 in biosphere

    International Nuclear Information System (INIS)

    The behaviour of cesium-137 in environment is reviewed. Problems on 137Cs migration in environment, on metabolism andbiological effects are considered. Data on nuclide accumulation in various plants, ways of their entering the man's organism are presented. It is marked that the rate of 137Cs metabolism in the man's organism depends considerably on age, sex, temperature of environment, conditions for activity, water and mineral metabolism and some other factors. It is shown that the annual effective equivalent dose per capita will increase to 2000 yr. up to 1 μSv, that constitutes 0.05% of the average value of irradiation by a natural source

  7. Removal of cesium using coconut fiber in raw and modified forms for the treatment of radioactive liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Jesus, Nella N.M. de; Nobre, Vanessa B.; Potiens Junior, Ademar J.; Sakata, Solange K., E-mail: sksakata@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Di Vitta, Patricia B. [Universidade de Sao Paulo (USP), SP (Brazil). Instituto de Quimica

    2013-07-01

    Sorption is one of the most studied methods to reduce the volume of radioactive waste streams. Cesium-137 is a radioisotope formed by the fission of uranium and it can cause health problems due to its easy assimilation by cells. The aim of this study is to evaluate the potential of coconut fiber in removing cesium from radioactive liquid wastes; this process can help in disposing radioactive waste. The experiments were performed in batch and the particle size of the fiber ranged between 0.30 mm and 0.50 mm. The fiber was treated with hydrogen peroxide in alkaline medium. The following parameters were analyzed: contact time, pH and concentration of cesium ions in aqueous solution. After the experiments the samples were filtered and cesium remaining in solution was quantified by inductively coupled plasma optical emission spectrometry. (author)

  8. Radioisotope production in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Wan Anuar Wan Awang [Medical Technology Div., Malaysian Inst. for Nuclear Technology Research (MINT) (Malaysia)

    1998-10-01

    Production of Mo-99 by neutron activation of Mo-99 in Malaysia began as early as 1984. Regular supply of the Tc-99m extracted from it to the hospitals began in early 1988 after going through formal registration with the Malaysian Ministry of Health. Initially, the weekly demand was about 1.2 Ci of Mo-99 which catered the needs of 3 nuclear medicine centres. Sensitive to the increasing demand of Tc-99m, we have producing our own Tc-99m generator from imported TeO{sub 2} because irradiation TeO{sub 2} with our reactor give low yield of I-131. We have established the production of radioisotope for industrial use. By next year, Sm-153 EDTMP will be produce after we have license from our competent authority. (author)

  9. Radioisotopes in sedimentology

    International Nuclear Information System (INIS)

    Radioisotopes have two main uses in sedimentology: they are used for the study of sediment movements in rivers and seas, and for continuous measurements of the amount of sediment suspended in a given medium. These two uses are considered in detail, and brief accounts given of some other uses. Study of sediment movements. After describing the basic technique used in sediment movement studies (injection of a labelled sediment or a simulator into the current, followed by tracking the radioactivity), the author enumerates as fully as possible the problems that can be solved with the help of this technique. Essentially, these problems fall into two groups: 1. Problems related to civil engineering works in coastal areas: the siltation of harbour channels and docks, the formation of banks and bars, the choice of sites for disposing of dredged sediment, the siting of ports, coastline protection, etc. Problems associated with civil engineering works in and near rivers; siting of the water intakes of hydroelectric and nuclear power stations, the effects of construction work on the transport of solids, the construction of dams, the protection of river banks, the construction of jetties, the siltation of lakes, etc. Problems common to these include the transport of effluent and the calibration of hydraulic models. The bibliography is based mainly on fairly recent references and on current research work. 2. Problems related to basic or applied research conducted mainly by universities and research centres: the study of the Quarternary of a particular region, pure sedimentology, the investigation of major sediment transport currents, the confirmation or refutation of transport theories, research into fundamental transport phenomena associated with channel experiments. After referring to the possible exploitation of natural tracers (contained in radioactive waste and fallout), the author discusses the technical aspects of using artificial tracers: the choice of radioisotope

  10. Agricultural application of radioisotopes

    International Nuclear Information System (INIS)

    The radiations and isotopic tracers laboratory (R.I.T.L.) is duly approved B-class laboratory for handling radioactivity and functions as a central research facility of our university which has played a very significant role in ushering green revolution in the country. Radiolabelled fertilizers, insecticides and isotopes mostly supplied by Board of Radiation and Isotope Technology, (BRIT) Department of Atomic Energy (DAE) are being used in our university for the last three decades to study the uptake of fertilizers, micro nutrients, photosynthesis and photorespiration studies in different crop plants, soil-water-plant relations and roots activity, pesticides and herbicides mode of action, plants physiology and microbiology. Main emphasis of research so far has been concentrated on the agricultural productivity. The present talk is an attempt to highlight the enormous potential of radioisotopes to evolve better management of crop system for eco-friendly and sustainable agriculture in the next century. (author)

  11. Foliar uptake of cesium, iodine and strontium and their transfer to the edible parts of beans, potatoes and radishes

    Science.gov (United States)

    Oestling, O.; Kopp, P.; Burkart, W.

    Considerable fractions of radionuclide solutions deposited on the surface of the leaves may be transferred to the edible parts of plants. In radishes we observed a transfer of more than 40% of the applied cesium radioisotope within a few days. A rather similar uptake was found for beans and potatoes when harvested a month after application of radioactivity. As much as 60% of the applied cesium-isotope remained in (or on) the potato leaves even 8 days after application. The major part could however be washed off the leaves a few hours after application. When radishes were showered with water within 7 h after the application of activity the uptake was greatly reduced. No competitive effect of potassium chloride for the foliar uptake of cesium was found. A 10 -2 M colloidal suspension of Prussian Blue, a chelating agent for monovalent alkali metals such as potassium, cesium, or other monovalent cations, applied as droplets to the leaves one day prior to application of active cesium was found to strongly inhibit the transfer of cesium to the radish. The transfer of iodine and strontium to the edible parts was found to be negligible (or slower) as compared to cesium. In most cases no detectable amounts of these two nuclides were transfered to the edible parts of the radish after 2-5 weeks.

  12. Cesium diffusion in graphite

    Energy Technology Data Exchange (ETDEWEB)

    Evans, R.B. III; Davis, W. Jr.; Sutton, A.L. Jr.

    1980-05-01

    Experiments on diffusion of /sup 137/Cs in five types of graphite were performed. The document provides a completion of the report that was started and includes a presentation of all of the diffusion data, previously unpublished. Except for data on mass transfer of /sup 137/Cs in the Hawker-Siddeley graphite, analyses of experimental results were initiated but not completed. The mass transfer process of cesium in HS-1-1 graphite at 600 to 1000/sup 0/C in a helium atmosphere is essentially pure diffusion wherein values of (E/epsilon) and ..delta..E of the equation D/epsilon = (D/epsilon)/sub 0/ exp (-..delta..E/RT) are about 4 x 10/sup -2/ cm/sup 2//s and 30 kcal/mole, respectively.

  13. Milliwatt Radioisotope Stirling Convertor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Studies of potential space missions have highlighted the need for very small electric power supplies for a variety of applications. The light weight radioisotope...

  14. Medical application of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang Woon; Lim, S. M.; Kim, E. H. [and others

    2000-05-01

    In this project, we studied following subjects: 1. Clinical research for radionuclide therapy 2. Development of in vitro assay method with radioisotope 3. Development of binary therapy; Boron neutron capture therapy and photodynamic therapy 4. Development of diagnostic methods in radionuclide imaging. The results can be applied for the following objectives: (1) Radionuclide therapy will be applied in clinical practice to treat the cancer patients or other diseases in multi-center trial (2) The newly developed monoclonal antibodies and biomolecules can be used in biology, chemistry or other basic life science research (3) The new methods for the analysis of therapeutic effects, such as dosimetry, and quantitative analysis methods of radioactivity, can be applied in basic research, such as radiation oncology and radiation biology (4) The result of the project will be expected to develop the new radioimmunoassay for drug monitoring following the clinical experiments (5) Boron porphyrin has been successfully labeled with iodine. This enables the pharmacodynamic study of the boron compound in human body (6) A method to evaluate the biological effect of neutrons on tumor cells has been developed (7) The establishment of macro- and microscopic dose assessment using alpha-track autoradiography (8) Clinical application of PDT in bladder cancers, oropharyngeal cancer and skin cancer (9) Radionuclide imaging of estrogen receptor in breast cancer, lipid metabolism, gene therapy, cancers, brain function and heart disease.

  15. Medical application of radioisotopes

    International Nuclear Information System (INIS)

    In this project, we studied following subjects: 1. Clinical research for radionuclide therapy 2. Development of in vitro assay method with radioisotope 3. Development of binary therapy; Boron neutron capture therapy and photodynamic therapy 4. Development of diagnostic methods in radionuclide imaging. The results can be applied for the following objectives: 1) Radionuclide therapy will be applied in clinical practice to treat the cancer patients or other diseases in multi-center trial 2) The newly developed monoclonal antibodies and biomolecules can be used in biology, chemistry or other basic life science research 3) The new methods for the analysis of therapeutic effects, such as dosimetry, and quantitative analysis methods of radioactivity, can be applied in basic research, such as radiation oncology and radiation biology 4) The result of the project will be expected to develop the new radioimmunoassay for drug monitoring following the clinical experiments 5) Boron porphyrin has been successfully labeled with iodine. This enables the pharmacodynamic study of the boron compound in human body 6) A method to evaluate the biological effect of neutrons on tumor cells has been developed 7) The establishment of macro- and microscopic dose assessment using alpha-track autoradiography 8) Clinical application of PDT in bladder cancers, oropharyngeal cancer and skin cancer 9) Radionuclide imaging of estrogen receptor in breast cancer, lipid metabolism, gene therapy, cancers, brain function and heart disease

  16. Manual for reactor produced radioisotopes

    International Nuclear Information System (INIS)

    Radioisotopes find extensive applications in several fields including medicine, industry, agriculture and research. Radioisotope production to service different sectors of economic significance constitutes an important ongoing activity of many national nuclear programmes. Radioisotopes, formed by nuclear reactions on targets in a reactor or cyclotron, require further processing in almost all cases to obtain them in a form suitable for use. Specifications for final products and testing procedures for ensuring quality are also an essential part of a radioisotope production programme. The International Atomic Energy Agency (IAEA) has compiled and published such information before for the benefit of laboratories of Member States. The first compilation, entitled Manual of Radioisotope Production, was published in 1966 (Technical Reports Series No. 63). A more elaborate and comprehensive compilation, entitled Radioisotope Production and Quality Control, was published in 1971 (Technical Reports Series No. 128). Both served as useful reference sources for scientists working in radioisotope production worldwide. The 1971 publication has been out of print for quite some time. The IAEA convened a consultants meeting to consider the need for compiling an updated manual. The consultants recommended the publication of an updated manual taking the following into consideration: significant changes have taken place since 1971 in many aspects of radioisotope production; many radioisotopes have been newly introduced while many others have become gradually obsolete; considerable experience and knowledge have been gained in production of important radioisotopes over the years, which can be preserved through compilation of the manual; there is still a need for a comprehensive manual on radioisotope production methods for new entrants to the field, and as a reference. It was also felt that updating all the subjects covered in the 1971 manual at a time may not be practical considering the

  17. Radioisotopes for All - Low-energy accelerators for radioisotope production

    International Nuclear Information System (INIS)

    Full text of publication follows. Since the development of the tracer principle by George de Hevesy in 1913, radioisotopes have become an integral part of medical practice and research. The imaging modalities Positron Emission Tomography (PET) and Single Photon Emission Computed Tomography (SPECT) have significantly enhanced our understanding of human biology and the development and progression of disease. Radioimmunotherapy (RIT) combines the cancer killing of radiation therapy with the targeting precision of immunotherapy to provide personalised cancer treatment. The technetium-99m crisis in 2008 highlighted the fragility of the current radioisotope supply network. Despite the significant impact of the shortages, only a handful of potential solutions have begun to be explored and developed. The supply of Tc-99m is again in doubt, with the shutdown of the High Flux Reactor (HFR) at Petten looming in 2014. Low-energy accelerators have the potential to greatly increase the availability of radioisotopes by providing a small, lower-cost production solution. Implementing these as a system of localised production centres that supply a small area would greatly reduce the impact of a facility shutdown and eliminate the risk of world-wide shortages. An accelerator system that is not tailored to the production of a single isotope will allow researchers to explore new options for SPECT, PET and RIT and improve access to radioisotopes for medical testing. The potential of low-energy accelerators for radioisotope production will be explored. Several case studies of production will be presented using both well-established and new isotopes to the fields of nuclear imaging and radiotherapy. These will include zirconium-89, iodine-123 and titanium-45. Calculated yields will be compared to predicted nuclear medicine requirements. Expected radionuclidic impurities will also be quantified with a discussion of suitable, simple radiochemical separation systems. The DC electrostatic

  18. INR capabilities for radioisotope production

    International Nuclear Information System (INIS)

    Radioisotope production at INR Pitesti was developed upon the basis of two TRIGA reactors, one stationary and the other pulsed (TRIGA SSR 14 MW and TRIGA ACPR 20000 MW). The TRIGA SSR 14 MW presents two types of neutron spectra in the irradiations channels: a thermal spectrum from a water channel in the core and a channel in the reflector, suitable for irradiations of materials with high thermal neutron cross sections; a hard spectrum of the fuel type obtained through the removal of a fuel pin in a cluster, suitable for irradiations of nuclides with significant epithermal. For the radioisotope production five irradiation devices were used: capsules with the raw materials; capsules for iridium; capsules for radioisotope of medical use; irradiations pins and capsules; capsules with pins. These devices are used for irradiations in the core for production of radioisotopes of industrial use (for instance 192 Ir). For irradiations in the reflector with develop special devices for the production of radioisotope medical used (131 I, 192 Ir and 60 Co). Underway are studies for establishing the optimal conditions for the production of the fission products 99 Mo, 131 I, 133 Xe and of 125 I produce by neutron activation

  19. Apparatus for eluting a daughter radioisotope from a parent radioisotope

    International Nuclear Information System (INIS)

    Apparatus for eluting a sterile daughter radioisotope from a parent radioisotope including a case, a generator having a supply of the parent radioisotope therein, a primary shield enclosing the generator for shielding against radioactive emissions from the parent radioisotope, and an annular wall extending up from the bottom of the case defining a compartment for reception of the primary shield thereby to hold the latter in position within the case is described. A vertical web extends between the annular wall and an exterior wall of the case. An auxiliary shield of suitable shielding material (e.g., lead) generally of the height of the primary shield is provided, this auxiliary shield having an inner cylindric surface conforming generally to the outer surface of the annular wall and having a slot therein for receiving the web. Thus, with the auxiliary shield positioned in the case adjacent the annular wall and with the web received by the slot, the auxiliary shield is held by the web in position in the case for shielding the user from excessive radioactive emissions from the generator in the event the radioactive emissions from the generator exceed the shielding capability of the primary shield

  20. Studies on cesium sorption in hydrous zirconium and titanium oxides

    International Nuclear Information System (INIS)

    Significant quantities of 137Cs (T1/2 = 30.1 y) and 90Sr (T1/2 = 28.5 y) are produced as fission products in nuclear reactors. These long-lived gamma-emitting radionuclides, regarded as a waste few decades ago, are being termed now as valuables owing to the upsurge in the utilization of these radioisotopes in the area of medicine, food irradiation, and sewage treatment technologies in recent years. For long-term waste management it is necessary to minimize the volume and toxicity of the waste. Selective recovery and utilization of these radionuclides from the waste is the concept of growing interest to many researchers. Inorganic sorbents are proven candidates for the separation and recovery of cesium and strontium from aqueous waste streams. They are chemically durable and stable against ionizing radiation. In addition, these materials can be converted into unleachable ceramic form for final disposal. Hydrous metal oxides belong to a particular class of inorganic ion exchangers extensively investigated for various applications in nuclear waste treatment. The present study deals with the preparation of hydrous zirconium and titanium oxide and the studies aimed at separation of cesium from aqueous wastes

  1. Cesium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

    1992-03-01

    Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of [sup 137]Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of [sup 137]Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope [sup 137]Cs releases have resulted in a negligible risk to the environment and the population it supports.

  2. Cesium in the Savannah River Site environment

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

    1992-03-01

    Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of {sup 137}Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of {sup 137}Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope {sup 137}Cs releases have resulted in a negligible risk to the environment and the population it supports.

  3. Uses of radioisotopes in Sudan

    International Nuclear Information System (INIS)

    In this research project, an inventory for the different radioisotopes that were imported by public and private sectors of Sudan in the period between ( 2007-2011) has been set up. These organizations import the appropriates for different but in general we classify them into these applications: Medical, Industrial, Agricultural and Research. However, each broad discipline is subdivided into subgroups. This inventory will help those who are willing to establish research reactors in Sudan on the type and power of the reactors to be purchases according to the actual needs of Sudan with forecasting of the near and for future needs. Also the expenditure that has been spent by these organizations have been estimated for most of the radioisotopes. It was observed that almost 50% of the expenditure went for the fright charges as these radioisotopes need special handling and care by installing a research reactor in Sudan, the cost of purchasing will be cut down several folds. Also it will help in availability of the radioisotopes with very short half lives (hours to days). This will be reflected in the cut down the cost of tests and provision of new tests.(Author)

  4. Cesium transport data for HTGR systems

    International Nuclear Information System (INIS)

    Cesium transport data on the release of cesium from HTGR fuel elements are reviewed and discussed. The data available through 1976 are treated. Equations, parameters, and associated variances describing the data are presented. The equations and parameters are in forms suitable for use in computer codes used to calculate the release of metallic fission products from HTGR fuel elements into the primary circuit. The data cover the following processes: (1) diffusion of cesium in fuel kernels and pyrocarbon, (2) sorption of cesium on fuel rod matrix material and on graphite, and (3) migration of cesium in graphite. The data are being confirmed and extended through work in progress

  5. Radioisotope x-ray analysis

    International Nuclear Information System (INIS)

    Radioisotope x-ray fluorescence and x-ray preferential absorption (XRA) techniques are used extensively for the analysis of materials, covering such diverse applications as analysis of alloys, coal, environmental samples, paper, waste materials, and metalliferous mineral ores and products. Many of these analyses are undertaken in the harsh environment of industrial plants and in the field. Some are continuous on-line analyses of material being processed in industry, where instantaneous analysis information is required for the control of rapidly changing processes. Radioisotope x-ray analysis systems are often tailored to a specific but limited range of applications. They are simpler and often considerably less expensive than analysis systems based on x-ray tubes. These systems are preferred to x-ray tube techniques when simplicity, ruggedness, reliability, and cost of equipment are important; when minimum size, weight, and power consumption are necessary; when a very constant and predictable x-ray output is required; when the use of high-energy x-rays is advantageous; and when short x-ray path lengths are required to minimize the absorption of low-energy x-rays in air. This chapter reviews radioisotope XRF, preferential absorption, and scattering techniques. Some of the basic analysis equations are given. The characteristics of radioisotope sources and x-ray detectors are described, and then the x-ray analytical techniques are presented. The choice of radioisotope technique for a specific application is discussed. This is followed by a summary of applications of these techniques, with a more detailed account given of some of the applications, particularly those of considerable industrial importance. 79 refs., 28 figs., 7 tabs

  6. Present status of OAP radioisotope production

    International Nuclear Information System (INIS)

    Radioisotope Production Program (RP), Office of Atoms for Peace (OAP) is a non-profit government organization which responsible for research development and service of radioisotopes. Several research works on radioisotope production have been carried on at OAP. The radioisotope products of successful R and D have been routinely produced to supply for medical, agriculture and research application. The main products are 131I (solution and capsule), 131I-MIBG, 131I-Hippuran, 153Sm-EDTMP, 153Sm-HA, and 99mTc-radiopharmaceutical kits to serve local users. Radioisotopes are very beneficial for science and human welfare so as almost of our products and services are mainly utilized for medical purpose for both diagnosis and therapy. OAP has a policy to serve and response to that community by providing radioisotopes and services with high quality but reasonable price. This policy will give the opportunity to the community to utilize these radioisotopes for their healthcare. (author)

  7. Radioisotope handling facilities and automation of radioisotope production

    International Nuclear Information System (INIS)

    If a survey is made of the advances in radioisotope handling facilities, as well as the technical conditions and equipment used for radioisotope production, it can be observed that no fundamental changes in the design principles and technical conditions of conventional manufacture have happened over the last several years. Recent developments are mainly based on previous experience aimed at providing safer and more reliable operations, more sophisticated maintenance technology and radioactive waste disposal. In addition to the above observation, significant improvements have been made in the production conditions of radioisotopes intended for medical use, by establishing aseptic conditions with clean areas and isolators, as well as by introducing quality assurance as governing principle in the production of pharmaceutical grade radioactive products. Requirements of the good manufacturing practice (GMP) are increasingly complied with by improving the technical and organizational conditions, as well as data registration and documentation. Technical conditions required for the aseptic production of pharmaceuticals and those required for radioactive materials conflicting in some aspects are because of the contrasting contamination mechanisms and due consideration of the radiation safety. These can be resolved by combining protection methods developed for pharmaceuticals and radioactive materials, with the necessary compromise in some cases. Automation serves to decrease the radiation dose to the operator and environment as well as to ensure more reliable and precise radiochemical processing. Automation has mainly been introduced in the production of sealed sources and PET radiopharmaceuticals. PC controlled technologies ensure high reliability for the production and product quality, whilst providing automatic data acquisition and registration required by quality assurance. PC control is also useful in the operation of measuring instruments and in devices used for

  8. The radioisotopes and radiations program

    International Nuclear Information System (INIS)

    This program of the National Atomic Energy Commission of Argentina refers to the application and production of radionuclides, their compounds and sealed sources. The applications are carried out in the medical, agricultural, cattle raising and industrial areas and in other engineering branches. The sub-program corresponding to the production of radioactive materials includes the production of radioisotopes and of sealed sources, and an engineering service for radioactive materials production and handling facilities. The sub-program of applications is performed through several groups or laboratories in charge of the biological and technological applications, intensive radiation sources, radiation dosimetry and training of personnel or of potential users of radioactive material. Furthermore, several aspects about technology transfer, technical assistance, manpower training courses and scholarships are analyzed. Finally, some legal aspects about the use of radioisotopes and radiations in Argentina are pointed out. (M.E.L.)

  9. Physical aspects of radioisotope brachytherapy

    International Nuclear Information System (INIS)

    The present report represents an attempt to provide, within a necessarily limited compass, an authoritative guide to all important physical aspects of the use of sealed gamma sources in radiotherapy. Within the report, reference is made wherever necessary to the more extensive but scattered literature on this subject. While this report attempts to cover all the physical aspects of radioisotope 'brachytherapy' it does not, of course, deal exhaustively with any one part of the subject. 384 refs, 3 figs, 6 tabs

  10. Extraction of radioactive cesium from tea leaves

    International Nuclear Information System (INIS)

    Radioactive contamination of foodstuffs attributed to the Fukushima Daiichi nuclear disaster has become a social problem. This study investigated the extraction of radioactive cesium from the contaminated leaves to the tea. The green tea was brewed twice reusing the same leaves to study the difference in extraction of cesium between the first and second brew. Moreover, the extraction of cesium was studied in correlation to brewing time. The concentration of radioactive cesium was determined with gamma spectrometry, and the concentration of caffeine was determined with absorption spectrometry. About 40% of cesium was extracted from leaves in the first brew, and about 80% was extracted in the second brew. The extraction of cesium increased over time, and it reached about 80% after 10 minutes brew. The ratio of radioactive cesium to caffeine decreased linearly over time. This study revealed that the extraction of cesium was higher for the second brew, and a rapid increase in extraction was seen as the tea was brewed for 6 minutes and more. Therefore, the first brew of green tea, which was brewed within 5 minutes, contained the least extraction of radioactive cesium from the contaminated leaves. (author)

  11. Research trends in radioisotopes: a scientometric analysis

    International Nuclear Information System (INIS)

    Radioisotopes or radionuclides are radioactive forms of elements and are usually produced in research reactors and accelerators. They have wide ranging applications in healthcare, industry, food and agriculture, and environmental monitoring. Following over five decades of vast experience accumulated, radioisotope technology has developed to a high degree of sophistication and it is estimated that about 200 radioisotopes are in regular use. This paper attempts to highlight the publication status and growth of radioisotope research across the world and make quantitative and qualitative assessment by way of analyzing the following features of research output based on Web of Science database during the period 1993-2012. (author)

  12. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1985

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A.

    1986-08-01

    This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1) isotope suppliers, facility contacts, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfer - FY 1985.

  13. Activity of cesium-134 and cesium-137 in game and mushrooms in Poland

    International Nuclear Information System (INIS)

    The activity of cesium-134 and cesium-137 was measured in mushrooms and game in 1986-1991. The samples were collected all over Poland and most of the measurements were carried out for export purposes. The results indicate that the activity ratio of cesium-137 to cesium-134 in some samples is not comparable to that with fallout after the Chernobyl accident. The analysis of some samples of mushrooms from 1985 showed that the activity of cesium-137 was higher compared to any other foodstuff. The level of contamination varied greatly throughout Poland

  14. Radioisotope studies on coconut nutrition

    International Nuclear Information System (INIS)

    Studies on coconut nutrition using radioisotopes are reviewed. Methods of soil placement and plant injection techniques for feeding nutrients to coconut have been studied, and irrigation practices for efficient uptake and utilization of nutrients are suggested. The absorption, distribution and translocation pattern of radioactive phosphorus and its incorporation into the nucleic acid fraction in healthy and root (wilt) diseased coconut palms have been studied. Carbon assimilation rates (using carbon-14) in spherical, semispherical and erect canopied coconut palms having different yield characteristics are reviewed and discussed. (author)

  15. Current Status of Radioisotope Applications in Defence

    Directory of Open Access Journals (Sweden)

    P. K. Bhatnagar

    1987-07-01

    Full Text Available Reviews the current status of radioisotope applications in Defence- R&D Establishments, Defence Inspectorates, Ordnance Factories, Public Sector Undertakings under the Defence Ministry, Army, Navy and Air Force Establishments and Military Hospitals. It also lists the users of film badge service in Defence. Training programmes in radioisotope applications in Defence conducted by DRDO organisations have also been highlighted.

  16. Trends in the development of radioisotope batteries

    International Nuclear Information System (INIS)

    Improved methods for producing radioisotopes by nuclear fuel reprocessing and the rapid development of microelectronics offer new possibilities for utilizing radioisotope batteries. A review is given of the main principles of conversion of decay energy into electric power. The current state of such energy sources is evaluated. Finally, new fields of application and further trends in the development are indicated. (author)

  17. Study of Radioisotope Requirements For Power Devices

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Nathan W

    1962-01-01

    The tables of this report summarize firm and anticipated radioisotope requirements and list the projects for which radioisotope electric power generators may be used. This compilation represents the results of a study made by Nathan W. Snyder of Royal Research Corporation for the Division of Isotopes Development, U. S. Atomic Energy Commission.

  18. Linear accelerator for radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

    Hansborough, L.D.; Hamm, R.W.; Stovall, J.E.

    1982-02-01

    A 200- to 500-..mu..A source of 70- to 90-MeV protons would be a valuable asset to the nuclear medicine program. A linear accelerator (linac) can achieve this performance, and it can be extended to even higher energies and currents. Variable energy and current options are available. A 70-MeV linac is described, based on recent innovations in linear accelerator technology; it would be 27.3 m long and cost approx. $6 million. By operating the radio-frequency (rf) power system at a level necessary to produce a 500-..mu..A beam current, the cost of power deposited in the radioisotope-production target is comparable with existing cyclotrons. If the rf-power system is operated at full power, the same accelerator is capable of producing an 1140-..mu..A beam, and the cost per beam watt on the target is less than half that of comparable cyclotrons.

  19. US Department of Energy radioisotope customers with summary of radioisotope shipments, FY 1988

    Energy Technology Data Exchange (ETDEWEB)

    Van Houten, N.C.

    1989-06-01

    Pacific Northwest Laboratory (PNL) prepared this edition of the radioisotope customer list at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, US Department of Energy (DOE). This is the 25th report in a series dating from 1964. This report covers DOE radioisotope sales and distribution activities by its facilities to domestic, foreign and other DOE facilities for FY 1988. The report is divided into five sections: radioisotope suppliers, facility contacts, and radioisotopes or services supplied; a list of customers, suppliers, and radioisotopes purchased; a list of radioisotopes purchased cross-referenced to customer numbers; geographic locations of radioisotope customers; and radioisotope sales and transfers -- FY 1988. Radioisotopes not previously reported in this series of reports were argon-37, arsenic-72, arsenic-73, bismuth-207, gadolinium-151, rhenium-188, rhodium-101, selenium-72, xenon-123 and zirconium-88. The total value of DOE radioisotope sales for FY 1988 was $11.1 million, an increase of 3% from FY 1987.

  20. US Department of Energy radioisotope customers with summary of radioisotope shipments, FY 1988

    International Nuclear Information System (INIS)

    Pacific Northwest Laboratory (PNL) prepared this edition of the radioisotope customer list at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, US Department of Energy (DOE). This is the 25th report in a series dating from 1964. This report covers DOE radioisotope sales and distribution activities by its facilities to domestic, foreign and other DOE facilities for FY 1988. The report is divided into five sections: radioisotope suppliers, facility contacts, and radioisotopes or services supplied; a list of customers, suppliers, and radioisotopes purchased; a list of radioisotopes purchased cross-referenced to customer numbers; geographic locations of radioisotope customers; and radioisotope sales and transfers -- FY 1988. Radioisotopes not previously reported in this series of reports were argon-37, arsenic-72, arsenic-73, bismuth-207, gadolinium-151, rhenium-188, rhodium-101, selenium-72, xenon-123 and zirconium-88. The total value of DOE radioisotope sales for FY 1988 was $11.1 million, an increase of 3% from FY 1987

  1. Surface tension of liquid dilute solutions of lead-cesium and bismuth-cesium systems

    International Nuclear Information System (INIS)

    Method of the maximal pressure in a drop was used to measure the surface tension of 15 liquid dilute solutions of lead-cesium system in 0-0.214 at% concentration range and of 12 diluted solutions of bismuth-cesium system in 0-0.160 at.% cesium range from solidification temperature up to 500 dec C. It was found that cesium was characterized as surfactant in lead and bismuth melts. It was established that the temperature coefficient of surface tension changes sufficiently in maximally diluted solutions of alkali metals in bismuth and lead melts. Effect of sodium, potassium, rubidum and cesium on the value of surface tension of lead and bismuth was systematized. Growth of activity in sodium, potassium, rubidium and cesium series was noted

  2. Sorption of cesium on Latvian clays

    International Nuclear Information System (INIS)

    Cesium is like potassium - good solubility and mobile in a ground, easily assimilate in organism expressly brawn woof. It is a problem if pollutant is a radioactive 137Cs. We made experiments to sorption a 2M CsF solution on some Latvian clays which mainly contain hydro micas (cesium content after good elute of clays are in table). We establish, that clay treated with 25 % sulfuric acid adsorb cesium two times more that waste clay. Hereto unstuck elute Cs from clays. (author)

  3. Overview of radioisotope production and utilization

    International Nuclear Information System (INIS)

    Radioisotopes are in widespread and increasing daily use throughout the world. Applications include medical diagnosis, treatment of cancer, sterilization of medical disposables, the perservation of food, and the hygienization of waste products. The unique production capabilities of Canadian research reactors and CANDU electrical generating stations have enabled Atomic Energy of Canada Limited to make an important contribution to the growth of this industry. The paper describes the production, processing, transportation and applications of the major radioisotopes in use today. The equipment required for the efficient use of these radioisotopes is described and the potential for growth is discussed

  4. Abstracts of the second conference on radioisotopes and their applications

    International Nuclear Information System (INIS)

    The Second Uzbekistan Conference on radioisotopes and their applications was held on 3-5 October, 2000 in Tashkent, Uzbekistan. The specialists discussed various aspects of modern problems of radiochemistry, radioisotope production, technology of radioisotopes and compounds, activations analysis applications, radionuclides, radioimmunoassays, application of radioisotopes in industry, medicine, biology and agriculture. More than 80 talks were presented in the meeting. (A.A.D.)

  5. Abstracts of the third conference on radioisotopes and their applications

    International Nuclear Information System (INIS)

    The Third Uzbekistan Conference on radioisotopes and their applications was held on 8-10 October, 2002 in Tashkent, Uzbekistan. The specialists discussed various aspects of modern problems of radiochemistry, radioisotope production, technology of radioisotopes and compounds, activations analysis applications, radionuclides, radioimmunoassays, application of radioisotopes in industry, medicine, biology and agriculture. More than 80 talks were presented in the meeting

  6. Hanford Isotope Project strategic business analysis Cesium-137 (Cs-137)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The purpose of this business analysis is to address the beneficial reuse of Cesium 137 (Cs-137) in order to utilize a valuable national asset and possibly save millions of tax dollars. Food irradiation is the front runner application along with other uses. This business analysis supports the objectives of the Department of Energy National Isotope Strategy distributed in August 1994 which describes the DOE plans for the production and distribution of isotope products and services. As part of the Department`s mission as stated in that document. ``The Department of Energy will also continue to produce and distribute other radioisotopes and enriched stable isotopes for medical diagnostics and therapeutics, industrial, agricultural, and other useful applications on a businesslike basis. This is consistent with the goals and objectives of the National Performance Review. The Department will endeavor to look at opportunities for private sector to co-fund or invest in new ventures. Also, the Department will seek to divest from ventures that can more profitably or reliably be operated by the private sector.``

  7. Hanford Isotope Project strategic business analysis Cesium-137 (Cs-137)

    International Nuclear Information System (INIS)

    The purpose of this business analysis is to address the beneficial reuse of Cesium 137 (Cs-137) in order to utilize a valuable national asset and possibly save millions of tax dollars. Food irradiation is the front runner application along with other uses. This business analysis supports the objectives of the Department of Energy National Isotope Strategy distributed in August 1994 which describes the DOE plans for the production and distribution of isotope products and services. As part of the Department's mission as stated in that document. ''The Department of Energy will also continue to produce and distribute other radioisotopes and enriched stable isotopes for medical diagnostics and therapeutics, industrial, agricultural, and other useful applications on a businesslike basis. This is consistent with the goals and objectives of the National Performance Review. The Department will endeavor to look at opportunities for private sector to co-fund or invest in new ventures. Also, the Department will seek to divest from ventures that can more profitably or reliably be operated by the private sector.''

  8. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1986

    Energy Technology Data Exchange (ETDEWEB)

    Lamar, D.A.

    1987-10-01

    This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1)isotope suppliers, facility contact, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfers for fiscal year 1986.

  9. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1984

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A.

    1985-08-01

    This edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, Department of Energy (DOE). This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1) isotope suppliers, facility contacts, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfers - FY 1984.

  10. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1987

    Energy Technology Data Exchange (ETDEWEB)

    Lamar, D.A.; Van Houten, N.C.

    1988-08-01

    This edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, US Department of Energy (DOE). This document describes radioisotope distribution from DOE facilities to private firms, including foreign and other DOE facilities. The information is divided into five sections: 1) isotope suppliers, facility contact, and isotopes or services supplied; 2) customers, suppliers, and isotopes purchased; 3) isotopes purchased cross- referenced with customer numbers; 4) geographic locations of radioisotope customers; and 5) radioisotope sales and transfers for fiscal year 1987.

  11. Radioisotopes: problems of responsibility arising from medicine

    International Nuclear Information System (INIS)

    Radioisotopes have brought about great progress in the battle against illnesses of mainly tumoral origin, whether in diagnosis (nuclear medicine) or in treatment (medical radiotherapy). They are important enough therefore to warrant investigation. Such a study is attempted here, with special emphasis, at a time when medical responsibility proceedings are being taken more and more often on the medicolegal problems arising from their medical use. It is hoped that this study on medical responsibility in the use of radioisotopes will have shown: that the use of radioisotopes for either diagnosis or therapy constitutes a major banch of medicine; that this importance implies an awareness by the practitioner of a vast responsibility, especially in law where legislation to ensure protection as strict as in the field of ionizing radiations is lacking. The civil responsibility of doctors who use radioisotopes remains to be defined, since for want of adequate jurisprudence we are reduced to hypotheses based on general principles

  12. Radioisotope Power Systems Technology Development Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Radioisotope Power Systems (RPS) is a multicenter, multiagency (with the Department of Energy (DOE)) program whose purpose is to manage the Science Mission...

  13. Studies on application of radiation and radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Rok; Lee, Ji Bok; Lee, Yeong Iil; Jin, Joon Ha; Beon, Myeong Uh; Park, Kyeong Bae; Han, Heon Soo; Jeong, Yong Sam; Uh, Jong Seop; Kang, Kyeong Cheol; Cho, Han Ok; Song, Hui Seop; Yoon, Byeong Mok; Jeon, Byeong Jin; Park, Hong Sik; Kim, Jae Seong; Jeong, Un Soo; Baek, Sam Tae; Cho, Seong Won; Jeon, Yeong Keon; Kim, Joon Yeon; Kwon, Joong Ho; Kim, Ki Yeop; Yang, Jae Seung; No, Yeong Chang; Lee, Yeong Keun; Shin, Byeong Cheol; Park, Sang Joon; Hong, Kwang Pyo; Cho, Seung Yeon; Kang, Iil Joon; Cho, Seong Ki; Jeong, Yeong Joo; Park, Chun Deuk; Lee, Yeong Koo; Seo, Chun Ha; Han, Kwang Hui; Shin, Hyeon Young; Kim, Jong Kuk; Park, Soon Chul; Shin, In Cheol; Lee, Sang Jae; Lee, Ki Un; Lim, Yong Taek; Park, Eung Uh; Kim, Dong Soo; Jeon, Sang Soo [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-05-01

    With the completion of construction of KMRR, the facility and technology of radiation application will be greatly improved. This study was performed as follows; (1) Studies on the production and application of radioisotopes. (2) The development of radiation processing technology. (3) The application of Irradiation techniques for food preservation and process improvement. (4) Studies on the radiation application for the development of genetic resources (5) Development of the radioisotope (RI) production facilities for Korea Multipurpose Research Reactor (KMRR).

  14. Studies on application of radiation and radioisotopes

    International Nuclear Information System (INIS)

    With the completion of construction of KMRR, the facility and technology of radiation application will be greatly improved. This study was performed as follows; (1) Studies on the production and application of radioisotopes. (2) The development of radiation processing technology. (3) The application of Irradiation techniques for food preservation and process improvement. (4) Studies on the radiation application for the development of genetic resources (5) Development of the radioisotope (RI) production facilities for Korea Multipurpose Research Reactor (KMRR)

  15. Radioisotopes as Political Instruments, 1946–1953

    OpenAIRE

    Creager, Angela N. H.

    2009-01-01

    The development of nuclear «piles», soon called reactors, in the Manhattan Project provided a new technology for manufacturing radioactive isotopes. Radioisotopes, unstable variants of chemical elements that give off detectable radiation upon decay, were available in small amounts for use in research and therapy before World War II. In 1946, the U.S. government began utilizing one of its first reactors, dubbed X-10 at Oak Ridge, as a production facility for radioisotopes available for purchas...

  16. Cesium and strontium ion specific exchangers

    Energy Technology Data Exchange (ETDEWEB)

    Yates, S.

    1996-10-01

    This work is one of two parallel projects that are part of an ESP task to develop high-capacity, selective, solid extractants for cesium, strontium, and technetium from nuclear wastes. In this subtask, Pacific Northwest National Laboratory (PNNL) is collaborating with AlliedSignal, Inc. (Des Plaines, Illinois) to develop inorganic ion exchangers that are selective for strontium and cesium from alkaline high-level waste and groundwater streams.

  17. Sorption of Cesium on Latvia clays

    International Nuclear Information System (INIS)

    Cesium is like potassium - good solubility and mobile in a ground, easy assimilates in organism expressly brawn woof. It is a problem if pollutant is radioactive 137Cs. We made experiments to sorption a 2M CsF solution on some Latvian clays which mainly contain hydro micas. We establish that clay treated with 25% sulfuric acid absorb cesium two times more that waste clay. Hereto unstuck elute Cs from clays

  18. Medical Radioisotopes Production Without A Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Van der Keur, H.

    2010-05-15

    This report is answering the key question: Is it possible to ban the use of research reactors for the production of medical radioisotopes? Chapter 2 offers a summarized overview on the history of nuclear medicine. Chapter 3 gives an overview of the basic principles and understandings of nuclear medicine. The production of radioisotopes and its use in radiopharmaceuticals as a tracer for imaging particular parts of the inside of the human body (diagnosis) or as an agent in radiotherapy. Chapter 4 lists the use of popular medical radioisotopes used in nuclear imaging techniques and radiotherapy. Chapter 5 analyses reactor-based radioisotopes that can be produced by particle accelerators on commercial scale, other alternatives and the advantages of the cyclotron. Chapter 6 gives an overview of recent developments and prospects in worldwide radioisotopes production. Chapter 7 presents discussion, conclusions and recommendations, and is answering the abovementioned key question of this report: Is it possible to ban the use of a nuclear reactor for the production of radiopharmaceuticals? Is a safe and secure production of radioisotopes possible?.

  19. Artificial radioisotopes in food chains

    International Nuclear Information System (INIS)

    Use of uranium for nuclear fission involves the risk of environmental contamination by radiation during the processes of mining, concentration, peaceful and military application and storage, reprocessing and waste disposal. Three of the most dangerous radioisotopes have been followed here as they move through four different food chains. The main bottlenecks for fast and massive transfer are for 131I its rather short half life, for 137Cs the defective plant uptake from soil (and much less so also the pathway through the animal body), and for 90Sr its discrimination relative to calcium in several transport processes in the animal body, and its preference for the bone mass. Hence it is often of advantage for man to use animals as an additional food chain. Known exceptions are discussed: the reindeer and karibou living entirely on lichens during the winter and thereby acquiring for 137Cs nearly identical specific activity as plant food, and cow's milk for iodine during a short period after contamination. 15 refs.; 1 figure; 4 tabs

  20. Development of radioisotope tracer technology

    International Nuclear Information System (INIS)

    The purpose of this study is to develop the radioisotope tracer technology, which can be used in solving industrial and environmental problems and to build a strong tracer group to support the local industries. In relation to the tracer technology in 1999, experiments to estimate the efficiencies of a sludge digester of a waste water treatment plant and a submerged biological reactor of a dye industry were conducted. As a result, the tracer technology for optimization of facilities related to wastewater treatment has been developed and is believed to contribute to improve their operation efficiency. The quantification of the experimental result was attempted to improve the confidence of tracer technology by ECRIN program which basically uses the MCNP simulation principle. Using thin layer activation technique, wear of tappet shim was estimated. Thin layer surface of a tappet shim was irradiated by proton beam and the correlation between the measured activity loss and the amount of wear was established. The equipment was developed to adjust the energy of proton which collides with the surface of tappet. The tracer project team has participated into the tracer test for estimating the efficiency of RFCC system in SK cooperation. From the experiment the tracer team has obtained the primary elements to be considered for judging the efficiency of RFCC unit. By developing the tracer techniques to test huge industrial units like RFCC, the tracer team will be able to support the local industries that require technical services to solve any urgent trouble. (author)

  1. Development of radioisotope tracer technology

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Joon Ha; Lee, Myun Joo; Jung, Sung Hee; Park, Soon Chul; Lim, Dong Soon; Kim, Jae Ho; Lee, Jae Choon; Lee, Doo Sung; Cho, Yong Suk; Shin, Sung Kuan

    2000-04-01

    The purpose of this study is to develop the radioisotope tracer technology, which can be used in solving industrial and environmental problems and to build a strong tracer group to support the local industries. In relation to the tracer technology in 1999, experiments to estimate the efficiencies of a sludge digester of a waste water treatment plant and a submerged biological reactor of a dye industry were conducted. As a result, the tracer technology for optimization of facilities related to wastewater treatment has been developed and is believed to contribute to improve their operation efficiency. The quantification of the experimental result was attempted to improve the confidence of tracer technology by ECRIN program which basically uses the MCNP simulation principle. Using thin layer activation technique, wear of tappet shim was estimated. Thin layer surface of a tappet shim was irradiated by proton beam and the correlation between the measured activity loss and the amount of wear was established. The equipment was developed to adjust the energy of proton which collides with the surface of tappet. The tracer project team has participated into the tracer test for estimating the efficiency of RFCC system in SK cooperation. From the experiment the tracer team has obtained the primary elements to be considered for judging the efficiency of RFCC unit. By developing the tracer techniques to test huge industrial units like RFCC, the tracer team will be able to support the local industries that require technical services to solve any urgent trouble. (author)

  2. Removal of cesium from wastewater: A cesium-specific ion exchange resin

    International Nuclear Information System (INIS)

    Researchers at the Savannah River Laboratory (SRL) have applied for a patent for an ion exchange resin that will remove cesium from water. Radioactive cesium-137 is a fission product of nuclear reactor operations. Cesium may enter the water of spent fuel holding basins through defects in fuel cladding. Control of cesium in these basins is desirable to keep personnel exposure to a minimum. Cesium is also present in the waste from reprocessing of defense nuclear reactor fuel. Research has been underway at SRL for over a decade to improve management of high-level reprocessing waste. The current technology separates the waste into soluble and insoluble components. Radioactive constituents are removed from the soluble component stream and combined with the insoluble components, which are then converted to a glass for long-term storage. Cesium is the most radioactive constituent of the soluble components stream. The SRL resin is a resorcinol-formaldehyde condensation polymer highly specific for cesium and is about 10 times more effective in removal of cesium than other ion exchange resins evaluated for use in processing defense nuclear waste. Tests have been run at SRL using both simulated and actual waste streams

  3. Risk assessment of radioisotope contamination for aquatic living resources in and around Japan

    Science.gov (United States)

    Okamura, Hiroshi; Ikeda, Shiro; Morita, Takami; Eguchi, Shinto

    2016-01-01

    Food contamination caused by radioisotopes released from the Fukushima Dai-ichi nuclear power plant is of great public concern. The contamination risk for food items should be estimated depending on the characteristics and geographic environments of each item. However, evaluating current and future risk for food items is generally difficult because of small sample sizes, high detection limits, and insufficient survey periods. We evaluated the risk for aquatic food items exceeding a threshold of the radioactive cesium in each species and location using a statistical model. Here we show that the overall contamination risk for aquatic food items is very low. Some freshwater biota, however, are still highly contaminated, particularly in Fukushima. Highly contaminated fish generally tend to have large body size and high trophic levels. PMID:26929347

  4. Radioisotope Production for Medical and Physics Applications

    Science.gov (United States)

    Mausner, Leonard

    2012-10-01

    Radioisotopes are critical to the science and technology base of the US. Discoveries and applications made as a result of the availability of radioisotopes span widely from medicine, biology, physics, chemistry and homeland security. The clinical use of radioisotopes for medical diagnosis is the largest sector of use, with about 16 million procedures a year in the US. The use of ^99Mo/^99mTc generator and ^18F make up the majority, but ^201Tl, ^123I, ^111In, and ^67Ga are also used routinely to perform imaging of organ function. Application of radioisotopes for therapy is dominated by use of ^131I for thyroid malignancies, ^90Y for some solid tumors, and ^89Sr for bone cancer, but production of several more exotic species such as ^225Ac and ^211At are of significant current research interest. In physics ^225Ra is of interest for CP violation studies, and the actinides ^242Am, ^249Bk, and ^254Es are needed as targets for experiments to create superheavy elements. Large amounts of ^252Cf are needed as a fission source for the CARIBU experiment at ANL. The process of radioisotope production is multidisciplinary. Nuclear physics input based on nuclear reaction excitation function data is needed to choose an optimum target/projectile in order to maximize desired isotope production and minimize unwanted byproducts. Mechanical engineering is needed to address issues of target heating, induced mechanical stress and material compatibility of target and claddings. Radiochemists are involved as well since chemical separation to purify the desired final radioisotope product from the bulk target and impurities is also usually necessary. Most neutron rich species are produced at a few government and university reactors. Other radioisotopes are produced in cyclotrons in the commercial sector, university/hospital based facilities, and larger devices at the DOE labs. The landscape of US facilities, the techniques involved, and current supply challenges will be reviewed.

  5. Diffusion of Implanted Radioisotopes in Solids

    CERN Multimedia

    2002-01-01

    Implantation of radioisotopes into metal and semiconductor samples is performed. The implanted isotope or its decay-product should have a half-life long enough for radiotracer diffusion experiments. Such radioisotopes are utilized to investigate basic diffusion properties in semiconductors and metals and to improve our understanding of the atomic mechanisms of diffusion. For suitably chosen systems the combination of on-line production and clean implantation of radioisotopes at the ISOLDE facility opens new possibilities for diffusion studies in solids. \\\\ \\\\ The investigations are concentrated on diffusion studies of $^{195}$Au in amorphous materials. The isotope $^{195}$Au was obtained from the mass 195 of the mercury beam. $^{195}$Hg decays into $^{195}$Au which is a very convenient isotope for diffusion experiments. \\\\ \\\\ It was found that $^{195}$Au is a slow diffusor in amorphous Co-Zr alloys, whereas Co is a fast diffusor in the same matrix. The ``asymmetry'' in the diffusion behaviour is of considerab...

  6. Radioactive cesium in Finnish mushrooms

    International Nuclear Information System (INIS)

    Surveillance of radioactive cesium in Finnish mushrooms was started in 1986 at STUK. Results of the surveillance programs carried out in Lapland and other parts of Finland are given in this report. More than 2000 samples of edible mushrooms have been analysed during 1986-2008. The 137Cs detected in the mushrooms mainly originates from the 137Cs deposition due to the accident at the Chernobyl nuclear power plant in 1986. The 137Cs concentrations of mushrooms in the end of 1970s and in the beginning of 1980s varied from some ten to two hundred becquerels per kilogram originating from the nuclear weapon test period. The uneven division of the Chernobyl fallout is seen in the areal variation of 137Cs concentrations of mushrooms, the 137Cs concentrations being about tenfold in the areas with the highest deposition compared to those where the deposition was lowest. After the Chernobyl accident the maximum values in the 137Cs concentrations were reached during 1987-88 among most species of mushrooms. The 137Cs concentrations have decreased slowly, being in 2008 about 40 per cent of the maximum values. The 137Cs concentrations may be tenfold in the mushroom species with high uptake of cesium (Rozites caperatus, Hygrophorus camarophyllus, Lactarius trivialis) compared to the species with low uptake (Albatrellus ovinus, Leccinum sp.) picked in the same area. The 137Cs contents in certain species of commercial mushrooms in Finland still exceed the maximum permitted level, 600 Bq/kg, recommended to be respected when placing wild game, wild berries, wild mushrooms and lake fish on the market (Commission recommendation 2003/274/Euratom). Therefore, the 137Cs concentrations of mushrooms should be measured before placing them on the market in the areas of the highest 137Cs deposition, except for Albatrellus ovinus, Boletus sp. and Cantharellus cibarius. The 137Cs concentrations of common commercial mushroom species, Cantharellus tubaeformis and Craterellus cornucopioides often

  7. Commercial Superconducting Electron Linac for Radioisotope Production

    Energy Technology Data Exchange (ETDEWEB)

    Grimm, Terry Lee [Niowave, Inc., Lansing, MI (United States); Boulware, Charles H. [Niowave, Inc., Lansing, MI (United States); Hollister, Jerry L. [Niowave, Inc., Lansing, MI (United States); Jecks, Randall W. [Niowave, Inc., Lansing, MI (United States); Mamtimin, Mayir [Niowave, Inc., Lansing, MI (United States); Starovoitova, Valeriia [Niowave, Inc., Lansing, MI (United States)

    2015-08-13

    The majority of radioisotopes used in the United States today come from foreign suppliers or are generated parasitically in large government accelerators and nuclear reactors. Both of these restrictions limit the availability of radioisotopes and discourage the development and evaluation of new isotopes and for nuclear medicine, science, and industry. Numerous studies have been recommending development of dedicated accelerators for production of radioisotopes for over 20 years (Institute of Medicine, 1995; Reba, et al, 2000; National Research Council, 2007; NSAC 2009). The 2015 NSAC Long Range Plan for Isotopes again identified electron accelerators as an area for continued research and development. Recommendation 1(c) from the 2015 NSAC Isotope report specifically identifies electron accelerators for continued funding for the purpose of producing medical and industrial radioisotopes. Recognizing the pressing need for new production methods of radioisotopes, the United States Congress passed the American Medical Isotope Production Act of 2012 to develop a domestic production of 99Mo and to eliminate the use of highly enriched uranium (HEU) in the production of 99Mo. One of the advantages of high power electron linear accelerators (linacs) is they can create both proton- and neutron-rich isotopes by generating high energy x-rays that knock out protons or neutrons from stable atoms or by fission of uranium. This allows for production of isotopes not possible in nuclear reactors. Recent advances in superconducting electron linacs have decreased the size and complexity of these systems such that they are economically competitive with nuclear reactors and large, high energy accelerators. Niowave, Inc. has been developing a radioisotope production facility based on a superconducting electron linac with liquid metal converters.

  8. Plasma etching of cesium iodide

    International Nuclear Information System (INIS)

    Thick films of cesium iodide (CsI) are often used to convert x-ray images into visible light. Spreading of the visible light within CsI, however, reduces the resolution of the resulting image. Anisotropic etching of the CsI film into an array of micropixels can improve the image resolution by confining light within each pixel. The etching process uses a high-density inductively coupled plasma to pattern CsI samples held by a heated, rf-biased chuck. Fluorine-containing gases such as CF4 are found to enhance the etch rate by an order of magnitude compared to Ar+ sputtering alone. Without inert-gas ion bombardment, however, the CF4 etch becomes self-limited within a few microns of depth due to the blanket deposition of a passivation layer. Using CF4+Ar continuously removes this layer from the lateral surfaces, but the formation of a thick passivation layer on the unbombarded sidewalls of etched features is observed by scanning electron microscopy. At a substrate temperature of 220 deg. C, the minimum ion-bombardment energy for etching is Ei∼50 eV, and the rate depends on Ei1/2 above 65 eV. In dilute mixtures of CF4 and Ar, the etch rate is proportional to the gas-phase density of atomic fluorine. Above 50% CF4, however, the rate decreases, indicating the onset of net surface polymer deposition. These observations suggest that anisotropy is obtained through the ion-enhanced inhibitor etching mechanism. Etching exhibits an Arrhenius-type behavior in which the etch rate increases from ∼40 nm/min at 40 deg. C to 380 nm/min at 330 deg. C. The temperature dependence corresponds to an activation energy of 0.13±0.01 eV. This activation energy is consistent with the electronic sputtering mechanism for alkali halides

  9. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1983

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A.

    1984-08-01

    This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Idaho Operations Office; Los Alamos National Laboratory; Oak Ridge National Laboratory; Savannah River Plant; and UNC Nuclear Industries, Inc. The information is divided into five sections: isotope suppliers, facility contacts, and isotopes or services supplied; lists of customers, suppliers and isotopes purchased; list of isotopes purchased cross-referenced to customer codes; geographic locations of radioisotope customers; and radioisotope sales and transfers - FY 1983.

  10. The progress of radioisotope technology and application in China

    Institute of Scientific and Technical Information of China (English)

    Zhang Jinrong; Luo Zhifu

    2008-01-01

    The inception of radioisotope and its application in China are introduced. The research, development, produc-tion, application progress and the future development prospect of radioisotope and its products are described.

  11. Perlite for permanent confinement of cesium

    Science.gov (United States)

    Balencie, J.; Burger, D.; Rehspringer, J.-L.; Estournès, C.; Vilminot, S.; Richard-Plouet, M.; Boos, A.

    2006-06-01

    We present the potential use of expanded perlite, a metastable amorphous hydrated aluminium silicate, as a permanent medium for the long-term confinement of cesium. The method requires simply a loading by mixing an aqueous cesium nitrate solution and expanded perlite at 300 K followed by densification by sintering. The formation of pollucite, CsAlSi2O6, a naturally occurring mineral phase, upon careful heat treatment is demonstrated by X-ray diffraction. Leaching tests on the resulting glass-ceramics reveal a very low Cs departure of 0.5 mg m-2 d-1.

  12. Crystalline silicotitanates for cesium/strontium removal

    Energy Technology Data Exchange (ETDEWEB)

    Brown, N.; Miller, J.; Sherman, J.

    1996-10-01

    A new class of inorganic ion exchangers called crystalline silicotitanates (CST) has been developed that exhibits very high selectivity for cesium and strontium in the highly alkaline radioactive wastes at the Hanford Site and other DOE sites. Tests have also shown that CSTs have high selectivity for cesium in acidic and neutral solutions. The ESP is supporting an effort at Sandia National Laboratories and Texas A & M University to further develop and characterize the important chemical and physical properties that will determine the applicability of CST to radioactive waste treatment at Hanford and other DOE facilities.

  13. Microbial accumulation of uranium, radium, and cesium

    International Nuclear Information System (INIS)

    Diverse microbial species varied considerably in their ability to accumulate uranium, cesium, and radium. Mechanistic differences in uranium uptake by Saccharomyces cerevisiae and Pseudomonas aeruginosa were indicated. S. serevisiae exhibited a slow (hours) surface accumulation of uranium which was subject to environmental factors, while P. aeruginosa accumulated uranium rapidly (minutes) as dense intracellular deposits and did not appear to be affected by environmental parameters. Metabolism was not required for uranium uptake by either organism. Cesium and radium were concentrated to a considerably lesser extent than uranium by the several species tested

  14. Critical literature study on the cesium transfer feed/meat of domestic animals

    International Nuclear Information System (INIS)

    A literature study concerning the transfer of cesium from feed to meat of domestic and wild animals has been carried out regarding approx. 3200 publications of the period 1950-1979. General criteria for the influence of experimental conditions on the transfer factor have been found. The transfer factor of radioisotopes of cesium is always smaller by one order of magnitude after single ingestion than after continuous administration until an equilibrium of incorporation to excretion is attained. The transfer factor of growing animals is greater than that of adult animals where transfer factor is not a function of age. The sex of the animals has no influence on the transfer factor. This value decreases with increasing weight of the animals. From these findings average transfer factors have been derived as follows: cattle 0.03 +- 0.02; calf 0.43 +- 0.06; goat 0.20; sheep 0.11 +- 0.02; pig 0.26 +- 0.01; hen 4.5; reindeer/caribou 0.31 +- 0.07; deer 0.18 +- 0.03. These values have been extracted from the original literature and relate mainly to animals undergoing metabolic experiments at equilibrium. Only the transfer factors of deer and caribou have been evaluated from data of the radiocesium concentration in feed and in meat. (orig.)

  15. Executive strategy plan for beneficial uses program: cesium-137 sewage sludge irradiation

    International Nuclear Information System (INIS)

    Energy-efficient disinfection of sewage sludge, permitting its use as a fertilizer and soil conditioner in areas open to public access or on certain food chain crops, is possible using the process technology developed by Sandia National Laboratories under DOE and EPA joint support. This process accomplishes disinfection by gamma ray irradiation with cesium-137, a by-product isotope recovered from reprocessing of defense production waste. Disinfection with cesium-137 gamma irradiation provides an energy-efficient option for the Nation's cities to beneficially utilize sewage sludge, while at the same time conserving energy by utilizing a radioisotope, traditionally considered waste, in a beneficial manner. While the Sandia sludge irradiation technology has successfully completed its research and development phase, a major consideration remains: the introduction of a new technology into a marketplace which traditionally is skeptical of new products or process technologies until their performance is well proven. This document analyzes the factors important to market introduction of this new technology, develops options, and recommends a program strategy for transfer of the Sandia sludge irradiation technology to the marketplace by developing public awareness and acceptance, and by stimulating private sector commercialization interest

  16. Removal of Radioactive Cesium Using Prussian Blue Magnetic Nanoparticles

    Directory of Open Access Journals (Sweden)

    Sung-Chan Jang

    2014-11-01

    Full Text Available Radioactive cesium (137Cs has inevitably become a human concern due to exposure from nuclear power plants and nuclear accident releases. Many efforts have been focused on removing cesium and the remediation of the contaminated environment. In this study, we elucidated the ability of Prussian blue-coated magnetic nanoparticles to eliminate cesium from radioactive contaminated waste. Thus, the obtained Prussian blue-coated magnetic nanoparticles were then characterized and examined for their physical and radioactive cesium adsorption properties. This Prussian blue-coated magnetic nanoparticle-based cesium magnetic sorbent can offer great potential for use in in situ remediation.

  17. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1980

    International Nuclear Information System (INIS)

    The sixteenth edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research, Office of energy Research, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboraory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: (1) isotope suppliers, facility, contracts and isotopes or services supplied; (2) alphabetical list of customers, and isotopes purchased; (3) alphabetical list of isotopes cross-referenced to customer numbers; (4) geographical location of radioisotope customers; and (5) radioisotope sales and transfers-FY 1980

  18. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1979

    International Nuclear Information System (INIS)

    The fifteenth edition of the radioisotope customer list was prepared at the request of the Division of Financial Services, Office of the Assistant Secretary for Environment, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboratory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Rocky Flats Area Office; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: Isotope suppliers, facility, contracts and isotopes or services supplied; alphabetical list of customers, and isotopes purchased; alphabetical list of isotopes cross-referenced to customer numbers; geographical location of radioisotope customers; and radioisotope sales and transfers-FY 1979

  19. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1979

    Energy Technology Data Exchange (ETDEWEB)

    Burlison, J.S. (comp.)

    1980-06-01

    The fifteenth edition of the radioisotope customer list was prepared at the request of the Division of Financial Services, Office of the Assistant Secretary for Environment, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboratory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Rocky Flats Area Office; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: Isotope suppliers, facility, contracts and isotopes or services supplied; alphabetical list of customers, and isotopes purchased; alphabetical list of isotopes cross-referenced to customer numbers; geographical location of radioisotope customers; and radioisotope sales and transfers-FY 1979.

  20. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1980

    Energy Technology Data Exchange (ETDEWEB)

    Burlison, J.S. (comp.)

    1981-08-01

    The sixteenth edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research, Office of energy Research, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboraory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: (1) isotope suppliers, facility, contracts and isotopes or services supplied; (2) alphabetical list of customers, and isotopes purchased; (3) alphabetical list of isotopes cross-referenced to customer numbers; (4) geographical location of radioisotope customers; and (5) radioisotope sales and transfers-FY 1980.

  1. Development of radioisotope production in the Philippines

    Energy Technology Data Exchange (ETDEWEB)

    Cabalfin, E.G. [Philippine Nuclear Research Institute, Quezon (Philippines)

    1998-10-01

    The Philippine Nuclear Research Institute (PNRI) started its activities on radioisotope production more than three decades ago, when the Philippine Research Reactor (PRR-1) started operating at its full rated power of 1 MW. Since then, several radionuclides in different chemical forms, were routinely produced and supplied for use in nuclear medicine, industry, agriculture, research and training, until the conversion of the PRR-1 to a 3 MW TRIGA type reactor. After the criticality test of the upgraded reactor, a leak was discovered in the pool liner. With the repair of the reactor still ongoing, routine radioisotope production activities have been reduced to dispensing of imported bulk {sup 131}I. In the Philippines, radioisotopes are widely used in nuclear medicine, with {sup 131}I and {sup 99m}Tc as the major radionuclides of interest. Thus the present radioisotope production program of PNRI is directed to meet this demand. With the technical assistance of the International Atomic Energy Agency (IAEA), PNRI is setting up a new {sup 131}I production facility. The in-cell equipment have been installed and tested using both inactive and active target, obtained from BATAN, Indonesia. In order to meet the need of producing {sup 99}Mo-{sup 99m}Tc generators, based on low specific activity reactor-produced {sup 99}Mo, research and development work on the preparation of {sup 99m}Tc gel generators is ongoing. (author)

  2. Radioisotopes and food preservation against insects

    International Nuclear Information System (INIS)

    The book describes how to preserve food from harmful insects by using radioisotopes. It focusses on the impact of ionized radiation on the different stages of insect growth and on its metabolism and immunity. It also discusses the relationship between radiation doses and insect reproduction. It explains the various methods to detect the irradiated foods

  3. ILLUSTRATIONS OF RADIOISOTOPES--DEFINITIONS AND APPLICATIONS.

    Science.gov (United States)

    Atomic Energy Commission, Oak Ridge, TN. Div. of Technical Information.

    THIS PUBLICATION IS COMPOSED OF OVER 150 PAGES OF BLACK AND WHITE ILLUSTRATIONS DEALING WITH RADIOISOTOPES AND THEIR USES. THESE ILLUSTRATIONS CONSIST OF CHARTS, GRAPHS, AND PICTORIAL REPRESENTATIONS WHICH COULD BE PREPARED AS HANDOUTS, TRANSPARENCIES FOR OVERHEAD PROJECTION, OR WHICH COULD BE USED IN A NUMBER OF OTHER WAYS FOR PRESENTING SUCH…

  4. List of ERDA radioisotope customers with summary of radioisotope shipments, FY 1976

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, J.L.

    1977-03-01

    The thirteenth edition of the ERDA radioisotope customer list has been prepared at the request of the Office of Program Coordination, Office of the Assistant Administrator. The purpose of the document is to list the FY 1976 commercial radioisotope production and distribution activities of ERDA facilities at Argonne National Laboratory, Battelle, Pacific Northwest Laboratories, Brookhaven National Laboratory, Hanford Engineering Development Laboratory, Idaho Operations Office, Los Alamos Scientific Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Savannah River Laboratory, and United Nuclear Industries, Inc.

  5. List of ERDA radioisotope (customers with summary of radioisotope shipments FY 1975

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, J.L.; Gano, S.R. (comp.)

    1976-01-01

    The twelfth edition of the ERDA radioisotope customer list has been prepared at the request of the Division of Biomedical and Environmental Research. The purpose of this document is to list the FY 1975 commercial radioisotope production and distribution activities of USERDA facilities at Argonne National Laboratory, Battelle, Pacific Northwest Laboratories, Brookhaven National Laboratory, United Nuclear Inc., Idaho Operations Office, Hanford Engineering Development Laboratory, Mound Laboratory, Oak Ridge National Laboratory, and Savannah River Plant. (TFD)

  6. Cesium vapor thermionic converter anomalies arising from negative ion emission

    Science.gov (United States)

    Rasor, Ned S.

    2016-08-01

    Compelling experimental evidence is given that a longstanding limit encountered on cesium vapor thermionic energy converter performance improvement and other anomalies arise from thermionic emission of cesium negative ions. It is shown that the energy that characterizes thermionic emission of cesium negative ions is 1.38 eV and, understandably, is not the electron affinity 0.47 eV determined for the photodetachment threshold of the cesium negative ion. The experimental evidence includes measurements of collector work functions and volt-ampere characteristics in quasi-vacuum cesium vapor thermionic diodes, along with reinterpretation of the classic Taylor-Langmuir S-curve data on electron emission in cesium vapor. The quantitative effects of negative ion emission on performance in the ignited, unignited, and quasi-vacuum modes of cesium vapor thermionic converter operation are estimated.

  7. Anomalous wetting of helium on cesium

    International Nuclear Information System (INIS)

    The authors report studies of the anomalous wetting of a cesium substrate by a liquid helium film by means of the technique of third sound. A hysteretic pre-wetting transition is observed as a function of the amount of helium in the experimental cell. 10 refs., 2 figs

  8. Cesium and Strontium Separation Technologies Literature Review

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Todd; T. A. Todd; J. D. Law; R. S. Herbst

    2004-03-01

    Integral to the Advanced Fuel Cycle Initiative (AFCI) Program’s proposed closed nuclear fuel cycle, the fission products cesium and strontium in the dissolved spent nuclear fuel stream are to be separated and managed separately. A comprehensive literature survey is presented to identify cesium and strontium separation technologies that have the highest potential and to focus research and development efforts on these technologies. Removal of these high-heat-emitting fission products reduces the radiation fields in subsequent fuel cycle reprocessing streams and provides a significant short-term (100 yr) heat source reduction in the repository. This, along with separation of actinides, may provide a substantial future improvement in the amount of fuel that could be stored in a geologic repository. The survey and review of the candidate cesium and strontium separation technologies are presented herein. Because the AFCI program intends to manage cesium and strontium together, technologies that simultaneously separate both elements are of the greatest interest, relative to technologies that separate only one of the two elements.

  9. Radioisotopes in Hydrology. Proceedings of a Symposium

    International Nuclear Information System (INIS)

    The increasing emphasis on the development of water resources poses problems which are of interest to all countries, both developing and advanced, where the demand for water is continuously rising. There is no doubt that greater efforts must be made to evaluate, control and develop water resources using all scientific means available and during recent years increasing attention has been directed to the supplementation of hydrological methods with radioisotope techniques. These techniques have already been applied to a number of problems and their potential usefulness demonstrated. Radioisotopes can be used for stream discharge measurements with an accuracy as good as that obtainable with conventional methods. They are also finding increasing application in the measurement of groundwater direction and velocity, the study of suspected interconnections between different sources of water, and the investigation of mixing processes in rivers and lakes. Radioisotope techniques have been used in different parts of the world for studying the transport of silt in rivers and harbours. Present research is directed towards making these investigations on a quantitative basis which, if successful, would be of great importance in the design of hydraulic structures. The method of finding out the age of groundwater by measuring its natural tritium content can be applied to the determination of the recharge rate of groundwater bodies, so enabling a more rational use of the groundwater reserves without fear of overexploitation. Current research is aimed at using carbon-14 for groundwater-dating to extend the age measurable by tritium. A Symposium on the use of radioisotopes in hydrology was organized by the Agency and held in March 1963 in Tokyo in co-operation with the Japanese Government, for whose material and other assistance and generous hospitality the Agency wishes to record its grateful appreciation. The Symposium was attended by about 100 participants from 14 countries and 5

  10. Research and development for the application of radioisotope technology in SINR

    International Nuclear Information System (INIS)

    A brief systematic account on the research and development for the application of radioisotope technology in Shanghai Institute of Nuclear Research (SINR) is presented. It comprehensively covers the following categories: 1. Radioisotopes produced by cyclotron; 2. Radioisotope-labelled compounds; 3. Radioisotope as source of energy converter; 4. Induced-radioisotope generation as a means for elemental analysis--the activation analysis; 5. Radioisotope equipped with electronic instrument for various application; and 6. Special usage of some radioisotopes

  11. Wolf-Rayet stars and radioisotope production

    CERN Document Server

    Meynet, G

    1999-01-01

    Radioisotopes are natural clocks which can be used to estimate the age of the solar system. They also influence the shape of supernova light curves. In addition, the diffuse emission at 1.8 MeV from the decay of 26Al may provide a measure of the present day nucleosynthetic activity in the Galaxy. Therefore, even if radionuclides represent only a tiny fraction of the cosmic matter, they carry a unique piece of information. A large number of radioisotopes are produced by massive stars at the time of their supernova explosion. A more or less substantial fraction of them are also synthesized during the previous hydrostatic burning phases. These nuclides are then ejected either at the time of the supernova event, or through stellar winds during their hydrostatic burning phases. This paper focusses of the non explosive ejection of radionuclides by non-rotating or rotating Wolf-Rayet stars.

  12. The future of medical radioisotope supply

    International Nuclear Information System (INIS)

    The NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have been actively examining the causes of supply shortages of the most widely used isotope in medical diagnostic imaging, technetium-99m (99mTc), and its parent isotope molybdenum-99 (99Mo). As a result of this examination, the HLG-MR has developed a policy approach that includes principles and supporting recommendations to address the causes of these supply shortages. Six policy principles were agreed by the HLG-MR in March 2011. These are implementation of full-cost recovery and outage reserve capacity (ORC) for 99Mo production, a government role in the market, conversion to low-enriched uranium targets, international collaboration and periodic reviews of the supply chain. This article describes progress made in the implementation of the six principles and examines the projected global capacity for medical radioisotope production in the near future. (author)

  13. Development of radioisotope labeled polymeric carriers

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Jin; Jeong, Jea Min; Hwang, Hyun Jeong [Ewha Womans University, Seoul (Korea)

    2000-04-01

    This research was performed with the aim of developing polymeric radioisotope or drug carriers for obtaining efficient diagnostic therapeutic efficacy. As polymers, polyethylene oxides, polylactides, polycaprolactone were chosen to prepare the devices including micelle system, microemulsion, nanospheres. In addition, anticancer drug loaded polylactide microparticulates were fabricated as a regional chemotherapeutics for the treatment of cancer. Technetium or radioactive iodine was labeled to the polymeric carriers via ligands such as DTPA and HPP, respectively. Labeling efficiency was above 90% and stable enough up to 24 hours. Moreover, injected polymer carriers demonstrated higher blood maintenance and bone uptake than Tin colloid, a control. These results suggested that radioisotope carrying polymeric particulate are promising tools for diagnosing blood vessels or bones. Besides, anticancer drug loaded particulates demonstrated appropriate maintenance of therapeutic concentration and localization. Therefore it was proposed that this therapeutic system may be potential as a cancer therapy modality. 20 refs., 24 figs.,5 tabs. (Author)

  14. Utilization of radioisotopes in the agriculture

    International Nuclear Information System (INIS)

    Some aspects of radioisotopes utilization in the agriculture, such as, the use of gamma radiation for genetic improvement of plants; the use of C14 as tracer for comprehension of the vegetable physiology; the use of nitrogen and phosphorus isotopes in soil fertilization and plant nutrition; the use of radiation for inset sterelization and, measurement of the humidity and density of soils by neutron moderation and attenuation of gamma radiation, are presented. (M.C.K.)

  15. The efficient importation and distribution of radioisotopes. Suggestions for the most economic importation of radioisotopes

    International Nuclear Information System (INIS)

    In the course of their work in many Member States, IAEA technical assistance experts have sometimes encountered difficulties in connection with the importation of radioactive isotopes. In some countries they have been consulted as to the possible improvement of import procedures. The purpose of this publication is to summarize the experience that has been gained in the hope that it may be useful both to scientists who wish to import radioisotopes for their work and to public officials who are concerned with the administrative and financial aspects of the problem. This question is of considerable importance because many countries have only limited resources of scientific man-power and foreign exchange and hence it is essential, if these resources are to be utilized fully, that efficient importing procedures be established. Furthermore, the success or failure of technical assistance activities may depend on whether radioisotopes needed for the project can be efficiently imported. Although the data summarized in this publication are based mainly on the experience of medical users of radioisotopes, they are equally applicable to their uses in other fields such as agriculture and hydrology. This publication covers the subject of importation and distribution of radioisotopes, and concludes with a brief section on the domestic production of short-lived radioisotopes in research reactors

  16. Steps of radioisotope separation in Japan

    International Nuclear Information System (INIS)

    The Extraordinary Specialist Committee on Radioisotope Separation of the Atomic Energy Society of Japan has supported various actions on foundation, application and industrialization of the radioisotope separation over past 30 years to continue wide range of actions at a standpoint of specialist, since established in Showa 44 (1969). On June 1993 (Heisei 5), a memorial lecture meeting, as the 100th committee was held at the Institute of Physical and Chemical Research (RIKEN) of Wako-city in Saitama prefecture. At that time, a planning to publish an impressive memorial issue, to prepare orbits and episodes of actions, painful stories and fault examples of developments, and so forth like novels and to use for a future foundation, was determined. For its writing principle, it was settled to the base not to use mathematical equation as possible, to collect the essence like a tale, to collect actual and historical reports, and so on. And, for its writing content, it was determined to report on actual, painful and fault experiences in research and development, on data, topics and human relation, and on what to be remained for references. This book can be used not only for data collected on traces from fundamental to applied studies, technical development for industrialization, and so forth on radioisotope concentration, but also for a knowledge bag to give some hints to a man aiming to overcome a new problem. (G.K.)

  17. Quantitation of renal function using radioisotopic techniques.

    Science.gov (United States)

    O'Malley, J P; Ziessman, H A

    1993-03-01

    Radioisotopic methods are practical for clinical use because they do not require continuous intravenous infusion or urine collection. This obviously is of great advantage in infants and small children, in whom accurate urine collection is difficult, but the techniques apply to adults as well. The ability to determine individual kidney function is a major benefit. Accuracies of the radioisotopic techniques vary but generally are within clinically acceptable ranges. The need for accuracy and reproducibility can be balanced with the desire for speed and convenience when choosing among the different techniques. Methods that use plasma sampling provide greater accuracy and are recommended in cases of severe dysfunction, whereas methods such as Gates' camera method, which eliminates plasma samples, can be completed in minutes. Radioisotopic techniques are most useful in the ranges of mild to moderately decreased function, in which serum creatinine concentration is nondiagnostic, and although they are much less accurate at markedly low renal function levels, so is 24-hour creatinine clearance. In conclusion, radiopharmaceutical agents offer a wide array of possible techniques for simple, accurate, and noninvasive measurement of global as well as individual GFR and ERPF. PMID:8462269

  18. Medical Radioisotope Scanning. Proceedings of a Seminar

    International Nuclear Information System (INIS)

    Of the many and varied uses of radioactive isotopes which have been developed in the past twenty years, their applications in medicine are among the most important. All over the world medical scientists have added radioisotopes to their armament in clinical research, diagnosis and radiotherapy. It is significant that the first scientific meeting organized by the International Atomic Energy Agency was devoted to a medical subject. It is not less significant as a symbol of the close co-operation which has been established between the Agency and other agencies of the United Nations family, that this first seminar was a joint undertaking with the World Health Organization. The determination of the distribution of a radioisotope within the human body - radioisotope scanning - is a technique which has made very rapid progress in the last few years in various medical centres throughout the world, and the necessity of providing an opportunity for an organized exchange of results, experience and opinions was clearly recognised. The value of such an exchange is demonstrated by the extensive discussions which took place and which are recorded in this volume, together with the original papers presented by those who have made such noteworthy contributions to progress in this field.

  19. Separation of radioisotopes from fuel reprocessing waste

    International Nuclear Information System (INIS)

    The technology development of radioisotope production from fuel reprocessing high level wastes in Radioisotope Production Division is described. To develop the separation method for partitioning as the waste management and production of useful radioisotopes, the separation of 90Sr, 137Cs and rare earth elements by solvent extraction and ion-exchange has been mainly studied. Ion-exchange resin and HDEHP as the extracting agents were irradiated with a 60Co radiation source to examine their radiation resistances; Both are satisfactory in this respect. Strontium-90 and 137Cs could be separated in 99% purity from a 10l waste solution (about 2 Ci) by ion-exchange using nitric acid as the only eluant. A system of solvent extraction and ion-exchange to treat large volume of the waste was constructed in trial, and its cold test was carried out. The results were satisfactory, with a few points for further improvement. The scheme as it is can be scaled up for an experiment with about 1 KCi of the waste. (auth.)

  20. NEW DIRECTIONS IN RADIOISOTOPE SPECTRUM IDENTIFICATION

    Energy Technology Data Exchange (ETDEWEB)

    Salaymeh, S.; Jeffcoat, R.

    2010-06-17

    Recent studies have found the performance of commercial handheld detectors with automatic RIID software to be less than acceptable. Previously, we have explored approaches rooted in speech processing such as cepstral features and information-theoretic measures. Scientific advances are often made when researchers identify mathematical or physical commonalities between different fields and are able to apply mature techniques or algorithms developed in one field to another field which shares some of the same challenges. The authors of this paper have identified similarities between the unsolved problems faced in gamma-spectroscopy for automated radioisotope identification and the challenges of the much larger body of research in speech processing. Our research has led to a probabilistic framework for describing and solving radioisotope identification problems. Many heuristic approaches to classification in current use, including for radioisotope classification, make implicit probabilistic assumptions which are not clear to the users and, if stated explicitly, might not be considered desirable. Our framework leads to a classification approach with demonstrable improvements using standard feature sets on proof-of-concept simulated and field-collected data.

  1. Lanthanide doped strontium-barium cesium halide scintillators

    Energy Technology Data Exchange (ETDEWEB)

    Bizarri, Gregory; Bourret-Courchesne, Edith; Derenzo, Stephen E.; Borade, Ramesh B.; Gundiah, Gautam; Yan, Zewu; Hanrahan, Stephen M.; Chaudhry, Anurag; Canning, Andrew

    2015-06-09

    The present invention provides for a composition comprising an inorganic scintillator comprising an optionally lanthanide-doped strontium-barium, optionally cesium, halide, useful for detecting nuclear material.

  2. Surface interactions of cesium and boric acid with stainless steel

    International Nuclear Information System (INIS)

    In this report, the effects of cesium hydroxide and boric acid on oxidized stainless steel surfaces at high temperatures and near one atmosphere of pressure are investigated. This is the first experimental investigation of this chemical system. The experimental investigations were performed using a mass spectrometer and a mass electrobalance. Surfaces from the different experiments were examined using a scanning electron microscope to identify the presence of deposited species, and electron spectroscopy for chemical analysis to identify the species deposited on the surface. A better understanding of the equilibrium thermodynamics, the kinetics of the steam-accelerated volatilizations, and the release kinetics are gained by these experiments. The release rate is characterized by bulk vaporization/gas-phase mass transfer data. The analysis couples vaporization, deposition, and desorption of the compounds formed by cesium hydroxide and boric acid under conditions similar to what is expected during certain nuclear reactor accidents. This study shows that cesium deposits on an oxidized stainless steel surface at temperatures between 1000 and 1200 Kelvin. Cesium also deposits on stainless steel surfaces coated with boric oxide in the same temperature ranges. The mechanism for cesium deposition onto the oxide layer was found to involve the chemical reaction between cesium and chromate. Some revaporization in the cesium hydroxide-boric acid system was observed. It has been found that under the conditions given, boric acid will react with cesium hydroxide to form cesium metaborate. A model is proposed for this chemical reaction

  3. Distribution and retention of cesium in Swedish boreal forest ecosystems

    International Nuclear Information System (INIS)

    The retention and distribution of cesium in forest environments are being studied at three locations in Sweden. The main part of the cesium found in the soil was recovered in horizons rich in organic matter. The cesium was retained in the soil organic matter in a more or less extractable form. As different soil types have a different distribution pattern of organic matter the distribution of cesium will depend on the forest soil type. The clay content in Swedish forest soils is in general low which will mitigate the retention of cesium in the soil mineral horizons. The cesium present in the tree was considered to be an effect of assimilation by the tissues in the canopy as well as by the roots. The redistribution of cesium within the trees was extensive which was considered to be an effect of a high mobility of cesium in the close system of a forest environment. The cesium will remain in the forest environment for a considerable time but can be removed by forest practice, by leaching out of the soil profile or by the radioactive decay. (au)

  4. Sorption of cesium in intact rock

    Energy Technology Data Exchange (ETDEWEB)

    Puukko, E. [Univ. of Helsinki, Dept. of Chemistry (Finland)

    2014-04-15

    The mass distribution coefficient K{sub d} is used in performance assessment (PA) to describe sorption of a radionuclide on rock. The R{sub d} is determined using crushed rock which causes uncertainty in converting the R{sub d} values to K{sub d} values for intact rock. This work describes a method to determine the equilibrium of sorption on intact rock. The rock types of the planned Olkiluoto waste disposal site were T-series mica gneiss (T-MGN), T-series tonalite granodiorite granite gneiss (T-TGG), P-series tonalite granodiorite granite gneiss (P-TGG) and pegmatitic granite (PGR). These rocks contain different amount of biotite which is the main sorbing mineral. The sorption of cesium on intact rock slices was studied by applying an electrical field to speed up migration of cesium into the rock. Cesium is in the solution as a noncomplex cation Cs{sup +} and it is sorbed by ion exchange. The tracer used in the experiments was {sup 134}Cs. The experimental sorption on the intact rock is compared with values calculated using the in house cation exchange sorption model (HYRL model) in PHREEQC program. The observed sorption on T-MGN and T-TGG rocks was close to the calculated values. Two PGR samples were from a depth of 70 m and three samples were from a depth of 150 m. Cesium sorbed more than predicted on the two 70 m PGR samples. The sorption of Cs on the three 150 m PGR samples was small which was consistent with the calculations. The pegmatitic granite PGR has the smallest content of biotite of the four rock types. In the case of P-TGG rock the observed values of sorption were only half of the calculated values. Two kind of slices were cut from P-TGG drill core. The slices were against and to the direction of the foliation of the biotite rims. The sorption of cesium on P-TGG rock was same in both cases. The results indicated that there was no effect of the directions of the electric field and the foliation of biotite in the P-TGG rock. (orig.)

  5. A report on the extent of radioisotope usage in Malaysia

    International Nuclear Information System (INIS)

    A market survey was carried out to study the extent of radioisotope usage in Malaysia. From the survey, the radioisotopes and their activities/quantities that are used in Industry, Medicine and Research were identified. The radioisotopes that are frequently needed or routinely used were also determined and this formed the basis of the recommendations put forward in this report. It is proposed that PUSPATI adopt the concept of a Distribution Centre in order to provide a service to the Malaysian community. (author)

  6. Radioisotope techniques for problem-solving on refineries

    International Nuclear Information System (INIS)

    Increasingly, refineries worldwide are recognizing the value of radioisotope technology in studying the operation of on-line plant. Using case studies, this paper illustrates the versatility of radioisotope techniques in a wide range of investigations: the density-profiling of distillation columns; the investigation of leaks on feed/effluent exchangers; on-line flowrate measurement; underground leakage detection. The economic benefits deriving from radioisotope applications are indicated

  7. SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION-EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATIONS-12092

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L.; Martin, K.; Hobbs, D.

    2012-01-03

    Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate and crystalline silicotitanate laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both strontium-85 and cesium-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor for strontium-85 with monosodium titanate impregnated filter membrane cartridges measured 26, representing 96% strontium-85 removal efficiency. On the other hand, the strontium-85 instantaneous decontamination factor with co-sintered active monosodium titanate cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the monosodium titanate impregnated membrane cartridges and crystalline silicotitanate impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active monosodium titanate cartridges and co-sintered active crystalline silicotitanate cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of cesium-137 with co-sintered crystalline silicotitanate cartridges. Tests results with crystalline silicotitanate impregnated membrane cartridges for cesium-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating monosodium titanate and crystalline silicotitanate sorbents into membranes represent a promising method for the semicontinuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.

  8. Vitrified chemically bonded phosphate ceramics for immobilization of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Wagh, Arun S.

    2016-04-05

    A method of immobilizing a radioisotope and vitrified chemically bonded phosphate ceramic (CBPC) articles formed by the method are described. The method comprises combining a radioisotope-containing material, MgO, a source of phosphate, and optionally, a reducing agent, in water at a temperature of less than 100.degree. C. to form a slurry; curing the slurry to form a solid intermediate CBPC article comprising the radioisotope therefrom; comminuting the intermediate CBPC article, mixing the comminuted material with glass frits, and heating the mixture at a temperature in the range of about 900 to about 1500.degree. C. to form a vitrified CBPC article comprising the radioisotope immobilized therein.

  9. Technical and economical availability of radioisotopes production in Brazil

    International Nuclear Information System (INIS)

    The technical and economical availability of radioisotopes production in Brazil by a low power research reactor, are done. The importance of radioisotope utilization and controled radiations, in areas such as medicine, industry and cost evaluation for the production in nuclear reactors. In the cost evaluation of a radioisotope production reactor, the studies developed by the Department of Nuclear Engineering of Universidade Federal de Minas Gerais - DEN/UFMG were used. The information analysis justify the technical and economical availability and the necessity of the radioisotopes production in Brazil. (E.G.)

  10. Advanced Radiative Emitters for Radioisotope Thermophotovoltaic Power Systems Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Radioisotope Power Systems (RPS) are critical for future flagship exploration missions in space and on planetary surfaces. Small improvements in the RPS...

  11. Markets for reactor-produced non-fission radioisotopes

    International Nuclear Information System (INIS)

    Current market segments for reactor produced radioisotopes are developed and reported from a review of current literature. Specific radioisotopes studied in is report are the primarily selected from those with major medical or industrial markets, or those expected to have strongly emerging markets. Relative market sizes are indicated. Special emphasis is given to those radioisotopes that are best matched to production in high flux reactors such as the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory or the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory. A general bibliography of medical and industrial radioisotope applications, trends, and historical notes is included

  12. Efficient, Long-Lived Radioisotope Power Generator Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Radiation Monitoring Devices, Inc., (RMD) proposes to develop an alternative very long term, radioisotope power source with thermoelectric power conversion with...

  13. Development of radioisotope preparation and application technology

    International Nuclear Information System (INIS)

    The purpose of this project is to develop RI production technology utility 'HANARO' and to construct a sound infra-structure for mass production and supply to domestic users. The developed contents and results are as follows: two types of rig for irradiation in reactor core were designed and manufactured. The safety of OR rig during irradiation was identified through various test and it is used for RI production. The prepared IR rig will be used to performance tests for safety. We prepared two welders and welding jigs for production of sealed sources, and equipments for quality control of the welded materials. Production processes and apparatus Cr-51, P-32, I-125 and Sr-89, were developed. Developed results would be used for routine production and supply of radioisotopes. The automatic Tc-99m extraction apparatus was supplied to Libya under IAEA support. For approval on special form radioactive material of the developed Ir-192 source assembly and projector documents were prepared and submitted to MOST. The high dose rate Ir-192 source(diameter 1.1 mm, length 5.2 mm) for RALS and the laser welding system for its fabrication were developed. Production technologies of Ir-192 sources for destructive test and medical therapy were transferred to private company for commercial supply. The chemical immobilization method based on the self-assemble monolayer of ω-functionalized thiol and the sensing scheme based on the beta-emitter labeling method were developed for the fabrication radioimmuno-sensors. Results of this study will be applied to mass production of radioisotopes 'HANARO' and are to contribute the advance of domestic medicine and industry related to radioisotopes

  14. Recent progress in radioisotope production in Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Le Van So [Radioisotope Dept., Nuclear Research Institute, Dalat (Viet Nam)

    1998-10-01

    This is a report on the recent progress in radioisotope production in Vietnam. Using a nuclear research reactor of 500 KW with continuous operation cycles of 100 hours a month, the production of some important radioisotopes used in nuclear medicine and research was routinely carried out. More than 80 per cent of irradiation capacity of reactor for radioisotope production were exploited. The radioactivity of more than 150 Ci of {sup 131}I, {sup 99}Mo-{sup 99m}Tc, {sup 32}P, {sup 51}Cr, {sup 153}Sm, {sup 46}Sc, {sup 192}Ir was produced annually. Radiopharmaceuticals such as {sup 131}I-Hippuran and in-vivo Kits for {sup 99m}Tc labelling were also prepared routinely and regularly. More than 10 in-vivo Kits including modern radiopharmaceuticals such as HmPAO kit were supplied to hospitals in Vietnam. The research on the improvement of dry distillation technology for production of {sup 131}I was carried out. As a result obtained a new distillation apparatus made from glass was successfully put to routine use in place of expensive quartz distillation furnace. We have also continued the research programme on the development of {sup 99m}Tc generators using low power research reactors. Gel technology using Zr- and Ti- molybdate gel columns for {sup 99m}Tc generator production was developed and improved continually. Portable {sup 99m}Tc generator using Zr-({sup 99}Mo) molybdate gel column and ZISORB adsorbent column for {sup 99m}Tc concentration were developed. The ZISORB adsorbent of high adsorption capacity for {sup 99}Mo and other parent radionuclides was also studied for the development purpose of alternative technology of {sup 99m}Tc and other different radionuclide generator systems. The studies on the preparation of therapeutic radiopharmaceuticals labelling with {sup 153}Sm and {sup 131}I such as {sup 153}Sm-EDTMP, {sup 131}I-MIBG were carried out. (author)

  15. Development of radioisotope preparation and application technology

    Energy Technology Data Exchange (ETDEWEB)

    Han, Hyon Soo; Park, K. B.; Bang, H. S. [and others

    2000-04-01

    The purpose of this project is to develop RI production technology utility 'HANARO' and to construct a sound infra-structure for mass production and supply to domestic users. The developed contents and results are as follows: two types of rig for irradiation in reactor core were designed and manufactured. The safety of OR rig during irradiation was identified through various test and it is used for RI production. The prepared IR rig will be used to performance tests for safety. We prepared two welders and welding jigs for production of sealed sources, and equipments for quality control of the welded materials. Production processes and apparatus Cr-51, P-32, I-125 and Sr-89, were developed. Developed results would be used for routine production and supply of radioisotopes. The automatic Tc-99m extraction apparatus was supplied to Libya under IAEA support. For approval on special form radioactive material of the developed Ir-192 source assembly and projector documents were prepared and submitted to MOST. The high dose rate Ir-192 source(diameter 1.1 mm, length 5.2 mm) for RALS and the laser welding system for its fabrication were developed. Production technologies of Ir-192 sources for destructive test and medical therapy were transferred to private company for commercial supply. The chemical immobilization method based on the self-assemble monolayer of {omega}-functionalized thiol and the sensing scheme based on the beta-emitter labeling method were developed for the fabrication radioimmuno-sensors. Results of this study will be applied to mass production of radioisotopes 'HANARO' and are to contribute the advance of domestic medicine and industry related to radioisotopes.

  16. Miniaturized radioisotope solid state power sources

    Science.gov (United States)

    Fleurial, J.-P.; Snyder, G. J.; Patel, J.; Herman, J. A.; Caillat, T.; Nesmith, B.; Kolawa, E. A.

    2000-01-01

    Electrical power requirements for the next generation of deep space missions cover a wide range from the kilowatt to the milliwatt. Several of these missions call for the development of compact, low weight, long life, rugged power sources capable of delivering a few milliwatts up to a couple of watts while operating in harsh environments. Advanced solid state thermoelectric microdevices combined with radioisotope heat sources and energy storage devices such as capacitors are ideally suited for these applications. By making use of macroscopic film technology, microgenrators operating across relatively small temperature differences can be conceptualized for a variety of high heat flux or low heat flux heat source configurations. Moreover, by shrinking the size of the thermoelements and increasing their number to several thousands in a single structure, these devices can generate high voltages even at low power outputs that are more compatible with electronic components. Because the miniaturization of state-of-the-art thermoelectric module technology based on Bi2Te3 alloys is limited due to mechanical and manufacturing constraints, we are developing novel microdevices using integrated-circuit type fabrication processes, electrochemical deposition techniques and high thermal conductivity substrate materials. One power source concept is based on several thermoelectric microgenerator modules that are tightly integrated with a 1.1W Radioisotope Heater Unit. Such a system could deliver up to 50mW of electrical power in a small lightweight package of approximately 50 to 60g and 30cm3. An even higher degree of miniaturization and high specific power values (mW/mm3) can be obtained when considering the potential use of radioisotope materials for an alpha-voltaic or a hybrid thermoelectric/alpha-voltaic power source. Some of the technical challenges associated with these concepts are discussed in this paper. .

  17. Self-reliance politics in radioisotopes production

    International Nuclear Information System (INIS)

    Full text: The Energetic and Nuclear Research Institute (IPEN), owned by National Commission of Nuclear Energy (CNEN), is a non-profit government institution that produces on a national scale more than 18 radioisotopes and radiopharmaceuticals for nuclear medicine. These radiopharmaceuticals are used in the diagnosis and treatment of more than 1.5 million people in Brazil. This level of production was achieved through the creation of new technologies and automation solutions, because of the difficulty and cost on importation of raw materials and labeling compounds ready for use. In Brazil, only CNEN has authorization to import, manipulate and distribute radiopharmaceuticals. Therefore, the quality of those radioisotopes must comply with international specifications and regulations. Much research and 40 years of improvements has won IPEN international approval for the radiopharmaceuticals that it produces, and quality standards and specifications are today as good as in any other developed country. IPEN has even developed a few solutions in radioisotope production for others countries, such as Cuba and soon Peru. The first step towards self-production was the acquisition of a cyclotron (Cyclone-30) and the improvement of the reactor power from 2 MW to 5 MW. Many technical visits were made to radiopharmaceutical institutions around the world with the purpose of bringing self-reliance and self-development solutions to IPEN. The international radiopharmaceutical community has always contributed to this effort, and only with their help our self-development and self-reliance could be possible. IPEN has ISO 9001-2000 certification and has made efforts to improve the installations in order to achieve Good Manufacturing Practice. Every effort we make today has the goal of making radiopharmaceuticals available for therapy at the most competitive price possible for our institution. (author)

  18. Applicability of sodium alginate in decorporation therapy of strontium radioisotopes in human being

    International Nuclear Information System (INIS)

    The increasing release of fission products from nuclear weapon tests in the environment has been rising the levels of radioactive contamination of food chains caused by the fall-out of these elements. In cases of accidental exposure, human subjects could be submitted to an internal contamination, which is likely to include several radionuclides. Special concern must be given, however, to the radioactive isotopes of strontium, cesium and iodine, along with the highly radio toxic transuranium elements like cerium. It was found that sodium alginate, a polyelectrolyte commonly used in food industry and obtained from brown algae (Phaeophyceae), provides the selective suppression of absorption of radioactive strontium presented in the ingested food material with no disturbance of the electrolyte balance nor undesirable side effects, even for a long term treatment. Moreover, these patterns were maintained when alginate was associated to other decontamination additives, specially those related to the other radioisotopes mentioned above, as, in this case, losses in the effectiveness, mutual interference or adverse health effects were not detected. These conclusions ground the discussion about the present trend in the usual choice of EDTA/DTPA complex therapy rather than of alginate therapy for medical assistance of radiocontaminated patients, although they corroborate the efficiency and usefulness of alginate salts in situations related to extensive intakes of strontium radioisotopes alone or associated to other fission products. The purpose of the present work is to make a general review of the alginate therapy as well as to discuss its present and future therapeutic importance from the scientific and institutional points of view. (author)

  19. Performance tuned radioisotope thermophotovoltaic space power system

    Science.gov (United States)

    Horne, W. E.; Morgan, M. D.; Saban, S. B.

    1998-01-01

    The trend in space exploration is to use many small, low-cost, special-purpose satellites instead of the large, high-cost, multipurpose satellites used in the past. As a result of this new trend, there is a need for lightweight, efficient, and compact radioisotope fueled electrical power generators. This paper presents an improved design for a radioisotope thermophotovoltaic (RTPV) space power system in the 10 W to 20 W class which promises up to 37.6 watts at 30.1% efficiency and 25 W/kg specific power. The RTPV power system concept has been studied and compared to radioisotope thermoelectric generators (RTG) radioisotope, Stirling generators and alkali metal thermal electric conversion (AMTEC) generators (Schock, 1995). The studies indicate that RTPV has the potential to be the lightest weight, most efficient and most reliable of the three concepts. However, in spite of the efficiency and light weight, the size of the thermal radiator required to eliminate excess heat from the PV cells and the lack of actual system operational performance data are perceived as obstacles to RTPV acceptance for space applications. Between 1994 and 1997 EDTEK optimized the key converter components for an RTPV generator under Department of Energy (DOE) funding administered via subcontracts to Orbital Sciences Corporation (OSC) and EG&G Mound Applied Technologies Laboratory (Horne, 1995). The optimized components included a resonant micromesh infrared bandpass filter, low-bandgap GaSb PV cells and cell arrays. Parametric data from these components were supplied to OSC who developed and analyzed the performance of 100 W, 20 W, and 10 W RTPV generators. These designs are described in references (Schock 1994, 1995 and 1996). Since the performance of each class of supply was roughly equivalent and simply scaled with size, this paper will consider the OSC 20 W design as a baseline. The baseline 20-W RTPV design was developed by Schock, et al of OSC and has been presented elsewhere. The

  20. Medical Radioisotope Data Survey: 2002 Preliminary Results

    Energy Technology Data Exchange (ETDEWEB)

    Siciliano, Edward R.

    2004-06-23

    A limited, but accurate amount of detailed information about the radioactive isotopes used in the U.S. for medical procedures was collected from a local hospital and from a recent report on the U.S. Radiopharmaceutical Markets. These data included the total number of procedures, the specific types of procedures, the specific radioisotopes used in these procedures, and the dosage administered per procedure. The information from these sources was compiled, assessed, pruned, and then merged into a single, comprehensive and consistent set of results presented in this report. (PIET-43471-TM-197)

  1. Industrial radioisotope economics. Findings of the study group

    International Nuclear Information System (INIS)

    Within twenty years of the availability of radioisotopes in quantity the use of these as tracers has been widely applied in scientific research and in industrial process and product control. Industry spends millions of dollars on these new techniques. Since the overall attitude of industry is to favour methods that involve rapid financial returns the economic benefits must be considerable. In promoting the peaceful uses of atomic energy, the IAEA is actively interested in the international exchange of experience in all applications of radioisotopes. This has been demonstrated by a number of scientific conferences where new results of direct importance to the industrial use of radioisotopes have been presented. In 1963 the IAEA also published literature survey on radioisotope applications described in the scientific literature up to 1960, classified according to industry. However, the available scientific literature was found insufficient to determine the extent of the use of radioisotopes and the economic benefits derived from it. Therefore, further fact-finding efforts were necessary. The IAEA thus decided to carry out an International Survey on the Use of Radioisotopes in Industry. In 1962 the IAEA's highly industrialized Member States Were invited to participate in the Survey; 25 declared their willingness to do so and in due course submitted their national reports. These included information on how radioisotopes were used by industry in each country and indicated the size and form of the economic advantages, primarily in terms of savings made by industry. The findings from the Survey were discussed at a Study Group Meeting on Radioisotope Economics, held in Vienna in March 1964. Forty participants from 22 countries were nominated for this Study Group. The program of the meeting was divided in three parts: (1) experience of the International Survey on the use of radioisotopes in industry; (2) present use of radioisotopes, technical and economic aspects; (3

  2. Distillation device supplies cesium vapor at constant pressure

    Science.gov (United States)

    Basiulis, A.; Shefsiek, P. K.

    1968-01-01

    Distillation apparatus in the form of a U tube supplies small amounts of pure cesium vapor at constant pressure to a thermionic converter. The upstream leg of the U tube is connected to a vacuum pump to withdraw noncondensable impurities, the bottom portion serves as a reservoir for the liquid cesium.

  3. Extraction of radioactive cesium from ash of flammable radioactive material

    International Nuclear Information System (INIS)

    Huge amount of radioactive materials was released by the hydrogen explosion at Fukushima Daiichi Nuclear Power Plant due to the Great East Japan Earthquake on March 11, 2011. Suppression of the volume of radioactive materials stored by decontamination works is strongly required since the preparation of storage places is not easy. We are developing the technology for separation and concentration of radioactive cesium using nano-particle, Prussian blue, as a cesium adsorption material which has a high efficiency and good selectivity. We propose a method in which radioactive cesium is extracted from the ash of flammable materials into the water and the Prussian blue nano-particles are added to the water to collect cesium. The volume of radioactive wastes contaminated by cesium is expected to be cut down with these processes. (J.P.N.)

  4. A combined cesium-strontium extraction/recovery process

    International Nuclear Information System (INIS)

    A new solvent extraction process for the simultaneous extraction of cesium and strontium from acidic nitrate media is described. This process uses a solvent formulation comprised of 0.05 M di-t-butylcyclohexano-18-crown-6 (DtBuCH18C6), 0.1 M Crown 100' (a proprietary, cesium-selective derivative of dibenzo-18-crown-6), 1.2 M tributyl phosphate (TBP), and 5% (v/v) lauryl nitrile in an isoparaffinic hydrocarbon diluent. Distribution ratios for cesium and strontium from 4 M nitric acid are 4.13 and 3.46, respectively. A benchtop batch countercurrent extraction experiment indicates that >98% of the cesium and strontium initially present in the feed solution can be removed in only four extraction stages. Through proper choice of extraction and strip conditions, extracted cesium and strontium can be recovered either together or individually

  5. Plutonium and Cesium Colloid Mediated Transport

    Science.gov (United States)

    Boukhalfa, H.; Dittrich, T.; Reimus, P. W.; Ware, D.; Erdmann, B.; Wasserman, N. L.; Abdel-Fattah, A. I.

    2013-12-01

    Plutonium and cesium have been released to the environment at many different locations worldwide and are present in spent fuel at significant levels. Accurate understanding of the mechanisms that control their fate and transport in the environment is important for the management of contaminated sites, for forensic applications, and for the development of robust repositories for the disposal of spent nuclear fuel and nuclear waste. Plutonium, which can be present in the environment in multiple oxidations states and various chemical forms including amorphous oxy(hydr)oxide phases, adsorbs/adheres very strongly to geological materials and is usually immobile in all its chemical forms. However, when associated with natural colloids, it has the potential to migrate significant distances from its point of release. Like plutonium, cesium is not very mobile and tends to remain adhered to geological materials near its release point, although its transport can be enhanced by natural colloids. However, the reactivity of plutonium and cesium are very different, so their colloid-mediated transport might be significantly different in subsurface environments. In this study, we performed controlled experiments in two identically-prepared columns; one dedicated to Pu and natural colloid transport experiments, and the other to Cs and colloid experiments. Multiple flow-through experiments were conducted in each column, with the effluent solutions being collected and re-injected into the same column two times to examine the persistence and scaling behavior of the natural colloids, Pu and Cs. The data show that that a significant fraction of colloids were retained in the first elution through each column, but the eluted colloids collected from the first run transported almost conservatively in subsequent runs. Plutonium transport tracked natural colloids in the first run but deviated from the transport of natural colloids in the second and third runs. Cesium transport tracked natural

  6. Radioisotopes in the training of medical students

    International Nuclear Information System (INIS)

    The importance of the discovery of radioisotopes for the progress of science in general and that of biochemistry and physiology in particular has led us to provide experimental practice which enables medical students to become effectively acquainted with the properties and methods of use of radioisotopes, the measurement of their activity, and the possible risks involved in handling them. We have included in the exercises in quantitative determination for third-year medical students (the last pre-clinical year), practice in calibrating micropipettes using a 24Na solution prepared in the TRICO Centre's reactor by irradiating sodium carbonate with slow neutrons. The students make several GM-counter measurements of the activity of the stock solution over a period of time and of the activity of five samples taken with two different micropipettes. They then calculate, by measuring the decay in activity, the half-life of the isotope and relate their measurements to a reference time. In this way they calculate the volume of their micropipettes and the accuracy of the measurements. By means of a statistical analysis they compare the averages for the two pipettes and the accuracy of two operators. (author)

  7. Preparing for Harvesting Radioisotopes from FRIB

    Energy Technology Data Exchange (ETDEWEB)

    Peaslee, Graham F. [Hope College, Holland, MI (United States); Lapi, Suzanne E. [Washington Univ., St. Louis, MO (United States)

    2015-02-02

    The Facility for Rare Isotope Beams (FRIB) is the next generation accelerator facility under construction at Michigan State University. FRIB will produce a wide variety of rare isotopes by a process called projectile fragmentation for a broad range of new experiments when it comes online in 2020. The accelerated rare isotope beams produced in this facility will be more intense than any current facility in the world - in many cases by more than 1000-fold. These beams will be available to the primary users of FRIB in order to do exciting new fundamental research with accelerated heavy ions. In the standard mode of operation, this will mean one radioisotope will be selected at a time for the user. However, the projectile fragmentation process also yields hundreds of other radioisotopes at these bombarding energies, and many of these rare isotopes are long-lived and could have practical applications in medicine, national security or the environment. This project developed new methods to collect these long-lived rare isotopes that are by-products of the standard FRIB operation. These isotopes are important to many areas of research, thus this project will have a broad impact in several scientific areas including medicine, environment and homeland security.

  8. Safety test of transport packages for radioisotopes

    International Nuclear Information System (INIS)

    The Division of Radioisotope Production, JAERI, has tested safety of type B(M), A and L packages according to the regulations of RI transportation. The type B(M) package weighing about 1800 kg. Used for transport of 192Ir(6540 Ci) and 32P(188 Ci) from reactors to the Radioisotope Production Laboratory, consists of a cylindrical plywood receptacle, aluminum honeycomb shock absorbers, steel framework and a 150 mm wall thickness drawer type lead container. Safety tests for type B(M) included 9 m high free drops in four postures, vertical, horizontal, corner and reverse, 1 m free drops on to an iron rod with in two postures, vertical and horizontal (the latter for punch test) and thermal test. The maximum acceleration in the punch test showed 735 G and in the 9 m drop test 2590 G. For thermal test of the whole package, a large muffle furnace was used. When the temperature of furnace reached 9200C, the package was inserted into it and heated for 30 min. During the test surface temperature of the lead container rose only by 19.10C. In 12.2 m free drop of type A and L package as safety test, 5 ml vials containing simulation RI solution retained their integrity without breakage. (author)

  9. Rhenium Radioisotopes for Therapeutic Radiopharmaceutical Development

    Energy Technology Data Exchange (ETDEWEB)

    Beets, A.L.; Knapp, F.F., Jr.; Kropp, J.; Lin, W.-Y.; Pinkert, J.; Wang, S.-Y.

    1999-01-18

    The availability of therapeutic radioisotopes at reasonable costs is important for applications in nuclear medicine, oncology and interventional cardiology, Rhenium-186 (Re-186) and rhenium-1 88 (Re-188) are two reactor-produced radioisotope which are attractive for a variety of therapeutic applications, Rhenium-186 has a half-life of 90 hours and decays with emission of a &particle with a maximum energy of 1.08 MeV and a 135 keV (9Yo) gamma which permits imaging. In contrast, Re- 188 has a much shorter half-life of 16.9 hours and emits a p-particle with a much higher energy of 2.12 MeV (Em=) and a 155 keV gamma photon (15Yo) for imaging. While Re-186 is unavailable from a generator system and must be directly produced in a nuclear reactor, Re-188 can also be directly produced in a reactor with high specific activity, but is more conveniently and cost-effectively available as carrier-free sodium perrhenate by saline elution of the alumina-based tungsten-188 (W1 88)/Re-l 88 generator system [1-2]. Since a comprehensive overviewofRe-186 and Re-188 therapeutic agents is beyond the scope of this &tended Abstrac4 the goal is to provide key examples of various agents currently in clinical use and those which are being developed for important clinical applications.

  10. Safe Handling of Radioisotopes. Medical Addendum

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains information necessary to medical officers concerned with the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the medical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

  11. Induced radioisotopes in a linac treatment hall

    International Nuclear Information System (INIS)

    When linacs operate above 8 MV an undesirable neutron field is produced whose spectrum has three main components: the direct spectrum due to those neutrons leaking out from the linac head, the scattered spectrum due to neutrons produced in the head that collides with the nuclei in the head losing energy and the third spectrum due to room-return effect. The third category of spectrum has mainly epithermal and thermal neutrons being constant at any location in the treatment hall. These neutrons induce activation in the linac components, the concrete walls and in the patient body. Here the induced radioisotopes have been identified in concrete samples located in the hall and in one of the wedges. The identification has been carried out using a gamma-ray spectrometer. - Highlights: • Portland cement samples were located inside a treatment hall with a 15 MV linac. • Induced radioisotopes were measured with a NaI(Tl) γ-ray spectrometer. • 56Mn, 24Na, and 28Al were identified and the specific activity was estimated. • In a wedge, 56Mn was induced by the photoneutrons

  12. Actual and future situations of the use of radioisotopes

    International Nuclear Information System (INIS)

    It is anticipated to medium term, an increase in the demand of the radioisotopes for medicine, industry and research, as well as the application of new radioisotopes derived from the development of new radiopharmaceuticals products for diagnosis and therapy applications. The personal and clinical dosimetry will have to be prepared for the new challenges. (Author)

  13. Utilization of material testing reactor for radioisotope production

    International Nuclear Information System (INIS)

    In April 2000, JAEA (former JAERI) and CTC reached an agreement that we took over the radioisotope production from JAEA. We set up our facility in the Tokai Research and Development Center Nuclear Science Research Institute and started services. In this paper, we state present status of the production of radioisotopes in Japan and development activities in the future. (author)

  14. Guide to the safe handling of radioisotopes in hydrology

    International Nuclear Information System (INIS)

    Radioisotopic tracers are frequently used in hydrological investigations. This manual provides recommendations on safety measures to be used in these investigations. The annexes provide lists of radioisotopic techniques that have been employed together with an indication of the quantities of isotopes used.

  15. Adsorption of cesium on cement mortar from aqueous solutions

    Energy Technology Data Exchange (ETDEWEB)

    Volchek, Konstantin, E-mail: konstantin.volchek@ec.gc.ca [Emergencies Science and Technology Section, Environment Canada, 335 River Road, Ottawa, Ontario, Canada K1A 0H3 (Canada); Miah, Muhammed Yusuf [Emergencies Science and Technology Section, Environment Canada, 335 River Road, Ottawa, Ontario, Canada K1A 0H3 (Canada); Department of Applied Chemistry and Chemical Technology, Noakhali Science and Technology University (Bangladesh); Kuang, Wenxing; DeMaleki, Zack [Emergencies Science and Technology Section, Environment Canada, 335 River Road, Ottawa, Ontario, Canada K1A 0H3 (Canada); Tezel, F. Handan [Department of Chemical and Biological Engineering, University of Ottawa, 161 Louis-Pasteur, Ottawa, Ontario, Canada K1N 6N5 (Canada)

    2011-10-30

    Highlights: {yields} The adsorption of cesium on cement mortar was investigated in a range of temperatures and cesium concentrations. {yields} The pseudo-second order kinetic model produced a good fit with the experimental kinetic data. {yields} Equilibrium test results correlated well with the Freundlich isotherm adsorption model. {yields} The interaction between cesium ions and cement mortar was dominated by chemical adsorption. - Abstract: The adsorption of cesium on cement mortar from aqueous solutions was studied in series of bench-scale tests. The effects of cesium concentration, temperature and contact time on process kinetics and equilibrium were evaluated. Experiments were carried out in a range of initial cesium concentrations from 0.0103 to 10.88 mg L{sup -1} and temperatures from 278 to 313 K using coupons of cement mortar immersed in the solutions. Non-radioactive cesium chloride was used as a surrogate of the radioactive {sup 137}Cs. Solution samples were taken after set periods of time and analyzed by inductively coupled plasma mass spectroscopy. Depending on the initial cesium concentration, its equilibrium concentration in solution ranged from 0.0069 to 8.837 mg L{sup -1} while the respective surface concentration on coupons varied from 0.0395 to 22.34 {mu}g cm{sup -2}. Equilibrium test results correlated well with the Freundlich isotherm model for the entire test duration. Test results revealed that an increase in temperature resulted in an increase in adsorption rate and a decrease in equilibrium cesium surface concentration. Among several kinetic models considered, the pseudo-second order reaction model was found to be the best to describe the kinetic test results in the studied range of concentrations. The adsorption activation energy determined from Arrhenius equation was found to be approximately 55.9 kJ mol{sup -1} suggesting that chemisorption was the prevalent mechanism of interaction between cesium ions and cement mortar.

  16. Medical Radioisotope Scanning, Vol. II. Proceedings of the Symposium on Medical Radioisotope Scanning

    International Nuclear Information System (INIS)

    Medical applications of radioisotopes continue to grow in number and importance and medical centres in almost all countries of the world are now using radioactive materials both in the diagnosis and treatment of disease. An increasing proportion of these applications involves studies of the spatial distribution of radioactive material within the human body, for which purpose highly specialized scanning methods have been elaborated. By these methods it is possible to study the position, size and functional state of different organs, to detect tumours, cysts and other abnormalities and to obtain much useful information about regions of the body that are otherwise inaccessible, except by surgery. Progress in scanning methods in recent years has been very rapid and there have been many important advances in instrumentation and technique. The development of new forms of the gamma camera and of colour-scanning techniques are but two examples of recent improvements. The production of new radioisotopes and new labelled compounds has further extended the scope of these methods. To survey these new advances the International Atomic Energy Agency held a Symposium on Medical Radioisotope Scanning in Athens from 20-24 April 1964. The scientific programme of the meeting covered all aspects of scanning methods including theoretical principles, instrumentation, techniques and clinical applications. The World Health Organization assisted in the selection of papers by providing a consultant to the selection committee. The meeting followed the earlier IAEA/WHO Seminar on Medical Radioisotope Scanning in Vienna in 1959, which was attended by 36 participants and at which 14 papers were presented. Some idea of the growth of interest in the subject may be gained from the fact that the Symposium was attended by 160 participants from 26 countries and 4 international organizations, and that 58 papers were presented. The published proceedings, comprising two volumes, contain all the

  17. Medical Radioisotope Scanning. Vol. I. Proceedings of the Symposium on Medical Radioisotope Scanning

    International Nuclear Information System (INIS)

    Medical applications of radioisotopes continue to grow in number and importance and medical centres in almost all countries of the world are now using radioactive materials both in the diagnosis and treatment of disease. An increasing proportion of these applications involves studies of the spatial distribution of radioactive material within the human body, for which purpose highly specialized scanning methods have been elaborated. By these methods it is possible to study the position, size and functional state of different organs, to detect tumours, cysts and other abnormalities and to obtain much useful information about regions of the body that are otherwise inaccessible, except by surgery. Progress in scanning methods in recent years has been very rapid and there have been many important advances in instrumentation and technique. The development of new forms of the gamma camera and of colour-scanning techniques are but two examples of recent improvements. The production of new radioisotopes and new labelled compounds has further extended the scope of these methods. To survey these new advances the International Atomic Energy Agency held a Symposium on Medical Radioisotope Scanning in Athens from 20 - 24 April 1964. The scientific programme of the meeting covered all aspects of scanning methods including theoretical principles, instrumentation, techniques and clinical applications. The World Health Organization assisted in the selection of papers by providing a consultant to the selection committee. The meeting followed the earlier IAEA/WHO Seminar on Medical Radioisotope Scanning in Vienna in 1959, which was attended by 36 participants and at which 14 papers were presented. Some idea of the growth of interest in the subject may be gained from the fact that the Symposium was attended by 160 participants from 26 countries and 4 international organizations, and that 58 papers were presented. The published proceedings, comprising two volumes, contain all the

  18. Sympathetic cooling in a rubidium cesium mixture: Production of ultracold cesium atoms

    International Nuclear Information System (INIS)

    This thesis presents experiments for the production of ultracold rubidium cesium mixture in a magnetic trap. The long-termed aim of the experiment is the study of the interaction of few cesium atoms with a Bose-Einstein condensate of rubidium atoms. Especially by controlled variation of the cesium atom number the transition in the description of the interaction by concepts of the one-particle physics to the description by concepts of the many-particle physics shall be studied. The rubidium atoms are trapped in a magneto-optical trap (MOT) and from there reloaded into a magnetic trap. In this the rubidium atoms are stored in the state vertical stroke f=2,mf=2 right angle of the electronic ground state and evaporatively cooled by means of microwave-induced transitions into the state vertical stroke f=1,mf=1] (microwave cooling). The cesium atoms are also trppaed in a MOT and into the same magnetic trap reloaded, in which they are stored in the state vertical stroke f=4,mf=4 right angle of the electronic ground state together with rubidium. Because of the different hyperfine splitting only rubidium is evaporatively cooled, while cesium is cooled jointly sympathetically - i.e. by theramal contact via elastic collisions with rubidium atoms. The first two chapters contain a description of interatomic interactions in ultracold gases as well as a short summary of theoretical concepts in the description of Bose-Einstein condensates. The chapters 3 and 4 contain a short presentation of the methods applied in the experiment for the production of ultracold gases as well as the experimental arrangement; especially in the framework of this thesis a new coil system has been designed, which offers in view of future experiments additionally optical access for an optical trap. Additionally the fourth chapter contains an extensive description of the experimental cycle, which is applied in order to store rubidium and cesium atoms together into the magnetic trap. The last chapter

  19. Integro-differential equation analysis and radioisotope imaging systems. Research proposal. [Testing of radioisotope imaging system in phantoms

    Energy Technology Data Exchange (ETDEWEB)

    Hart, H.

    1976-03-09

    Design modifications of a five-probe focusing collimator coincidence radioisotope scanning system are described. Clinical applications of the system were tested in phantoms using radioisotopes with short biological half-lives, including /sup 75/Se, /sup 192/Ir, /sup 43/K, /sup 130/I, and /sup 82/Br. Data processing methods are also described. (CH)

  20. Notification determining details of technical standards concerning transport of radioisotopes or goods contaminated by radioisotopes outside works or enterprises

    International Nuclear Information System (INIS)

    This rule is established under the provisions of the regulation for the execution of the law on the prevention of radiation injuries by radioisotopes. Terms are used in this rule for the same meanings as in the regulation. The concentration of radioisotopes to which the technical standards for transport outside enterprises are not applied is 0.002 micro-curie per gram. The radioisotopes which can be transported as L type transported goods are defined in detail, excluding explosive or spontaneously igniting radioisotopes. The quantity limit of radioisotopes which can be transported as A type transported goods is the values A1 and A2 defined in this rule. The permissible surface density defined by the Director General of the Science and Technology Agency are 1/100,000 micro-curie per cm2 for the radioisotopes emitting alpha-ray, and 1/10,000 micro-curie per cm2 for the radioisotopes which do not emit alpha-ray. The leak quantity of radioisotopes specified by the Director General is 1/1,000,000 of A2 value for BM type transported goods and 1/1,000 of A2 value for BU type goods. The test conditions for each type of transported goods, dangerous goods, the limit of the number of transported goods and signs are stipulated, respectively. Permissible exposure dose is 1.5 rem a year for persons other than radiation workers. (Okada, K.)

  1. Intense non-relativistic cesium ion beam

    International Nuclear Information System (INIS)

    The Heavy Ion Fusion group at Lawrence Berkeley Laboratory has constructed the One Ampere Cesium Injector as a proof of principle source to supply an induction linac with a high charge density and high brightness ion beam. This is studied here. An electron beam probe was developed as the major diagnostic tool for characterizing ion beam space charge. Electron beam probe data inversion is accomplished with the EBEAM code and a parametrically adjusted model radial charge distribution. The longitudinal charge distribution was not derived, although it is possible to do so. The radial charge distribution that is derived reveals an unexpected halo of trapped electrons surrounding the ion beam. A charge fluid theory of the effect of finite electron temperature on the focusing of neutralized ion beams (Nucl. Fus. 21, 529 (1981)) is applied to the problem of the Cesium beam final focus at the end of the injector. It is shown that the theory's predictions and assumptions are consistent with the experimental data, and that it accounts for the observed ion beam radius of approx. 5 cm, and the electron halo, including the determination of an electron Debye length of approx. 10 cm

  2. Microbial uptake of uranium, cesium, and radium

    International Nuclear Information System (INIS)

    The ability of diverse microbial species to concentrate uranium, cesium, and radium was examined. Saccharomyces cerevisiae, Pseudomonas aeruginosa, and a mixed culture of denitrifying bacteria accumulated uranium to 10 to 15% of the dry cell weight. Only a fraction of the cells in a given population had visible uranium deposits in electron micrographs. While metabolism was not required for uranium uptake, mechanistic differences in the metal uptake process were indicated. Uranium accumulated slowly (hours) on the surface of S. cerevisiae and was subject to environmental factors (i.e., temperature, pH, interfering cations and anions). In contrast, P. aeruginosa and the mixed culture of denitrifying bacteria accumulated uranium rapidly (minutes) as dense, apparently random, intracellular deposits. This very rapid accumulation has prevented us from determining whether the uptake rate during the transient between the initial and equilibrium distribution of uranium is affected by environmental conditions. However, the final equilibrium distributions are not affected by those conditions which affect uptake by S. cerevisiae. Cesium and radium were concentrated to a considerably lesser extent than uranium by the several microbial species tested. The potential utility of microorganisms for the removal and concentration of these metals from nuclear processing wastes and several bioreactor designs for contacting microorganisms with contaminated waste streams will be discussed

  3. Biosorption behavior and mechanism of cesium-137 on Rhodosporidium fluviale strain UA2 isolated from cesium solution

    International Nuclear Information System (INIS)

    In order to identify a more efficient biosorbent for 137Cs, we have investigated the biosorption behavior and mechanism of 137Cs on Rhodosporidium fluviale (R. fluviale) strain UA2, one of the dominant species of a fungal group isolated from a stable cesium solution. We observed that the biosorption of 137Cs on R. fluviale strain UA2 was a fast and pH-dependent process in the solution composed of R. fluviale strain UA2 (5 g/L) and cesium (1 mg/L). While a Langmuir isotherm equation indicated that the biosorption of 137Cs was a monolayer adsorption, the biosorption behavior implied that R. fluviale strain UA2 adsorbed cesium ions by electrostatic attraction. The TEM analysis revealed that cesium ions were absorbed into the cytoplasm of R. fluviale strain UA2 across the cell membrane, not merely fixed on the cell surface, which implied that a mechanism of metal uptake contributed largely to the cesium biosorption process. Moreover, PIXE and EPBS analyses showed that ion-exchange was another biosorption mechanism for the cell biosorption of 137Cs, in which the decreased potassium ions were replaced by cesium ions. All the above results implied that the biosorption of 137Cs on R. fluviale strain UA2 involved a two-step process. The first step is passive biosorption that cesium ions are adsorbed to cells surface by electrostatic attraction; after that, the second step is active biosorption that cesium ions penetrate the cell membrane and accumulate in the cytoplasm. - Highlights: • Microorganisms isolated from a cesium solution are considered as a biosorbent to remove cesium ions. • The biosorption equilibrium is fitted well to a Langmuir model with a correlation coefficient of 0.9997. • First attempt to explore biosorption mechanisms using PIXE and EPBS. • Living and dead microorganisms have different biosorption mechanisms. • The biosorption of 137Cs involved a two-step process: passive and active

  4. Adsorption of cesium on cement mortar from aqueous solutions.

    Science.gov (United States)

    Volchek, Konstantin; Miah, Muhammed Yusuf; Kuang, Wenxing; DeMaleki, Zack; Tezel, F Handan

    2011-10-30

    The adsorption of cesium on cement mortar from aqueous solutions was studied in series of bench-scale tests. The effects of cesium concentration, temperature and contact time on process kinetics and equilibrium were evaluated. Experiments were carried out in a range of initial cesium concentrations from 0.0103 to 10.88 mg L(-1) and temperatures from 278 to 313 K using coupons of cement mortar immersed in the solutions. Non-radioactive cesium chloride was used as a surrogate of the radioactive (137)Cs. Solution samples were taken after set periods of time and analyzed by inductively coupled plasma mass spectroscopy. Depending on the initial cesium concentration, its equilibrium concentration in solution ranged from 0.0069 to 8.837 mg L(-1) while the respective surface concentration on coupons varied from 0.0395 to 22.34 μg cm(-2). Equilibrium test results correlated well with the Freundlich isotherm model for the entire test duration. Test results revealed that an increase in temperature resulted in an increase in adsorption rate and a decrease in equilibrium cesium surface concentration. Among several kinetic models considered, the pseudo-second order reaction model was found to be the best to describe the kinetic test results in the studied range of concentrations. The adsorption activation energy determined from Arrhenius equation was found to be approximately 55.9 kJ mol(-1) suggesting that chemisorption was the prevalent mechanism of interaction between cesium ions and cement mortar.

  5. Energy Recovery Linacs for Commercial Radioisotope Production

    Energy Technology Data Exchange (ETDEWEB)

    Sy, Amy [Jefferson Lab, Newport News, VA; Krafft, Geoffrey A. [Jefferson Lab, Newport News, VA; Johnson, Rolland [Muons, Inc., Batavia, IL; Roberts, Tom; Boulware, Chase; Hollister, Jerry

    2015-09-01

    Photonuclear reactions with bremsstrahlung photon beams from electron linacs can generate radioisotopes of critical interest. An SRF Energy Recovery Linac (ERL) provides a path to a more diverse and reliable domestic supply of short-lived, high-value, high-demand isotopes in a more compact footprint and at a lower cost than those produced by conventional reactor or ion accelerator methods. Use of an ERL enables increased energy efficiency of the complex through energy recovery of the waste electron beam, high electron currents for high production yields, and reduced neutron production and shielding activation at beam dump components. Simulation studies using G4Beamline/GEANT4 and MCNP6 through MuSim, as well as other simulation codes, will design an ERL-based isotope production facility utilizing bremsstrahlung photon beams from an electron linac. Balancing the isotope production parameters versus energy recovery requirements will inform a choice of isotope production target for future experiments.

  6. Emerging applications of radioisotopes in nuclear medicine

    International Nuclear Information System (INIS)

    Advances in the domain of radioisotopes and radiopharmaceuticals has been very noteworthy over the past decade and played a major role in enhancing the Nuclear Medicine practice. A number of them have been employed in the day to day clinical practice and have benefited a large number of patients. For the purpose of systematic discussion, we shall classify into two major heads A. Recent advances in clinical applications of traditional radiotracers. B. Newer Radiopharmaceuticals and their applications. The latter could be further subdivided in to the following: (a) Diagnostic (includes i. PET radiopharmaceuticals and ii. Non-PET radiopharmaceuticals for conventional gamma camera imaging) and (b) Therapeutic advances. In the present communication, we shall explore the major developments emphasizing the country perspective

  7. Radioisotope Power Systems Program: A Program Overview

    Science.gov (United States)

    Hamley, John A.

    2016-01-01

    NASA's Radioisotope Power Systems (RPS) Program continues to plan, mature research in energy conversion, and partners with the Department of Energy (DOE) to make RPS ready and available to support the exploration of the solar system in environments where the use of conventional solar or chemical power generation is impractical or impossible to meet potential future mission needs. Recent programs responsibilities include providing investment recommendations to NASA stakeholders on emerging thermoelectric and Stirling energy conversion technologies and insight on NASA investments at DOE in readying a generator for the Mars 2020 mission. This presentation provides an overview of the RPS Program content and status and the approach used to maintain the readiness of RPS to support potential future NASA missions.

  8. Recent progress in development of radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Byung Mok [HANARO Center, Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-10-01

    The Korea multipurpose research reactor, HANARO(Hi-flux Advanced Neutron Application Reactor) is designed and constructed to obtain high density neutron flux (max. 5x10{sup 14} n/cm{sup 2}{center_dot}sec) with relatively low thermal output (30 MW) in order to utilize for various studies such as fuel and material test, radioisotope production, neutron activation analysis, neutron beam experiment, neutron transmutation doping, etc. HANARO has 32 vertical channels (3 in-core, 4 out-core, 25 reflector) and 7 horizontal channels. KAERI has constructed 4 concrete hot cells for production of Co-60, Ir-192, etc. and 6 lead hot cells for production of medical RIs(I-131, Mo-99, etc.). Other 11 lead hot cells will be completed by Feb. 1998 for production of Sm-153, Dy-165, Ho-166, etc. Clean room facilities were installed for production of radiopharmaceuticals. (author)

  9. Alpha indirect conversion radioisotope power source

    Energy Technology Data Exchange (ETDEWEB)

    Sychov, Maxim [TRACE Photonics Inc., 1680 West Polk, Charleston, IL 61920 (United States)], E-mail: msychov@yahoo.com; Kavetsky, Alexandr; Yakubova, Galina; Walter, Gabriel; Yousaf, Shahid; Lin, Qian; Chan, Doris; Socarras, Heather; Bower, Kenneth [TRACE Photonics Inc., 1680 West Polk, Charleston, IL 61920 (United States)

    2008-02-15

    Advantages of radioisotope-powered electric generators include long service life, wide temperature range operation and high-energy density. We report development of a long-life generator based on indirect conversion of alpha decay energy. Prototyping used 300 mCi Pu-238 alpha emitter and AlGaAs photovoltaic cells designed for low light intensity conditions. The alpha emitter, phosphor screens, and voltaic arrays were assembled into a power source with the following characteristics: I{sub sc}=14 {mu}A; U{sub oc}=2.3 V; power output -21 {mu}W. Using this prototype we have powered an eight-digit electronic calculator and wrist watch.

  10. Radioisotope Power System Facility shielding analysis

    International Nuclear Information System (INIS)

    A series of calculations for the Radioisotope Power System Facility have been performed. These analyses have determined the shielding required for storage, testing, and transport of 238Pu heat source modules using the Monte Carlo code MCNP3B. The source terms and the assumptions used have been verified by comparison of calculated dose rates with measured ones. This paper describes the methodology used for shielding designs and the utilization of available variance reduction techniques to improve the computational efficiency. The new version of MCNP (MCNP3B) with a repeated structure capability was used. It decreased the chance for computer model errors and greatly decreased the model setup time. 2 refs., 3 figs., 2 tabs

  11. Recent developments in radiation equipment and radioisotopes

    International Nuclear Information System (INIS)

    A review is given of the technology of the uses of radiation equipment and radioisotopes, in which field Canada has long been a world leader. AECL Commercial Products has pioneered many of the most important applications. The development and sale of Co-60 radiation teletherapy units for cancer treatment is a familiar example of such an application and Commercial Products dominates the world market. Another such example is the marketing of Mo-99, which is produced in the NRX and NRU reactors at Chalk River, and from which the short-lived daughter Tc-99 is eluted as required for use in in-vivo diagnosis. New products coming into use for this purpose include Tl-201, I-123, Ga-67 and In-111, all produced in the TRIUMF cyclotron in Vancouver, while I-125 continues to be in demand for in-vitro radioimmunoassays. Radioisotopes continue to play an important part in manufacturing, where their well-known uses include controlling thickness, contents, etc., in production, and industrial radiography. The application of large industrial irradiators for the sterilization of medical products is now a major world industry for which Commercial Products is the main manufacturer. Isotopes are also used in products such as smoke detectors. Isotopes continue to find extensive use as tracers, both in industrial applications and in animal and plant biology studies. Some more recent uses include pest control by the Σsterile maleΣ technique and neutron activation and delayed neutron counting in uranium assay. The review concludes with an account of the development and prospects of AECL Commercial Products. (author)

  12. Status of the NASA Stirling Radioisotope Project

    Science.gov (United States)

    Schreiber, Jeffrey G.

    2007-01-01

    Free-piston Stirling power conversion has been considered a candidate for radioisotope power systems for space for more than a decade. Prior to the free-piston Stirling architecture, systems were designed with kinematic Stirling engines that used linkages and rotary alternators to convert heat to electricity. These systems were able to achieve long life by lightly loading the linkages; however, the live was nonetheless limited. When the free-piston configuration was initially proposed, it was thought to be attractive due to the relatively high conversion efficiency, acceptable mass, and the potential for long life and high reliability based on wear-free operation. These features have consistently been recognized by teams that have studied technology options for radioisotope space power systems. Since free-piston Stirling power conversion was first considered for space power applications, there have been major advances in three general areas of development: hardware that has demonstrated long-life and reliability, the success achieved by Stirling cryocoolers in space, and the overall developmental maturity of the technology for both space and terrestrial applications. Based on these advances, free-piston Stirling convertors are currently being developed for space power, and for a number of terrestrial applications. They commonly operate with the power, efficiency, life, and reliability as intended, and much of the development now centers on system integration. This paper will summarize the accomplishments of free-piston Stirling power conversion technology over the past decade, review the status of development with regard to space power, and discuss the challenges that remain.

  13. Training in radioisotope uses for agricultural investigations

    International Nuclear Information System (INIS)

    Full text: Seventeen students from Cambodia, the Republic of China, India, Israel, Pakistan, the Philippines, Syria, Thailand and the United Arab Republic attended an inter-regional training course on the use of radioisotopes in soil and plant investigations in Manila, Philippines. Held from 3 October to 25 November 1966, the course was organised by the International Atomic Energy Agency (IAEA) and the Food and Agricultural Organization (FAO) under the UN Expanded Programme of Technical Assistance. During the first three weeks, the students, most of whom had graduate training or experience in agricultural research, were taught the basic characteristics of isotopes and the techniques of measuring radiation. Lectures and practical laboratory exercises in the more specialized studies of soil-plant relations took up the rest of the time. Some of the topics covered were: field and water culture experiments, measurement of nutrient in the soil, autoradiography of plant materials, plant mutation and breeding, use of radioisotopes in the study of photosynthesis and plant growth, nuclear techniques for determining soil moisture and density, the use of labelled fertilizer in studying the efficient utilization of fertilizer, etc. Dr. Getulio B. Viado, Head of the Training Institute, Philippine Atomic Energy Commission, was Director of the course, while Dr. Shaukat Ahmed, Director of the Atomic Research Centre, West Pakistan, served as Technical Adviser and as a principal lecturer. The teaching staff consisted of Philippine scientists and three visiting professors: Dr. Victor Middelboe of the IAEA Seibersdorf Laboratory, Dr. M.S. Chandraratna of Ceylon and Dr. S.C. Chang of the Republic of China. (author)

  14. A 5 MW TRIGA reactor design for radioisotope production

    International Nuclear Information System (INIS)

    The production and preparation of commercial-scale quantities of radioisotopes has become an important activity as their medical and industrial applications continue to expand. There are currently various large multipurpose research reactors capable of producing ample quantities of radioisotopes. These facilities, however, have many competing demands placed upon them by a wide variety of researchers and scientific programs which severely limit their radioisotope production capability. A demonstrated need has developed for a simpler reactor facility dedicated to the production of radioisotopes on a commercial basis. This smaller, dedicated reactor could provide continuous fission and activation product radioisotopes to meet commercial requirements for the foreseeable future. The design of a 5 MW TRIGA reactor facility, upgradeable to 10 MW, dedicated to the production of industrial and medical radioisotopes is discussed. A TRIGA reactor designed specifically for this purpose with its demonstrated long core life and simplicity of operation would translate into increased radioisotope production. As an example, a single TRIGA could supply the entire US needs for Mo-99. The facility is based on the experience gained by General Atomics in the design, installation, and construction of over 60 other TRIGAs over the past 35 years. The unique uranium-zirconium hydride fuel makes TRIGA reactors inexpensive to build and operate, reliable in their simplicity, highly flexible due to unique passive safety, and environmentally friendly because of minimal power requirements and long-lived fuel. (author)

  15. Development and application of industrial radioisotope instruments in China

    International Nuclear Information System (INIS)

    Industrial radioisotope instruments are emerging as advanced monitoring, controlling and automation tools for industries in China. Especially the on-line analysis systems based on radioisotope instruments, referred to as nucleonic control systems (NCS), have more and more important role in the modernization and optimization of industrial processes. Over nearly four decades significant progress has been made in the development and application of radioisotope instruments in China. After a brief review of the history of radioisotope instruments, the state of the art of this kind of instruments and recent examples of their applications are given. Technical and economic benefits have resulted from the industrial applications of radioisotope instruments and the sales of products of their own in marketing. It is expected that along with the high speed growth of national economy, there will be greater demand for radioisotope instruments and nucleonic control systems in Chinese industry to promote the technological transformation and progress of traditional industries and to establish high-tech industries with technology-intensive products. Sustained efforts for the research and development of radioisotope instrument should be made to up-grade domestic instruments and to satisfy the needs of the smaller scale industries more common in China for low cost systems. (1 fig., 2 tabs.)

  16. Synthesis and peculiarities of the cesium zeolite crystal structure (cesite)

    International Nuclear Information System (INIS)

    An attempt is made to synthesize cesium zeolite by introduction of amorphous seed crystals which correspond by composition with cesium-containing zeolite into the aluminosilicate gel, since this method can produce zeolite with a crystal structure it would not adopt under the usual conditions. It is seen that during crystablization upon introduction of a seed crystal the cesium content in zeolite decreases. A more complete structural elucidation of zeolite obtained by the suggested method was carried out by x0ray and IR spectral analyses. The data of x-ray analysis showed that the structures of synthesized zeolite and binary octagonal pores are similar

  17. Pollution of drug-technical materials by cesium-137

    International Nuclear Information System (INIS)

    Drug-technical raw materials are medicinal plants (flowers, folium, grasses, mushrooms, roots, fruits, berry, kidney, cortex), used in pharmacy. To limit receipt cesium-137 in people body in 1993 in the Republic of Belarus were created 'Temporary permission levels of the cesium-137 radionuclides contents in drug-technical raw materials' were created (TPL-1993). The permission levels of cesium-137 are following: for drug-technical raw material (flowers, folium, grass, mushrooms, roots and other plants parts) - 1850 Bq/kg, for dried up fruits and berries - 2590 Bq/kg. (Author)

  18. Management of cesium loaded AMP- Part I preparation of 137Cesium concentrate and cementation of secondary wastes

    International Nuclear Information System (INIS)

    Separation of 137cesium from High Level Waste can be achieved by use of composite-AMP, an engineered form of Ammonium Molybdo-Phosphate(AMP). Direct vitrification of cesium loaded composite AMP in borosilicate glass matrix leads to separation of water soluble molybdate phase. A proposed process describes two different routes of selective separation of molybdates and phosphate to obtain solutions of cesium concentrates. Elution of 137Cesium from composite-AMP by decomposing it under flow conditions using saturated barium hydroxide was investigated. This method leaves molybdate and phosphate embedded in the column but only 70% of total cesium loaded on column could be eluted. Alternatively composite-AMP was dissolved in sodium hydroxide and precipitation of barium molybdate-phosphate from the resultant solution, using barium nitrate was investigated by batch methods. The precipitation technique gave over 99.9% of 137Cesium activity in solutions, free of molybdates and phosphates, which is ideally suited for immobilization in borosilicate glass matrix. Detailed studies were carried out to immobilize secondary waste of 137Cesium contaminated barium molybdate-phosphate precipitates in the slag cement matrix using vermiculite and bentonite as admixtures. The cumulative fraction of 137Cs leached from the cement matrix blocks was 0.05 in 140 days while the 137Cs leach rate was 0.001 gm/cm2/d. (author)

  19. Utilization of radioisotopes and irradiation in crop protection research

    International Nuclear Information System (INIS)

    There is a growing realization of the benefits which may be derived from the application of radioisotopes and radiation sources in the different disciplines of crop protection research. Many investigations which might only be carried out with extreme difficulty or not all by conventional methods, could be pursued with relative ease. Radioisotopes and irradiation have been utilized in understanding the physiology and behaviour of pests and their biochemical processes and in consequence, have contributed beneficially to the development of better control techniques and more effective pesticides. On the environmental aspects, radioisotopic techniques have provided a useful tool in understanding the behaviour, metabolism and residues of pesticides in the environment. (author)

  20. Waste minimization in the Los Alamos Medical Radioisotope Program

    International Nuclear Information System (INIS)

    Since the mid-1970s the Los Alamos Medical Radioisotope Program has been irradiating target materials to produce and recover radioisotopes for applications in medicine, environmental science, biology, physics, materials research, and other disciplines where radiotracers find utility. By necessity, the chemical processing of targets and the isolation of radioisotopes generates radioactive waste materials. Recent years have brought pressure to discontinue the use of hazardous materials and to minimize radioactive waste volumes. Substantial waste reduction measures have been introduced at the irradiation facility, in processing approaches, and even in the ways the product isotopes are supplied to users

  1. Cesium adsorption/desorption behavior of clay minerals considering actual contamination conditions in Fukushima

    Science.gov (United States)

    Mukai, Hiroki; Hirose, Atsushi; Motai, Satoko; Kikuchi, Ryosuke; Tanoi, Keitaro; Nakanishi, Tomoko M.; Yaita, Tsuyoshi; Kogure, Toshihiro

    2016-02-01

    Cesium adsorption/desorption experiments for various clay minerals, considering actual contamination conditions in Fukushima, were conducted using the 137Cs radioisotope and an autoradiography using imaging plates (IPs). A 50 μl solution containing 0.185 ~ 1.85 Bq of 137Cs (10-11 ~ 10-9 molL-1 of 137Cs) was dropped onto a substrate where various mineral particles were arranged. It was found that partially-vermiculitized biotite, which is termed “weathered biotite” (WB) in this study, from Fukushima sorbed 137Cs far more than the other clay minerals (fresh biotite, illite, smectite, kaolinite, halloysite, allophane, imogolite) on the same substrate. When WB was absent on the substrate, the amount of 137Cs sorbed to the other clay minerals was considerably increased, implying that selective sorption to WB caused depletion of radiocesium in the solution and less sorption to the coexisting minerals. Cs-sorption to WB continued for about one day, whereas that to ferruginous smectite was completed within one hour. The sorbed 137Cs in WB was hardly leached with hydrochloric acid at pH 1, particularly in samples with a longer sorption time. The presence/absence of WB sorbing radiocesium is a key factor affecting the dynamics and fate of radiocesium in Fukushima.

  2. Cesium adsorption/desorption behavior of clay minerals considering actual contamination conditions in Fukushima.

    Science.gov (United States)

    Mukai, Hiroki; Hirose, Atsushi; Motai, Satoko; Kikuchi, Ryosuke; Tanoi, Keitaro; Nakanishi, Tomoko M; Yaita, Tsuyoshi; Kogure, Toshihiro

    2016-01-01

    Cesium adsorption/desorption experiments for various clay minerals, considering actual contamination conditions in Fukushima, were conducted using the (137)Cs radioisotope and an autoradiography using imaging plates (IPs). A 50 μl solution containing 0.185 ~ 1.85 Bq of (137)Cs (10(-11) ~ 10(-9 )molL(-1) of (137)Cs) was dropped onto a substrate where various mineral particles were arranged. It was found that partially-vermiculitized biotite, which is termed "weathered biotite" (WB) in this study, from Fukushima sorbed (137)Cs far more than the other clay minerals (fresh biotite, illite, smectite, kaolinite, halloysite, allophane, imogolite) on the same substrate. When WB was absent on the substrate, the amount of (137)Cs sorbed to the other clay minerals was considerably increased, implying that selective sorption to WB caused depletion of radiocesium in the solution and less sorption to the coexisting minerals. Cs-sorption to WB continued for about one day, whereas that to ferruginous smectite was completed within one hour. The sorbed (137)Cs in WB was hardly leached with hydrochloric acid at pH 1, particularly in samples with a longer sorption time. The presence/absence of WB sorbing radiocesium is a key factor affecting the dynamics and fate of radiocesium in Fukushima.

  3. Development of composite ion exchanger for separation of cesium from high level liquid waste

    International Nuclear Information System (INIS)

    137Cs (t1/2 = 30 years) is one of the major radioisotope present in high level liquid waste (HLLW) generated during the reprocessing of nuclear fuel. Separation of 137Cs from HLLW results in reduction of personal radiation exposure during the conditioning, transportation, storage and disposal. In addition, 137Cs has enormous application as a radiation source in food preservation, sterilization of medical products, brachytherapy, blood irradiation, hygienization of sewage sludge etc. Ammonium molybdophosphate (AMP), an inorganic ion exchanger, has high selectivity and high exchange capacity for Cs. It exits as microcrystalline powder which is not amenable for column operation. ALIX is a composite material in which AMP is physically blended with inert polymeric substrate to improve its column property, exchange kinetics and increase its mechanical strength. The observed excellent properties of the composite are attributed to its engineered structure which is formed during its production. SEM analysis of ALIX shows that AMP crystals embedded in the cavities are not covered by the polymer which greatly enhances its availability for cesium exchange. The highly porous structure of the composite having 49% void volume facilitates faster kinetics of exchange of Cs from the aqueous phase and increased rate of reaction with alkali required during its dissolution

  4. Structure of double hafnium and cesium sulfate

    International Nuclear Information System (INIS)

    The structure of a compound whose formula according to the structural investigation is Cssub(2+x)Hf(SOsub(4))sub(2+x)(HSOsub(4))sub(2-x)x3Hsub(2)O (x approximately 0.7) (a=10.220, b=12.004, c=15.767 A, space group Pcmn) is determined by diffractometric data (2840 reflections, anisotropic refinement, R=0.087). It is build of complex unions [Hf(SO4)4H2O]4-, Cs+ cations and water molecules. Eight O atoms surrounding Hf atom (dodecahedron Hf-O 2.10-2.22 A) belong to four sulphate groups and water molecule. Three sulphate groups are bidentate-cyclic, and one group - monodentate relative to Hf. The structure has a cesium deficit in particular positions

  5. Biosorption of uranium, radium, and cesium

    International Nuclear Information System (INIS)

    Some fundamental aspects of the biosorption of metals by microbial cells were investigated. These studies were carried out in conjunction with efforts to develop a process to utilize microbial cells as biosorbents for the removal of radionuclides from waste streams generated by the nuclear fuel cycle. It was felt that an understanding of the mechanism(s) of metal uptake would potentially enable the enhancement of the metal uptake phenomenon through environmental or genetic manipulation of the microorganisms. Also presented are the results of a preliminary investigation of the applicability of microorganisms for the removal of 137cesium and 226radium from existing waste solutions. The studies were directed primarily at a characterization of uranium uptake by the yeast, Saccharomyces cerevisiae, and the bacterium, Pseudomonas aeruginosa

  6. Atmospheric transmission for cesium DPAL using TDLAS

    Science.gov (United States)

    Rice, Christopher A.; Perram, Glen P.

    2012-03-01

    The cesium (Cs) Diode Pumped Alkali Laser (DPAL) operates near 894 nm, in the vicinity of atmospheric water vapor absorption lines. An open-path Tunable Diode Laser Absorption (TDLAS) system composed of narrow band (~300 kHz) diode laser fiber coupled to a 12" Ritchey-Chrétien transmit telescope has been used to study the atmospheric transmission characteristics of Cs DPALs over extended paths. The ruggedized system has been field deployed and tested for propagation distances of greater than 1 km. By scanning the diode laser across many free spectral ranges, many rotational absorption features are observed. Absolute laser frequency is monitored with a High Finesse wavemeter to an accuracy of less than 10 MHz. Phase sensitive detection is employed with an absorbance of less than 1% observable under field conditions.

  7. Sorption of cesium and strontium by arid region desert soil

    International Nuclear Information System (INIS)

    Adsorption and ion exchange in soil systems are the principal mechanisms that retard the migration of nuclear waste to the biosphere. Cesium and strontium are two elements with radioactive isotopes (Cs137 and Sr90) that are commonly disposed of as nuclear waste. The sorption and ion exchange properties of nonradioactive cesium and strontium were studied in this investigation. The soil used in this study was collected at an experimental infiltration site on Frenchman Flat, a closed drainage basin on the Nevada Test Site. This soil is mostly nonsaline-alkali sandy loam and loamy sand with a cation exchange capacity ranging from 13 to 30 me/100g. The clay fraction of the soil contains illite, montmorillonite, and clinoptilolite. Ion exchange studies have shown that this soil sorbs cesium preferentially relative to strontium, and that charge for charge, the exchange-phase cations released from exchange sites exceed the cesium and strontium sorbed by the soil. 38 references, 22 figures

  8. Sorption of cesium on Olkiluoto mica gneiss, granodiorite and granite

    Energy Technology Data Exchange (ETDEWEB)

    Huitti, T.; Hakanen, M. [Univ. of Helsinki (Finland). Lab. of Radiochemistry; Lindberg, A. [Geological Survey of Finland, Espoo (Finland)

    1998-09-01

    Cesium was selected as a model to study the sorption in bedrock occurring by ion exchange mechanism. The aim of the study was to supplement the existing data on sorption occurring by ion exchange mechanism in bedrock of the candidate sites for spent fuel disposal at Olkiluoto. The sorption of cesium was studied on crushed mica gneiss, tonalite (granodiorite) and granite in artificial groundwaters. Fresh water was represented by Allard water, pH 8 and pH 7, and saline water by Ol-So water, pH 7 and pH 9. In addition, a Na-Ca-Cl brine water and its 1:10 dilution were used as simulants. Cesium concentrations were between 10{sup -8} and 10{sup -3} mol/l. The distribution coefficients of the sorption, R{sub d} and R{sub a} values were determined by batch method. Isotherms were partly non-linear with slopes 0.7 - 1.0 depending on rock and water. At the end of the sorption experiment, the water was analysed for cations exchanged for cesium. The sorption of cesium was also studied as a function of ionic strength. The ionic strength increased in the order Allard < 0l-Br 1:10 < 0l-So < 0l-Br. The sorption of cesium was lower at higher ionic strength and higher Cs concentration. The mineral composition of rocks was determined by thin section analysis, and the sorption distribution ratios on thin sections in the different waters were determined by batch technique. The minerals, that sorbed most cesium were determined by autoradiography. These were biotite, muscovite and chlorite. Cordierite in mica gneiss also sorbed cesium very effectively. (orig.) 12 refs.

  9. Adsorption Behaviour of Liquid 4He on Cesium Substrates

    OpenAIRE

    Iov, Valentin

    2004-01-01

    The aim of this thesis is to investigate the wetting properties of 4He on cesium substrates using optical and electrical methods. Due to the fact that the cesium substrates are deposited at low temperatures onto a thin silver underlayer, it is necessary firstly to study and understand the adsorption of helium on silver. The work presented here is structured as follows: some of the fundamental concepts on the theory of physisorbed films, such as van der Waals interaction, adsorption isotherms ...

  10. Current utilization of research reactor on radioisotopes production in China

    Energy Technology Data Exchange (ETDEWEB)

    Liu Yishu [Nuclear Power Institute of China, Chengdu (China)

    2000-10-01

    The main technical parameters of the four research reactors and their current utilization status in radioisotope manufacture and labeling compounds preparation are described. The radioisotopes, such as Co-60 sealed source, Ir-192 sealed source, {gamma}-knife source, I-131, I-125, Sm-153, P-32 series products, In-113m generator, Tc-99m gel generator, Re-188 gel generator, C-14, Ba-131, Sr-89, {sup 90}Y, etc., and their labeling compounds prepared from the reactor produced radionuclides, such as I-131-MIBG, I-131-Hippure, I-131-capsul, Sm-153-EDTMP, Re-186-HEDP, Re-186-HA, C-14-urea, and radioimmunoassay kits etc. are presented as well. Future development plan of radioisotopes and labeling compounds in China is also given. Simultaneously, the possibility and methods of bilateral or multilateral co-operation in utilization of research reactor, personnel and technology exchange of radioisotope production and labeling compounds is also discussed. (author)

  11. Variable Conductance Heat Pipes for Radioisotope Stirling Systems Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The overall program objective is to develop a high temperature variable conductance heat pipe (VCHP) backup radiator, and integrate it into a Stirling radioisotope...

  12. Short course on the use of radioisotopes in agriculture

    International Nuclear Information System (INIS)

    This report contains the papers delivered at the short course on the use of radioisotopes in agriculture held in Pretoria, South Africa, 22-24 April 1981. The following topics were discussed: principles of nuclear physics and radioactivity; biological effects of radiation; regulatory control of radioisotopes; basic radiation protection procedures; radiation detectors and counting instrumentation; statistics of radioactive observations; use of the neutron moisture meter in soil moisture determinations; soil moisture content and soil density measurements by the gamma soil moisture meter; trace element analysis; application and use of radioisotopes as tracers in soil studies; applications of isotopes in plants for the study of absorption and transportation of mineral elements; applications of radioisotopes in zoological studies

  13. A historical perspective on radioisotopic tracers in metabolism and biochemistry.

    Science.gov (United States)

    Lappin, Graham

    2015-01-01

    Radioisotopes are used routinely in the modern laboratory to trace and quantify a myriad of biochemical processes. The technique has a captivating history peppered with groundbreaking science and with more than its share of Nobel Prizes. The discovery of radioactivity at the end of the 19th century paved the way to understanding atomic structure and quickly led to the use of radioisotopes to trace the fate of molecules as they flowed through complex organic life. The 1940s saw the first radiotracer studies using homemade instrumentation and analytical techniques such as paper chromatography. This article follows the history of radioisotopic tracers from meager beginnings, through to the most recent applications. The author hopes that those researchers involved in radioisotopic tracer studies today will pause to remember the origins of the technique and those who pioneered this fascinating science.

  14. Safety Analysis for a Radioisotope Stirling Generator

    International Nuclear Information System (INIS)

    The Idaho National Laboratory (INL) is conducting safety analyses of various lowpower Radioisotope Stirling Generator (RSG) design concepts for the U. S. Department of Energy. These systems are electrical power generators converting thermal energy from plutonium (238Pu) decay to electrical energy via a Stirling cycle generator. The design and function are similar to the RTG (Radioisotope Thermoelectric Generator) used in space missions since the early 1960's, with a more efficient Stirling cycle generator replacing the proven thermoelectric converter. This paper discusses the methods the INL is employing in the safety analysis effort, along with the software tools, lessons learned, and results. The overall goal of our safety analyses is to determine the probability of an accidental plutonium release over the life of the generator. Historical accident rates for various transportation modes were investigated using event tree methods. Source terms were developed for these accidents including primarily impact, fire, and creep rupture. A negative result was defined as rupture of the tantalum alloy containment vessel surrounding the encapsulated plutonia pellet. Damage due to identified impact accidents was evaluated using non-linear finite element software tools. Material models, gathered from a wide variety of sources, included strain-rate and temperature dependencies on yield strength, strain hardening, and rupture. Both individual component and overall system simulation results will be validated by impact testing to be conducted by Los Alamos National Laboratory. Results from deterministic impact, fire, and creep rupture analyses were integrated into the probabilistic (Monte Carlo) risk assessment by correlation functions relating accident parameters to component damage. This approach presented challenges, which are addressed. Other significant issues include limitations of reliable material data at high temperatures and strain rates and development of a technique to

  15. Efficiency of Pm-147 direct charge radioisotope battery

    Energy Technology Data Exchange (ETDEWEB)

    Kavetskiy, A.; Yakubova, G.; Yousaf, S.M. [TRACE Photonics Inc, 1680 West Polk Avenue, Charleston, IL 61920 (United States); Bower, K., E-mail: kbower@tracephotonics.co [TRACE Photonics Inc, 1680 West Polk Avenue, Charleston, IL 61920 (United States); Robertson, J.D.; Garnov, A. [Department of Chemistry and University of Missouri Research Reactor, 1513 Research Park Drive, Columbia, MO 65211 (United States)

    2011-05-15

    A theoretical analysis is presented here of the efficiency of direct charge radioisotope batteries based on the efficiency of the radioactive source, the system geometry, electrostatic repulsion of beta particles from the collector, the secondary electron emission, and backscattered beta particles from the collector. Efficiency of various design batteries using Pm-147 sources was experimentally measured and found to be in good agreement with calculations. The present approach can be used for predicting the efficiency for different designs of direct charge radioisotope batteries.

  16. Seasonal variation of cesium 134 and cesium 137 in semidomestic reindeer in Norway after the Chernobyl accident

    Directory of Open Access Journals (Sweden)

    I.M. H. Eikelmann

    1990-09-01

    Full Text Available The Chernobyl accident had a great impact on the semidomestic reindeer husbandry in central Norway. Seasonal differences in habitat and diet resulted in large variations in observed radiocesium concentrations in reindeer after the Chernobyl accident. In three areas with high values of cesium-134 and cesium-137 in lichens, the main feed for reindeer in winter, reindeer were sampled every second month to monitor the seasonal variation and the decrease rate of the radioactivity. The results are based on measurements of cesium-134 and cesium-137 content in meat and blood and by whole-body monitoring of live animals. In 1987 the increase of radiocesium content in reindeer in Vågå were 4x from August to January. The mean reductions in radiocesium content from the winter 1986/87 to the winter 1987/88 were 32%, 50% and 43% in the areas of Vågå, Østre-Namdal and Lom respectively.

  17. Strategy for securing the national supply of radioisotopes

    International Nuclear Information System (INIS)

    Background: The global supply shortage of medical radioisotopes caused by the unscheduled shutdown of the aged reactors which supply over 90% of radioisotopes overall the world, has severely affected the normal healthcare system which depend on the technology of molecular imaging for diagnoses and therapy as well as the development of nuclear molecular imaging technology. Purpose: It is urgently needed to develop new alternative technologies to solve the problem of global radioisotope supply shortage. Methods: The proton cyclotron is a potential alternative technology to produce the 99mTc and the most of medical radioisotopes of clinical importance. Results: The quality of 99mTc produced by cyclotron, such as nuclide purity, specific activity and nonradioisotope impurities, has reached and/or exceeded that eluted from 99Mo/99mTc generator produced by reactor. Conclusions: It is the most operational and sustainable way to substitute the conventional global centralized supply by reactors with local centralized supply of radioisotopes by proton cyclotrons for securing the national supply of radioisotopes. (author)

  18. Prospect of radioisotopes and radiation utilization

    International Nuclear Information System (INIS)

    Radiation Utilization in Japan has been positioned, together with nuclear power generation, as one of the important cornerstones, and research and development and practical usage of it has been proceeded with steadily in the fields of industry, agriculture, medicine, and so on. In the field of medicine, SPECT and PET facilities, radio-immunoassay, radiotherapy has come widely to practical use. In the field of agriculture and fisheries, improvement of breed, sterile insect technique have been implemented, and eradication of melon fly has been achieved. In the field of industry, it is expected that the practical use of neutron radiography technique and research and development of synthesizing high performance, high function materials are progressed. In the environment preservation area, a pilot test using electron beam to treat the exhaust gases out of coal fired power plants, city garbages combustion facilities, city high way tunnels in order to establish de- sulphur/de-nitrogen technique is carried out. As the international contribution in the field of radiation utilization, the cooperation with developing countries and the cooperation among advanced countries are reported. In this paper, a prospect of radioisotopes and radiation utilization is described. (J.P.N.)

  19. Treatment of animal wastes contaminated with radioisotopes

    International Nuclear Information System (INIS)

    With increase of isotope utilizations as tracers in medicine, pharmacy, agriculture, biology and others, the management of resultant organic waste liquids and animal wastes is becoming a major problem. For the animal wastes contaminated with radioisotopes, numbers of studies and tests showed that drying them fully and the subsequent suitable disposal would be the most feasible procedures. This new method is being carried out since last year, which will shortly take the place of the keeping in formalin. For the drying, two alternative processes in particular are being investigated. As the one, freeze-drying apparatuses consist of refrigerating and freeze-drying devices. As the other, microwave-drying apparatuses feature rapid dehydration. The following matters are described: problems emerged in the course of studies and test; the drying processes, i.e. freeze-drying and microwave-drying, and their respective characteristics; and views of the Nuclear Safety Bureau, Science and Technology Agency, on animal waste drying. (J.P.N.)

  20. Versatile PC-logger for radioisotope measurements

    International Nuclear Information System (INIS)

    The logger, a personal computer and software is all to set up a radioisotope measuring system. It may find numerous applications in a wide range of disciplines: kinetics description of flow process in industry, slip velocity measurements in hydrotransport, flow rates evaluation in waste water treatment plants, nucleonic gauges in industry, ect. Readings from up to 4 scintillation detectors, the user has set to log, are stored in regular intervals. The user can set the logger to start and stop logging manually, with keyboard or from a program running on a connected PC. Stored data can be transferred to any computer with RS232 serial interface. The logger works equally well together with conventional PC's and 'lap-tops' for field work. Its internal program is stored in nonvolatile RAM. This makes it possible to upgrade or change the code by just down loading a new one. The logger is internal rechargeable batteries for measuring off-line; they remain as a back-up in case the external supply is disconnected or fails. (author)

  1. Safe Handling of Radioisotopes. 1973 Edition

    International Nuclear Information System (INIS)

    Under its Statute the International Atomic Energy Agency is empowered to provide for the application of standards of safety for protection against radiation to its own operations and to operations making use of assistance provided by it or with which it is otherwise directly associated. To this end authorities receiving such assistance are required to observe relevant health and safety measures prescribed by the Agency. As a first step, it was considered an urgent task to provide users of radionuclides with a manual of practice for the safe handling of these substances. The first edition of such a manual was published in 1958 and represented the first of the ''Safety Series'', a series of manuals and codes on health and safety published by the Agency. It was prepared after careful consideration of existing national and international codes of radiation safety by a group of international experts and in consultation with other international bodies. This edition presents the second revision. In response to the suggestion made by some Member States, the term 'radioisotopes' has been changed to 'radionuclides' in the title and, as appropriate, in the text because the term 'radionuclides' includes the radioactive element itself as well as the isotopes. The series of manuals and codes published in the Safety Series and the Technical Reports Series give more complete advice to the user on specialized topics.

  2. Development of a radioisotope heat source for the two-watt radioisotope thermoelectric generator

    Science.gov (United States)

    Howell, Edwin I.; McNeil, Dennis C.; Amos, Wayne R.

    1992-01-01

    Described is a radioisotope heat source for the Two-Watt Radioisotope Thermoelectric Generator (RTG) which is being considered for possible application by the U.S. Navy and for other Department of Defense applications. The heat source thermal energy (75 Wt) is produced from the alpha decay of plutonium-238 which is in the form of high-fired plutonium dioxide. The capsule is non-vented and consists of three domed cylindrical components each closed with a corresponding sealed end cap. Surrounding the fuel is the liner component, which is fabricated from a tantalum-based alloy, T-111. Also fabricated from T-111 is the next component, the strength member, which serves to meet pressure and impact criteria. The outermost component, or clad, is the oxidation- and corrosion-resistant nickel-based alloy, Hastelloy S. This paper defines the design considerations, details the hardware fabrication and welding processes, discusses the addition of yttrium to the fuel to reduce liner embrittlement, and describes the testing that has been conducted or is planned to assure that there is fuel containment not only during the heat source operational life, but also in case of an accident environment.

  3. Coated particle fuel for radioisotope power systems (RPSs) and radioisotope heater units (RHUs)

    Science.gov (United States)

    Sholtis, Joseph A.; Lipinski, Ronald J.; El-Genk, Mohamed S.

    1999-01-01

    Coated particle fuel offers great promise for advanced radioisotope power systems (RPSs) and radioisotope heater units (RHUs) being pursued for future U.S. solar system exploration missions. Potential benefits of this fuel include improved design flexibility and materials compatibility, enhanced safety and performance, and reduced specific mass and volume. This paper describes and discusses coated particle fuel, with emphasis on its applicability, attributes, and potential benefits to future RPSs and RHUs. Additionally, this paper identifies further analyses and verification testing that should be conducted before a commitment is made to fully develop this fuel. Efforts to date indicate there is every reason to believe that the potential benefits of coated particle fuel to future RPSs and RHUs can be demonstrated with a modest, phased analytical and verification test effort. Thus, developmental risk appears minimal, while the potential benefits are substantial. If coated particle fuel is pursued and ultimately developed successfully, it could revolutionize the design and space use of future RPSs and RHUs.

  4. Survey of literature on dispersion ratio and collection ratio of radioisotopes in animal study using radioisotopes

    International Nuclear Information System (INIS)

    A survey of literature in the title was performed to know the actual status of the dispersion from excretion and expiration studies of radioisotopes since, at present, the probable dispersion ratio is assumed to be 100% in calculation for legally permitted use of radioisotopes which conceivably being far from the real status and being incompatible with the guideline for pharmacokinetic studies requiring the recovery of >95% of dosed radioactivity in balance study. There are two interpretations for the dispersion; it is the expiration ratio and it is the fraction unrecovered. Survey was done on 11 Japanese and foreign journals in 1985-1996 publishing most of pharmacokinetic studies and on 650 compounds in 358 facilities with 1,975 experiments in total. In those experiments, the total recovery of radioactivity was 95% in average, unrecovered fraction, 5% and expiration ratio, 2%. As for unclide, 14C, 3H, 125I and 35S were surveyed since they occupied 99.4% of the experiments and their dispersion was <5%. Rats were used in 70% of the experiments and the dispersion in all animal experiments was about 5%. Administration route was regardless of the dispersion. (K.H.)

  5. Cesium and strontium in Black Sea macroalgae

    International Nuclear Information System (INIS)

    The trace level of metals and particularly radioactive ones should be monitored to evaluate the transfer along the trophic chain, assess the risk for biota and can be used for global changes assessment. Plants respond rapidly to all changes in the ecosystem conditions and are widely used as indicators and predictors for changes in hydrology and geology. In this work we represent our successful development and applications of a methodology for monitoring of stable and radioactive strontium and cesium in marine biota (Black Sea algae's). In case of radioactive release they are of high interest. We use ED-XRF, gamma spectrometers and LSC instrumentation and only 0.25 g sample. Obtained results are compared with those of other authors in same regions. The novelty is the connection between the radioactive isotopes and their stable elements in algae in time and space scale. All our samples were collected from Bulgarian Black Sea coast. - Highlights: • An extraction chromatography method for radiochemical separation of Sr and Cs. • Assessment of Sr and Cs accumulation capacity of six Black Sea macroalgae species. • Connection between the isotopes and their stable elements content in algae. • Assessment of Sr and Cs content in ecosystems along the Bulgarian coast

  6. Radioisotopic splenoportography in patients with portal hypertension

    Energy Technology Data Exchange (ETDEWEB)

    Samejima, Natsuki; Ikeda, Koichiro; Yokoyama, Yasuhiro; Hirata, Satoru

    1989-05-01

    Radio-isotopic splenoportography was performed by injecting /sup 99m/TcO/sub 4//sup -/into the spleens of 46 patients with portal hypertension and 14 patients with various disorders not having portal hypertension. No collateral circulation was demonstrated in the 14 patients without portal hypertension whereas some RI-images of portosystemic collaterals were found in 40 (87.0 per cent) of the 46 patients with portal hypertension. Collaterals were divided into an ascending group and a descending group, the appearance rate of ascending collaterals being 80.4 per cent and that of descending collaterals, 41.3 per cent. There were 3 image patterns in the ascending group, namely, an AZ-pattern in which the azygos vein was demonstrated; a SC-pattern in which the RI-bolus ascended along the esophagus to the neck and the subclavian vein; and an EG-pattern which showed stagnation of the RI-bolus in the esophagogastric region. There were 4 patterns in the descending group, namely; a pattern of gastro-renal caval shunt (GR-pattern); reverse flow patterns into the umbilical or paraumbilical veins (UV-pattern); into the superior mesenteric vein (SMV-pattern); and into the inferior mesenteric vein (IMV-pattern). The appearance of the EG-pattern was seen most frequently (74.4 per cent). The usefulness of this method for surveying the collateral circulation in portal hypertension, estimating the risk of esophageal variceal bleeding and evaluating its treatments, was suggested by the results of this study. (author).

  7. Radioisotopic splenoportography in patients with portal hypertension.

    Science.gov (United States)

    Samejima, N; Ikeda, K; Yokoyama, Y; Hirata, S

    1989-05-01

    Radio-isotopic splenoportography was performed by injecting 99mTcO4- into the spleens of 46 patients with portal hypertension and 14 patients with various disorders not having portal hypertension. No collateral circulation was demonstrated in the 14 patients without portal hypertension whereas some RI-images of portosystemic collaterals were found in 40 (87.0 per cent) of the 46 patients with portal hypertension. Collaterals were divided into an ascending group and a descending group, the appearance rate of ascending collaterals being 80.4 per cent and that of descending collaterals, 41.3 per cent. There were 3 image patterns in the ascending group, namely, an AZ-pattern in which the azygos vein was demonstrated; a SC-pattern in which the RI-bolus ascended along the esophagus to the neck and the subclavian vein; and an EG-pattern which showed stagnation of the RI-bolus in the esophagogastric region. There were 4 patterns in the descending group, namely; a pattern of gastro-renal caval shunt (GR-pattern); reverse flow patterns into the umbilical or paraumbilical veins (UV-pattern); into the superior mesenteric vein (SMV-pattern); and into the inferior mesenteric vein (IMV-pattern). The appearance of the EG-pattern was seen most frequently (74.4 per cent). The usefulness of this method for surveying the collateral circulation in portal hypertension, estimating the risk of esophageal variceal bleeding and evaluating its treatments, was suggested by the results of this study. PMID:2674500

  8. Radioisotopic splenoportography in patients with portal hypertension

    International Nuclear Information System (INIS)

    Radio-isotopic splenoportography was performed by injecting 99mTcO4-into the spleens of 46 patients with portal hypertension and 14 patients with various disorders not having portal hypertension. No collateral circulation was demonstrated in the 14 patients without portal hypertension whereas some RI-images of portosystemic collaterals were found in 40 (87.0 per cent) of the 46 patients with portal hypertension. Collaterals were divided into an ascending group and a descending group, the appearance rate of ascending collaterals being 80.4 per cent and that of descending collaterals, 41.3 per cent. There were 3 image patterns in the ascending group, namely, an AZ-pattern in which the azygos vein was demonstrated; a SC-pattern in which the RI-bolus ascended along the esophagus to the neck and the subclavian vein; and an EG-pattern which showed stagnation of the RI-bolus in the esophagogastric region. There were 4 patterns in the descending group, namely; a pattern of gastro-renal caval shunt (GR-pattern); reverse flow patterns into the umbilical or paraumbilical veins (UV-pattern); into the superior mesenteric vein (SMV-pattern); and into the inferior mesenteric vein (IMV-pattern). The appearance of the EG-pattern was seen most frequently (74.4 per cent). The usefulness of this method for surveying the collateral circulation in portal hypertension, estimating the risk of esophageal variceal bleeding and evaluating its treatments, was suggested by the results of this study. (author)

  9. Viscosity and crystallization mechanism of cesium loaded iron phosphate glasses

    Energy Technology Data Exchange (ETDEWEB)

    Joseph, Kitheri, E-mail: joskit@igcar.gov.in [Chemistry Group, IGCAR, Kalpakkam 603 102 (India); Kutty, K.V. Govindan [Chemistry Group, IGCAR, Kalpakkam 603 102 (India); Goswami, M.C. [National Metallurgical Laboratory, Jamshedpur 831 007 (India); Rao, P.R. Vasudeva [Chemistry Group, IGCAR, Kalpakkam 603 102 (India)

    2014-07-01

    Highlights: • Melt viscosity of cesium loaded iron phosphate glasses is measured and reported for the first time. • Viscosity – temperature followed Arrhenius model. • Activation energy of viscous flow is strongly correlated to glass transition temperature of the glasses. • Process of crystallization of cesium loaded glass by approximation-free kinetic method to understand the mechanism. • Cesium loaded IPG and IPG shows bulk crystallization mechanism. - Abstract: This paper describes the melt viscosity behaviour and the crystallization mechanism of a series of iron phosphate glasses. High temperature viscosity measurements were carried out on pristine iron phosphate glass and a series of cesium loaded iron phosphate glasses in order to understand the effect of addition of Cs{sub 2}O on viscosity of iron phosphate glasses. Activation energy of viscous flow was estimated from the experimental data by applying Arrhenius model of viscosity–temperature relationship. Activation energy of viscous flow is observed to be strongly correlated to glass transition temperature of these glasses. Fragility of iron phosphate and cesium loaded iron phosphate glass systems were also evaluated in region of high temperature. Crystallization of these glasses was studied using thermal analysis techniques. Temperature integral approximation free method was utilized to evaluate the kinetic parameters such as activation energy of crystallization (E{sub c}) and Avrami exponent (n). The value of Avrami exponent ‘n’ obtained showed that the glasses under present study crystallize via bulk crystallization mechanism, i.e., nucleation and three dimensional growth.

  10. Cesium corrosion process in Fe–Cr steel

    International Nuclear Information System (INIS)

    A cesium corrosion out-pile test was performed to Fe–Cr steel in a simulated fuel pin environment. In order to specify the corrosion products, the corroded area was analyzed by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). A cesium corrosion process in Fe–Cr steel was successfully developed proceeding from both experimental results and thermochemical consideration. The corroded area was mainly formed by Fe layer and Fe depleted oxidized layer. The Fe depleted oxidized layer was formed by Cr0.5Fe0.5 and Cr2O3. The presumed main corrosion reactions were 2Cr+2/3 O2→Cr2O3(ΔG650°C=-894.1kJ/mol) and Cr23C6+46Cs+46O2→23Cs2CrO4+6C(ΔG650°C=-25018.1kJ/mol). Factors of these reactions are chromium, carbon, oxygen and cesium. Therefore, cesium corrosion progression must be dependent on the chromium content, carbon content in the steel, the supply rate of oxygen and temperature which correlated with the diffusion rate of cesium and oxygen into the specimen

  11. Viscosity and crystallization mechanism of cesium loaded iron phosphate glasses

    International Nuclear Information System (INIS)

    Highlights: • Melt viscosity of cesium loaded iron phosphate glasses is measured and reported for the first time. • Viscosity – temperature followed Arrhenius model. • Activation energy of viscous flow is strongly correlated to glass transition temperature of the glasses. • Process of crystallization of cesium loaded glass by approximation-free kinetic method to understand the mechanism. • Cesium loaded IPG and IPG shows bulk crystallization mechanism. - Abstract: This paper describes the melt viscosity behaviour and the crystallization mechanism of a series of iron phosphate glasses. High temperature viscosity measurements were carried out on pristine iron phosphate glass and a series of cesium loaded iron phosphate glasses in order to understand the effect of addition of Cs2O on viscosity of iron phosphate glasses. Activation energy of viscous flow was estimated from the experimental data by applying Arrhenius model of viscosity–temperature relationship. Activation energy of viscous flow is observed to be strongly correlated to glass transition temperature of these glasses. Fragility of iron phosphate and cesium loaded iron phosphate glass systems were also evaluated in region of high temperature. Crystallization of these glasses was studied using thermal analysis techniques. Temperature integral approximation free method was utilized to evaluate the kinetic parameters such as activation energy of crystallization (Ec) and Avrami exponent (n). The value of Avrami exponent ‘n’ obtained showed that the glasses under present study crystallize via bulk crystallization mechanism, i.e., nucleation and three dimensional growth

  12. The diffusion of cesium, strontium, and europium in silicon carbide

    Science.gov (United States)

    Dwaraknath, S. S.; Was, G. S.

    2016-08-01

    A novel multi-layer diffusion couple was used to isolate the diffusion of strontium, europium and cesium in SiC without introducing radiation damage to SiC and at concentrations below the solubility limit for the fission products in SiC. Diffusion occurred by both bulk and grain boundary pathways for all three fission products between 900∘ C and 1 ,300∘ C. Cesium was the fastest diffuser below 1 ,100∘ C and the slowest above this temperature. Strontium and europium diffusion tracked very closely as a function of temperature for both bulk and grain boundary diffusion. Migration energies ranged from 1.0 eV to 5.7 eV for bulk diffusion and between 2.2 eV and 4.7 eV for grain boundary diffusion. These constitute the first measurements of diffusion of cesium, europium, and strontium in silicon carbide, and the magnitude of the cesium diffusion coefficient supports the premise that high quality TRISO fuel should have minimal cesium release.

  13. Studies on the production and application of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Han, Hyon Soo; Park, K. B.; Kim, J. R.; Yoon, B. M.; Bang, H. S.; Shin, B. C.; Cho, W. K.; Park, U. J.; Park, C. D.; Lee, Y. G.; Suh, C. H.; Shin, H. Y.; Kim, D. S.; Hong, S. B.; Jun, S. S.; Min, E. S.; Jang, K. D.; Kim, J. K.; Kim, S. J.; Yang, S. Y.; Yang, S. H.; Chun, K. J.; Kang, H. Y.; Suh, K. S.; Goo, J. H.; Chung, S. H.; Lee, J. C.; Choi, J. L.; Lee, H. Y.; Bang, K. S.

    1997-09-01

    To produce radioisotopes utilizing the research reactor `HANARO`, development of RI production process, target fabrication, preparation of devices and tools for RI process, preparation of production facility for radiopharmaceuticals, test production for the established process, etc. have been carried out, respectively. Production processes for various kinds of radionuclides were developed and the settled methods were applied to test production using `HANARO`. The results of developed process are as follows: (1) I-131 dry distillation method. (2) Large scale production of Ir-192 sources (3) P-32 production process by distillation under reduced pressure (4) Cr-51 production process using enriched target. To irradiate the target for RI production in `HANARO`, target for neutron irradiation, loading/unloading devices, working table in service pool, remote handling tools, shield cask for irradiated target transfer, etc. were designed and fabricated. The function test of prepared targets and the safety analysis of shielding casks were carried out. License for practical use of the prepared casks were obtained from Ministry of Science and Technology. For production of medical radioisotopes, their production facilities were designed in detail and were installed in RIPF (Radioisotope Production Facility), with full reflection of the basic concept of the good manufacturing practice for radiopharmaceuticals. The constructed GMP facilities have started to be operated after authorization since Jun., 1997. Results of this study will be applied to mass production of radioisotopes in `HANARO` and are to contribute the advance of domestic medicine and industry related to radioisotopes. (author). 7 refs., 7 tabs., 4 figs.

  14. Outlook on radioisotope production at TRIGA SSR 14 MW reactor

    International Nuclear Information System (INIS)

    INR Pitesti, endowed with a research nuclear reactor of TRIGA SSR 14 MW type, has developed activities of radioisotope production, being at present licensed for production and selling Ir-192 sources for industrial gamma radiography and Co-60 sources (2,000 Ci) for medical uses (cobalto therapy). A collaboration was initiated with the CPR Department of IFIN-HH Bucharest, particularly after the WWR-S reactor shutdown on December 21, 1997. In the frame of this program the INR Pitesti offers services of raw material irradiations followed by the radioisotope production performed subsequently at the Radioisotope Production Department (CPR) of IFIN-HH Bucharest which also deals with selling the product on internal market . The experimental facilities with the two TRIGA reactors (TRIGA SSR 14 MW and TRIGA ACPR) of INR Pitesti are described. The maximum neutron flux is 2.9 · 1014 n/cm2s. The irradiation channels are of two neutron spectra types. Also the neutron flux is characterized by radial and axial distribution which are taken into account when a given raw material is to be irradiated, to avoid perturbing non-homogeneities in the raw material activation. Five irradiation devices are presented. Preparations are currently under way for production of fission radioisotopes Mo-99, I-131 and Xe-133 and activation radioisotope I-125 for medical application

  15. Dissociative excitation of cesium atom upon e-CsOH collisions

    International Nuclear Information System (INIS)

    The process of dissociative excitation of cesium atom in collisions with mono-kinetic molecules of cesium hydroxide is studied. It is established that behaviour of dissociative excitations the cesium atom in spectral series corresponds of to the grade dependence of cross sections on the main quantum number of the upper level. The values of constants, characterizing the behaviour of cross sections in the eight spectral series of the cesium atom are determined

  16. Controllable evaporation of cesium from a dispenser oven

    Science.gov (United States)

    Fantz, U.; Friedl, R.; Fröschle, M.

    2012-12-01

    This instrument allows controlled evaporation of the alkali metal cesium over a wide range of evaporation rates. The oven has three unique features. The first is an alkali metal reservoir that uses a dispenser as a cesium source. The heating current of the dispenser controls the evaporation rate allowing generation of an adjustable and stable flow of pure cesium. The second is a blocking valve, which is fully metallic as is the body of the oven. This construction both reduces contamination of the dispenser and enables the oven to be operated up to 300 °C, with only small temperature variations (metal at a cold spot is significantly hindered. The last feature is an integral surface ionization detector for measuring and controlling the evaporation rate. The dispenser oven can be easily transferred to the other alkali-metals.

  17. Dating of mine waste in lacustrine sediments using cesium-137

    Science.gov (United States)

    Rember, W. C.; Erdman, T. W.; Hoffmann, M. L.; Chamberlain, V. E.; Sprenke, K. F.

    1993-11-01

    For over a century Medicine Lake in northern Idaho has received heavy-metal-laden tailings from the Coeur d'Alene mining district. Establishing the depositional chronology of the lake bottom sediments provides information on the source and rate of deposition of the tailings. Cesium-137, an isotope produced in the atmosphere by nuclear bomb tests, was virtually absent in the environment prior to 1951, but reached its apex in 1964. Our analysis of cesium-137 in the sediments of Medicine Lake revealed that 14 cm of fine-grained tailings were deposited in the lake from 1951 to 1964 and tailing deposition downstream was greatly reduced by the installation of tailings dams in the district in 1968. Cesium-137 analysis is accomplished by a fairly simple gamma-ray counting technique and should be a valuable tool for analyzing sedimentation in any lacustrine environment that was active during the 1950s and 1960s.

  18. Cesium 137 in oils and plants from Guatemala

    International Nuclear Information System (INIS)

    Since 1990 the project of radioactive and environmental contamination started in Guatemala. Studies about the radioactive contamination levels are made within the framework of this project. Cesium-137 has been an interest radionuclide, because it is a fission product released to the environment by the use of nuclear weapons and nuclear power plants accidents. The sampling consisted in collection of soil and grass in 20 provinces of Guatemala, one point by province, and it was made in 1990. The cesium-137 concentration in the samples, was determined by gamma spectrometry, using an hyper pure germanium detector. The results show the presence of radioactive contamination in soil and grass due to cesium-137, at levels that might be considered as normal. The levels found are not harmful for human health, and its importance is the fact that can be used as reference levels for the environmental radioactivity monitoring in Guatemala

  19. Study of radiatively sustained cesium plasmas for solar energy conversion

    Science.gov (United States)

    Palmer, A. J.; Dunning, G. J.

    1980-01-01

    The results of a study aimed at developing a high temperature solar electric converter are reported. The converter concept is based on the use of an alkali plasma to serve as both an efficient high temperature collector of solar radiation as well as the working fluid for a high temperature working cycle. The working cycle is a simple magnetohydrodynamic (MHD) Rankine cycle employing a solid electrode Faraday MHD channel. Research milestones include the construction of a theoretical model for coupling sunlight in a cesium plasma and the experimental demonstration of cesium plasma heating with a solar simulator in excellent agreement with the theory. Analysis of a solar MHD working cycle in which excimer laser power rather than electric power is extracted is also presented. The analysis predicts a positive gain coefficient on the cesium-xenon excimer laser transition.

  20. Investigation of Miniaturized Radioisotope Thermionic Power Generation for General Use

    Science.gov (United States)

    Duzik, Adam J.; Choi, Sang H.

    2016-01-01

    Radioisotope thermoelectric generators (RTGs) running off the radioisotope Pu238 are the current standard in deep space probe power supplies. While reliable, these generators are very inefficient, operating at only approx.7% efficiency. As an alternative, more efficient radioisotope thermionic emission generators (RTIGs) are being explored. Like RTGs, current RTIGs concepts use exotic materials for the emitter, limiting applicability to space and other niche applications. The high demand for long-lasting mobile power sources would be satisfied if RTIGs could be produced inexpensively. This work focuses on exposing several common materials, such as Al, stainless steel, W, Si, and Cu, to elevated temperatures under vacuum to determine the efficiency of each material as inexpensive replacements for thermoelectric materials.

  1. Hair radioactivity as a measure of exposure to radioisotopes

    Science.gov (United States)

    Strain, W. H.; Pories, W. J.; Fratianne, R. B.; Flynn, A.

    1972-01-01

    Since many radioisotopes accumulate in hair, this tropism was investigated by comparing the radioactivity of shaved with plucked hair collected from rats at various time intervals up to 24 hrs after intravenous injection of the ecologically important radioisotopes, iodine-131, manganese-54, strontium-85, and zinc-65. The plucked hair includes the hair follicles where biochemical transformations are taking place. The data indicate a slight surge of each radioisotpe into the hair immediately after injection, a variation of content of each radionuclide in the hair, and a greater accumulation of radioactivity in plucked than in shaved hair. These results have application not only to hair as a measure of exposure to radioisotopes, but also to tissue damage and repair at the hair follicle.

  2. Application of radioisotopes to studies of crystal imperfections

    International Nuclear Information System (INIS)

    Radioisotopes have been used in two important ways in studying imperfections in alkali halide crystals. The zone refining of the compounds has been monitored by addition of tracers, and segregation coefficients have been determined from such measurements. The other application has been to insert small concentrations of impurity ions into alkali halides in order to study the phonon scattering by such impurities or by the vacancies they introduce; these measurements are carried out at very low temperatures where the phonon mean free path is limited by lattice imperfections. The most commonly used radioisotope in this work has been Ca45. This work is reviewed and some current and possible future applications of radioisotopes in this field are mentioned. (author)

  3. Determination of the radiological impact of radioisotope waste disposal

    International Nuclear Information System (INIS)

    The Atomic Energy Control Board (AECB) controls the uses of radioisotopes and the management of wastes resulting from radioisotope use through licences. In most cases, wastes generated through the use of radioisotopes are required by licence condition to be sent to Chalk River Nuclear Laboratories for storage but if the amounts of radioisotope are very small, have a low activity or a very short half-life, the radioisotope is permitted to be released to regular waste management systems. The AECB commissioned this study to determine the doses to individuals working in municipal waste management systems and to populations of cities where small amounts of radioisotopes are disposed of through the municipal waste managment systems. The Hamilton-Burlington area surrounding Hamilton Harbour was selected as the study area. The pathways and dosimetry models were put into a computer spread sheet, to give the model flexibility so that it could be easily modified to model other cities. Within the occupational critical group, the maximum doses were calculated for the Hamilton sewage treatment plant aeration worker at 1.2E-6 Sv/a. If this individual were also a member of the critical group in the general population, the maximum dose would be 2.0E-6 Sv/a. Individual doses to the critical group within the general population were calculated as 7.7E-7 Sv/a for adults and 6.8E-8 Sv/a for infants. These compare to AECB regulatory limits of 5.0E-2 Sv/a per person for atomic radiation workers and 5.0E-3 Sv/a per person for the general public. The collective population dose for the study area was 1.37E-1 person-Sv/a or an average dose of 2.6E-7 Sv/a per person for the 525,000 population

  4. Solid targets for production of radioisotopes with cyclotron

    International Nuclear Information System (INIS)

    The design of targets for production of radioisotopes and radiopharmaceuticals of cyclotron to medical applications requires a detailed analysis of several variables such as: cyclotron operation conditions, choice of used materials as target and their physicochemical characteristics, activity calculation, the yielding of each radioisotope by irradiation, the competition of nuclear reactions in function of the projectiles energy and the collision processes amongst others. The objective of this work is to determine the equations for the calculation for yielding of solid targets at the end of the proton irradiation. (Author)

  5. Results with radioisotope techniques in veterinary science in Hungary

    International Nuclear Information System (INIS)

    Radioisotopes have been applied to veterinary science in Hungary since the fifties. A short chronologic review on the development of isotope technology is given emphasizing the possibilities offered by the application of closed and open radiation sources, of instrumental neutron activation analysis and atomic absorption spectroscopy, and in vitro nuclear procedures which include competitive protein-binding analysis and radioimmunoassay. The progesterone test, applicable to diagnose the pregnancy of cattles, is carried out generally by RIA. Radioisotopic methods are applied also to determine the thyroid function of cattles, swines and domestic fowls. (V.N.)

  6. KAERI charged particle cross section library for radioisotope production

    CERN Document Server

    Chang, J H; Kim, D H; Lee, Y O; Zhuang, Y X

    2001-01-01

    This report summarized information and figures describing the 'KAERI Charged Particle Cross Section Library for Radioisotope production' The library contains proton-, deutron-, He-3-, and alpha-induced monitor cross sections, and gamma- and positron-emitter production cross sections. Experimental data and evaluation methods are described, and the evaluated cross sections are compared with those of the IAEA, MENDL, and LA150. The library has cross sections and emission spectra suitable for the transport analysis in the design of radioisotope production system, and are available at http://atom.kaeri.re.kr/ in ENDF-6 format.

  7. Procurement of a fully licensed radioisotope thermoelectric generator transportation system

    Science.gov (United States)

    Adkins, Harold E.; Bearden, Thomas E.

    1991-01-01

    A fully licensed transportation system for Radioisotope Thermoelectric Generators and Light-Weight Radioisotope Heater Units is currently being designed and built. The system will comply with all applicable U.S. Department of Transportation regulations without the use of a ``DOE Alternative.'' The U.S. Department of Transportation has special ``double containment'' requirements for plutonium. The system packaging uses a doubly contained ``bell jar'' concept. A refrigerated trailer is used for cooling the high-heat payloads. The same packaging is used for both high- and low-heat payloads. The system is scheduled to be available for use by mid-1992.

  8. Ablation response testing of simulated radioisotope power supplies

    Science.gov (United States)

    Lutz, Steven A.; Chan, Chris C.

    1994-05-01

    Results of an experimental program to assess the aerothermal ablation response of simulated radioisotope power supplies are presented. Full-scale general purpose heat source, graphite impact shell, and lightweight radioisotope heater unit test articles are all tested without nuclear fuel in simulated reentry environments. Convective stagnation heating, stagnation pressure, stagnation surface temperature, surface recession profile, and weight loss measurements are obtained for diffusion-limited and sublimation ablation conditions. The recession profile and weight loss measurements show an effect of surface features on the stagnation face. The surface features alter the local heating which in turn affects the local ablation.

  9. The application of radioisotopes in the Argentine technology

    International Nuclear Information System (INIS)

    The different applications of radioisotopes: as sealed sources or tracers, as well as activation analysis have cast a new light on Argentine engineering and industry. The Argentine Atomic Energy Commission is carrying out an active plan for the developement and promotion of these techniques since the 60's. This report describes and analyzes the most outstanding applications, and brings up to date other previous papers on the same subject. It suggests some ideas for achieving a complete penetration of radioisotope techniques into Argentine technology. It also outlines some future perspectives, based on present statistical data. (author)

  10. Synthesis and characterization of radioisotope nanospheres containing two gamma emitters.

    Science.gov (United States)

    Jung, Jin-Hyuck; Jung, Sung-Hee; Kim, Sang-Ho; Choi, Seong-Ho

    2012-12-01

    Silica-coated gold-silver alloy nanospheres prepared by Stöber's method were irradiated in a nuclear reactor to prepare radioisotope nanospheres for use as radiotracers. The radioisotope nanospheres included two gamma nuclides: (i) Au-198, emitting major photons with 0.412 MeV and (ii) Ag-108, emitting photons with 0.434 and 0.633 MeV. The nanospheres shell and core diameters were 100-112 nm and 20-50 nm, respectively, depending on their preparation. The gamma-emitting nanospheres could be used as tracers in high-temperature petrochemical and refinery processes in which conventional organic radioactive labels will decompose.

  11. An Integrated Hydrologic Modeling Approach to Cesium-137 Transport in Forested Fukushima Watersheds

    Science.gov (United States)

    Siirila-Woodburn, E. R.; Steefel, C. I.; Williams, K. H.; Birkholzer, J. T.

    2015-12-01

    The 2011 Fukushima Daiichi Nuclear Power Plant (FDNPP) accident in Japan resulted in a significant dissemination of cesium-137 (Cs-137) over a wide area west of the plant, including the contamination of many watersheds and the subsequent evacuation of many communities. Today approximately 90% of on-land Cs-137 fallout following the accident resides in the upper 5 cm of forest soils. While this can be partially attributed to the forested composition of the prefecture (70%), there is also difficulty in cleanup efforts in these regions due to a lack of understanding and predictive capability of radioisotopes transport at the catchment to watershed scale. Subsequently, there is an uncertain, but likely long-term impact on local communities with implications for the use of nuclear energy use worldwide. Due to the complex nature of forest eco-hydrology, sophisticated modeling tools to accurately predict Cs-137 fluxes across different spatial and temporal scales are required. High fidelity, high resolution numerical modeling techniques in conjunction with parallel high performance computing is required to accurately determine transport and feedbacks in these complex systems. To better understand the fundamental transport of Cs-137, a watershed near the FDNPP is modeled with an integrated hydrologic model that includes variably saturated groundwater and overland flow in addition to atmospheric and vegetative processes via a coupled land surface model. Of specific interest is the impact of land cover type on hydrologic flow in the area, which will likely play an important role in erosion patterns and the consequent transport of Cs-137 strongly sorbed to surface soils. Risk management practices (for example, passive remediation versus active remediation such as targeted logging) for two principal tree types (evergreen and deciduous) are informed given the simulated responses to flow patterns assuming different quantities and spatial distribution patterns of each tree type.

  12. Remote control: Decommissioning RTGs [radioisotope theromelectric generators

    International Nuclear Information System (INIS)

    Several hundred radioisotope thermoelectric generators (RTGs) are deployed along the Russian Federation's Arctic coast to power remote lighthouses and navigation beacons. Similar RTGs were also used as power sources in other remote locations in the Russian Federation and elsewhere in the former Soviet Union. All Russian RTG's have out-lived their lifespan and are in need of decommissioning. The RTGs typically contain one or more radionuclide heat sources (RHS) each with an activity of thousands of TBq of strontium-90. This means that they are Category 1 sources as defined in the IAEA international 'Code of Conduct on the Safety and Security of Radioactive Sources'. According to the Federal Atomic Energy Agency of the Russian Federation (Rosatom), there are 651 RTGs at various locations in the Russian Federation which are subject to decommissioning or replacement with alternative sources of energy. The Norwegian Government has played a significant role in international efforts, fully cooperating with Russian authorities to safely decommission RTGs and provide alternative power sources. Norway has actively supported improvement of nuclear safety and security in northwest Russia for more then ten years. Over this period, the Norwegian Government has spent approximately $150 million on a variety of industrial projects, including specific improvements in radioactive waste treatment and storage, physical security, and infrastructure support. The national authority, the Norwegian Radiation Protection Authority (NRPA), takes an active part advising the Government regarding prioritization and quality assurance of all these activities. In addition, the Plan of Action places great emphasis on adequate regulatory supervision. Accordingly, the NRPA programme includes a variety of regulatory support projects. These are designed to assist the Russian authorities in ensuring that work is properly carried out within the framework of Russian law, taking into account international

  13. Sorption of cesium in young till soils

    Energy Technology Data Exchange (ETDEWEB)

    Lusa, Merja; Lempinen, Janne; Ahola, Hanna; Soederlund, Mervi; Lehto, Jukka [Helsinki Univ. (Finland). Laboratory of Radiochemistry; Lahdenperae, Anne-Maj [Saanio and Riekkola Oy, Consulting Engineers, Helsinki (Finland); Ikonen, Ari T.K. [Posiva Oy, Eurajoki (Finland)

    2014-10-01

    Soil samples from three forest soil pits were examined down to a depth of approximately three metres using 1 M ammonium acetate extraction and microwave-assisted extraction with concentrated nitric acid (HNO{sub 3}), to study the binding of cesium (Cs) at Olkiluoto Island, southern Finland. Ammonium acetate was used to extract the readily exchangeable Cs fractions roughly representing the Cs fraction in soil which is available for plants. Microwave-assisted HNO{sub 3} extraction dissolves various minerals, e.g. carbonates, most sulphides, arsenides, selenides, phosphates, molybdates, sulphates, iron (Fe) and manganese (Mn) oxides and some silicates (olivine, biotite, zeolite), and reflects the total Cs concentrations. Cs was mostly found in the strongly bound fraction obtained through HNO{sub 3} extraction. The average Cs concentrations found in this fraction were 3.53 ± 0.30 mg/kg (d.w.), 3.06 ± 1.86 mg/kg (d.w.) and 1.83 ± 0.42 mg/kg (d.w.) in the three soil pits, respectively. The average exchangeable Cs found in the ammonium acetate extraction in all three sampling pits was 0.015 ± 0.008 mg/kg (d.w.). In addition, Cs concentrations in the soil solution were determined and in situ distribution coefficients (K{sub d}) for Cs were calculated. Furthermore, the in situ K{sub d} data was compared with the Cs K{sub d} data obtained using the model batch experiments. The in situ K{sub d} values were observed to fairly well follow the trend of batch sorption data with respect to soil depth, but on average the batch distribution coefficients were almost an order of magnitude higher than the in situ K{sub d} data. In situ Cs sorption data could be satisfactory fitted with the Langmuir sorption isotherm, but the Freundlich isotherm failed to fit the data. Finally, distribution coefficients were calculated by an ion exchange approach using soil solution data, the cation exchange capacity (CEC) as well as Cs to sodium (Na) and Cs to potassium (K) ion exchange selectivity

  14. Spallation production of neutron deficient radioisotopes in North America

    Energy Technology Data Exchange (ETDEWEB)

    Jamriska, D.J.; Peterson, E.J. [Los Alamos National Laboratory, Los Alamos, NM (United States); Carty, J. [US Department of Energy, Office of Isotope Production and Distribution, Germantown, MD (United States)

    1997-10-01

    The United States Department of Energy produces a number of neutron deficient radioisotopes by high energy proton induced spallation reactions in accelerators at Los Alamos National Laboratory in New Mexico and Brookhaven National Laboratory in New York. Research isotopes are also recovered from targets irradiated at TRIUMF in British Columbia, Canada. The radioisotopes recovered are distributed for use in nuclear medicine, environmental research, physics research, and industry worldwide. In addition to the main product line of Sr-82 from either Mo or Rb targets, Cu-67 from ZnO targets, and Ge-68 from RbBr targets, these irradiation facilities also produce some unique isotopes in quantities not available from any other source such as Be-10, Al-26, Mg-28, Si-32, El-44, Fe-52, Gd-248, and Hg-194. We will describe the accelerator irradiation facilities at the Los Alamos and Brookhaven National Laboratories. The high level radiochemical processing facilities at Los Alamos and brief chemical processes from Los Alamos and Brookhaven will be described. Chemical separation techniques have been developed to recover the radioisotopes of interest in both high radiochemical purity and yield and at the same time trying to reduce or eliminate the generation of mixed waste. nearly 75 neutron deficient radioisotopes produced in spallation targets have been produced and distributed to researchers around the world since the inception of the program in 1974

  15. Radioisotope Production Plan and Strategy of Kijang Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kye Hong; Lee, Jun Sig [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    This reactor will be located at Kijang, Busan, Korea and be dedicated to produce mainly medical radioisotopes. Tc-99m is very important isotope for diagnosis and more than 80% of radiation diagnostic procedures in nuclear medicine depend on this isotope. There were, however, several times of insecure production of Mo-99 due to the shutdown of major production reactors worldwide. OECD/NEA is leading member countries to resolve the shortage of this isotope and trying to secure the international market of Mo-99. The radioisotope plan and strategy of Kijang Research Reactor (KJRR) should be carefully established to fit not only the domestic but also international demand on Mo-99. The implementation strategy of 6 principles of HLG-MR should be established that is appropriate to national environments. Ministry of Science, ICT and Future Planning and Ministry of Health and welfare should cooperate well to organize the national radioisotope supply structure, to set up the reasonable and competitive pricing of radioisotopes, and to cope with the international supply strategy.

  16. Radioisotope techniques for the study of protein turnover

    International Nuclear Information System (INIS)

    Before the era of isotope-labelled proteins, investigations of protein metabolism were largely based on nitrogen balance studies. They were widely applied in both animal experiments and clinical investigations. In 1959, researchers began using isotope-labelled proteins to study protein metabolism. Examples of radioisotope techniques for the study of protein metabolism are examined in this paper. 7 figs, 1 tab

  17. Radioisotope study of Eustachian tube. A preliminary report

    Energy Technology Data Exchange (ETDEWEB)

    De Rossi, G.; Campioni, P.; Vaccaro, A.

    1988-08-01

    Radioisotope studies of Eustachian tube are suggested in the preoperative phase of tympanoplasty, in order to assess tubal drainage and secretion. The use of gamma camera fitted to a computer allowed the AA, to calculate some semi-quantitative parameters for an exact assessment of the radioactivity transit from the tympanic cass up to the pharyngeal cavity, throughout the Eustachian tube.

  18. Optimization of water treatment facility by using radioisotope tracer

    Energy Technology Data Exchange (ETDEWEB)

    Jin, J. H.; Lee, M. J.; Jung, S. H.

    1997-01-01

    In order to get the optimization of conventional water treatment facility, radioisotope tracer technique was applied. It is desirable to set the baffles inside of mixing basin for the enhancement of mixing effect. It was appeared that most of flocs were settled down within 60 - 70 % of total length of sedimentation basin even with high flow rate. (author). 2 tabs., 32 figs.

  19. Future Supply of Medical Radioisotopes for the UK Report 2014

    CERN Document Server

    Neilly, Brian; Ballinger, Jim; Buscombe, John; Clarke, Rob; Ellis, Beverley; Flux, Glenn; Fraser, Louise; Hall, Adrian; Owen, Hywel; Paterson, Audrey; Perkins, Alan; Scarsbrook, Andrew

    2015-01-01

    The UK has no research nuclear reactors and relies on the importation of 99Mo and other medical radioisotopes (e.g. Iodine-131) from overseas (excluding PET radioisotopes). The UK is therefore vulnerable not only to global shortages, but to problems with shipping and importation of the products. In this context Professor Erika Denton UK national Clinical Director for Diagnostics requested that the British Nuclear Medicine Society lead a working group with stakeholders including representatives from the Science & Technology Facilities Council (STFC) to prepare a report. The group had a first meeting on 10 April 2013 followed by a working group meeting with presentations on 9th September 2013 where the scope of the work required to produce a report was agreed. The objectives of the report are: to describe the status of the use of medical radioisotopes in the UK; to anticipate the potential impact of shortages for the UK; to assess potential alternative avenues of medical radioisotope production for the UK m...

  20. States and future trends of the studies of radioisotopic batteries

    International Nuclear Information System (INIS)

    The history and current situation of radioisotopic batteries are reviewed, with the emphasis on the introduction of various power-generation mechanisms by nuclear decay energy. The newly developed theories and the new progress are presented. More than that, an insight is given into the prospect and future direction of this field

  1. Basic principles and developments of the radioisotope powered voltaic batteries

    International Nuclear Information System (INIS)

    The basic principles and some kinds of voltaic effect type radioisotope batteries are reviewed. This paper is focused on the micro-batteries based on radio-voltaic effect, which are widely used in micro-electromechanical systems (MEMs) and cardiac pacemakers. The prospects of such radio-voltaic isotope batteries are also reported. (authors)

  2. The use of radioisotopes for determination of complex equilibria

    International Nuclear Information System (INIS)

    Radioisotopes can be used for determination of complex equilibria in solution, provided this solution is in equilibrium with another phase. The most versatile systems for studying aqueous solutions use solvent-extraction and ion-exchange methods. These two methods more seen be to universally practical for determining complex equilibria than EMF, spectrophotometric and other more conventional ones. (author)

  3. Cesium-137 Levels Detected in Otters from Austria

    Directory of Open Access Journals (Sweden)

    Gutleb A.C.

    1991-02-01

    Full Text Available Pollution seems to be one of the most important causes for the decline of the European otter (Lutra lutra. The accident in the Chernobyl nuclear power plant added another aspect to environmental pollution. Few data on cesium-137 contents in otters are available, so levels were measured in 3 otters from Austria. All levels found were very low.

  4. Membrane-based separation technologies for cesium, strontium, and technetium

    Energy Technology Data Exchange (ETDEWEB)

    Kafka, T.

    1996-10-01

    This work is one of two parallel projects that are part of an ESP task to develop high-capacity, selective, solid extractants for cesium, strontium, and technetium from nuclear wastes. In this subtask, Pacific Northwest National Laboratory (PNNL) is collaborating with 3M, St. Paul, Minnesota, working in cooperation with IBC Advanced Technologies, American Fork, Utah.

  5. Cesium Ion Exchange Using Tank 241-AN-104 Supernate

    International Nuclear Information System (INIS)

    The River Protection Project is to design and build a high level nuclear waste treatment facility. The waste treatment plant is to process millions of gallons of radioactive waste stored in tanks at the Hanford Site. The high level nuclear waste treatment process includes various unit operations, such as ultrafiltration, precipitation, evaporation, ion exchange, and vitrification. Ion exchange is identified as the optimal treatment method for removal of cesium-137 and Tc-99 from the waste. Extensive ion exchange testing was performed using small-scale columns with actual waste samples. The objectives of this study were to: demonstrate SuperLig 644 ion exchange performance and process steps for the removal of cesium from actual AN-104 tank waste; pretreat actual AN-104 tank waste to reduce the concentration of cesium-137 in the waste below LAW vitrification limit; produce and characterize cesium eluate solutions for use in eluate evaporation tests. The experiments consisted of batch contact and small-scale column tests. The batch contact tests measured sorption partition coefficients Kds. The Kds were used to predict the effective resin capacity. The small-scale column tests, which closely mimic plant conditions, generated loading and elution profile data used to determine whether removal targets and design requirements were met

  6. Discovery of Cesium, Lanthanum, Praseodymium and Promethium Isotopes

    OpenAIRE

    May, E.; Thoennessen, M

    2011-01-01

    Currently, forty-one cesium, thirty-five lanthanum, thirty-two praseodymium, and thirty-one promethium, isotopes have been observed and the discovery of these isotopes is discussed here. For each isotope a brief synopsis of the first refereed publication, including the production and identification method, is presented.

  7. Strontium-90 and cesium-137 in fresh water

    International Nuclear Information System (INIS)

    Japan Chemical Analysis Center has analysed the strontium-90 and Cesium-137 contents in fresh water from 7 prefectures in Japan by the commission of Science and Technology Agency of Japanese Government. The method described in ''Radioactivity Survey Data in Japan No. 43 (NIRS-RSD-43, 1977) was applied to the analysis of these two radionuclides in samples. (author)

  8. Control of radioisotopes and radiation sources in Indonesia

    International Nuclear Information System (INIS)

    Radioisotopes and radiation sources are extensively used in Indonesia in medicine, industry, mining, agriculture and research. These materials are controlled by the regulatory authority, according to established legal procedures. The Nuclear Energy Control Board of Indonesia (BAPETEN), which was established in 1998 through the Nuclear Energy Act No. 10/1997, is entrusted with the control of any application of nuclear energy, including the application of radioisotopes and radiation sources, through regulation, licensing and inspection. The control is aimed to assure welfare, security and peace, the safety and health of workers and the public, and environmental protection. The number of licences issued to date is around 2400, consisting of 1600 licences for radioisotopes and radiation sources used in hospitals, 347 in radiography, 256 in industry, 53 in mining, and the rest in many other areas such as research and agriculture. A licence can cover one or more radioisotopes or radiation sources, depending on the location of the user institution. These radioisotopes and radiation sources are Co-60, Cs-137, Ir-192, Ra-226, Am-241, Sr-90, Kr-85, Pm-147, linear accelerator and X-ray, and short half-life radioisotopes such as I-125, I-131 and Tc-99m. There are 10 LINACs, 27 X-ray medicines, 61 radioisotope devices for Co-60 and Cs-137, and 10 mHDR Ir-192 for therapeutic purposes currently used in Indonesia and some Ra-226 in storage. Any activity related to the application of nuclear energy is required to be conducted in a manner which observes safety and security. According to the legal requirements, each user has to employ at least one radiation safety officer. To improve the control of the application of radiation sources and radioactive material in the country, BAPETEN introduced some new approaches to the users, including regular dialogues with radiation safety officers and the management of the users, requalification for radiation protection officers twice in five

  9. Applications of radioisotopes in industry and healthcare in Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Dien, N.N.; Quang, N.H. [Nucealr Research Institute, Dalat, (Viet Nam)

    1997-10-01

    Nowadays, in Vietnam radioisotopes have been used very widely in various socio-economic branches, especially in industry and healthcare. Applications of radioisotopes have significant meaning in economic development, people health protection, as well as in scientific research. In this paper, the present status and main applications of radiation and radioactive isotopes in industry and healthcare in Vietnam are reported. In order to control and monitor industrial processes, nucleonic control systems and radioactive tracer techniques have been utilized. Actually, sealed source applications are popular in Vietnam industry. A number of nuclear control devices and gauges have been used in the various industrial factories, such as liquid level gauges in steel industry, cement and beverage factories; density and moisture gauges in paper industry, etc. Tracer technique and sealed source applications have also been utilized in industrial production plants and in trouble-shooting in the petroleum industry. For medicine purposes, two departments of nuclear medicine were primarily established at the beginning of the 1970s. At the present time, a number of nuclear medicine departments have been set up and they have been equipped with advanced equipment. Main activities are focused on thyroid function studies, nuclear cardiology, brain scans, gastrointestinal studies, bone scans, etc. Since march 1984 Dalat nuclear research reactor of nominal power of 500 kW has been reconstructed and put into operation. This reactor is unique in Vietnam and has become an important scientific tool for development of nuclear techniques and radioisotope applications for socio-economic progress. Thanks to this important scientific tool, a variety of radioisotopes for medicine and industry applications as well as for scientific research has been produced. Utilization of the Dalat research reactor for radioisotope production is also summarized in this paper

  10. Applications of radioisotopes in industry and healthcare in Vietnam

    International Nuclear Information System (INIS)

    Nowadays, in Vietnam radioisotopes have been used very widely in various socio-economic branches, especially in industry and healthcare. Applications of radioisotopes have significant meaning in economic development, people health protection, as well as in scientific research. In this paper, the present status and main applications of radiation and radioactive isotopes in industry and healthcare in Vietnam are reported. In order to control and monitor industrial processes, nucleonic control systems and radioactive tracer techniques have been utilized. Actually, sealed source applications are popular in Vietnam industry. A number of nuclear control devices and gauges have been used in the various industrial factories, such as liquid level gauges in steel industry, cement and beverage factories; density and moisture gauges in paper industry, etc. Tracer technique and sealed source applications have also been utilized in industrial production plants and in trouble-shooting in the petroleum industry. For medicine purposes, two departments of nuclear medicine were primarily established at the beginning of the 1970s. At the present time, a number of nuclear medicine departments have been set up and they have been equipped with advanced equipment. Main activities are focused on thyroid function studies, nuclear cardiology, brain scans, gastrointestinal studies, bone scans, etc. Since march 1984 Dalat nuclear research reactor of nominal power of 500 kW has been reconstructed and put into operation. This reactor is unique in Vietnam and has become an important scientific tool for development of nuclear techniques and radioisotope applications for socio-economic progress. Thanks to this important scientific tool, a variety of radioisotopes for medicine and industry applications as well as for scientific research has been produced. Utilization of the Dalat research reactor for radioisotope production is also summarized in this paper

  11. Production capabilities in US nuclear reactors for medical radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Mirzadeh, S.; Callahan, A.P.; Knapp, F.F. Jr. [Oak Ridge National Lab., TN (United States); Schenter, R.E. [Westinghouse Hanford Co., Richland, WA (United States)

    1992-11-01

    The availability of reactor-produced radioisotopes in the United States for use in medical research and nuclear medicine has traditionally depended on facilities which are an integral part of the US national laboratories and a few reactors at universities. One exception is the reactor in Sterling Forest, New York, originally operated as part of the Cintichem (Union Carbide) system, which is currently in the process of permanent shutdown. Since there are no industry-run reactors in the US, the national laboratories and universities thus play a critical role in providing reactor-produced radioisotopes for medical research and clinical use. The goal of this survey is to provide a comprehensive summary of these production capabilities. With the temporary shutdown of the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) in November 1986, the radioisotopes required for DOE-supported radionuclide generators were made available at the Brookhaven National Laboratory (BNL) High Flux Beam Reactor (HFBR). In March 1988, however, the HFBR was temporarily shut down which forced investigators to look at other reactors for production of the radioisotopes. During this period the Missouri University Research Reactor (MURR) played an important role in providing these services. The HFIR resumed routine operation in July 1990 at 85 MW power, and the HFBR resumed operation in June 1991, at 30 MW power. At the time of the HFBR shutdown, there was no available comprehensive overview which could provide information on status of the reactors operating in the US and their capabilities for radioisotope production. The obvious need for a useful overview was thus the impetus for preparing this survey, which would provide an up-to-date summary of those reactors available in the US at both the DOE-funded national laboratories and at US universities where service irradiations are currently or expected to be conducted.

  12. Some aspects of cesium deposition in Transilvania (Romania)

    International Nuclear Information System (INIS)

    Following the accident of the Chernobyl atomic electric power station, a great quantity of radionuclides (∼100MCi) escaped from the reactor. It was estimated that 13% of the inventory activity of cesium representing 1.5-2 MCi left the reactor. The radioactive deposits were very nonuniform for the same distance and in the same direction from Chernobyl nuclear center having a close dependence upon direction and speed of wind and pluviometric conditions. The rains, especially the storms, spectacularly increased the radioactive fallout. Although, for the first two-three days, subsequent to accident, the meteorological conditions were favorable for Romania, after April 29/30, because of the changing in the wind direction on SW (initial it was N and NW) the countries were on this direction - Romania, Bulgaria, Greece, former Yugoslavia - began to be intensely contaminated with radioactive fallout. In Romania, the radioactive cloud passing coincided with abundant rains, especially on the direction mentioned above. On this direction, the cesium deposits are of 8-2 times larger than other Romanian regions. The torrential rain which fell on May 1st 1986, in the western side of Cluj Napoca town caused an intense contamination especially with short-life isotopes as Te, I, Ba, La, Mo. Medium and long-life isotopes as Ru, Zr, Cs, Sr were present in large quantities in this area.too. For the total contribution the value obtained was 1130 kBq/m2, much larger than the average in Romania. This work presents data about cesium content of pollen samples gathered daily between 1-30 May 1986; cesium deposits in five areas and some measurements in connection with cesium mitigation in soils

  13. Distribution and retention of cesium and strontium in Swedish boreal forest ecosystems

    International Nuclear Information System (INIS)

    The retention and distribution of cesium, and to some extent strontium, in forest environments are being studied at three sites in Sweden. The main part of the cesium found in the soil was recovered in horizons rich in organic matter. The cesium was retained in the soil organic matter in a more or less extractable form. As different soil types have a different distribution pattern of organic matter, the distribution of cesium will depend on the forest soil type. The clay content in Swedish forest soils is, in general, low which will mitigate the retention of cesium in the soil mineral horizons. The cesium and strontium present in the trees was considered to be an effect of assimilation by the tissues in the canopy as well as by the roots. The redistribution of cesium within the trees was extensive which was considered to be the effect of a high mobility of cesium in the trees. The recovery of strontium-90 in pines, in relation to the deposition rate was higher compared to the relative recovery of cesium-137, 30 years after deposition. The cesium and strontium will remain in the forest environment for a considerable time but can be reduced by forest practice, by leaching out of the soil profile or by radioactive decay

  14. Thermophotoelectric converter with radioisotope source of thermal radiation

    International Nuclear Information System (INIS)

    Results of investigating a thermophotoelectric converter with a radioisotope heat source to warm up a radiating surface are presented. Results are given of calculating the efficiency of thermophotoelectric converters with germanium and silicon photocells in the temperature range from 1000 to 1300 K, and of the comparative analysis of experimental and theoretical values of thermophotoelectric converter efficiencies. The possibility of developing a thermophotoconverter with a radioisotope source of thermal energy which has an efficiency of up to 15% is substantiated. It is shown that for effective energy conversion at radiator temperatures of 1000-1300 K it is necessary to use Ge, GaSb, InAs, PbS and PbTe semiconducting materials, and to increase to maximum the reflection coefficient of the photocell back contact and the radiation blackness

  15. Spallation production of neutron deficient radioisotopes in North America

    Energy Technology Data Exchange (ETDEWEB)

    Jamriska, D.J.; Peterson, E.J. [Los Alamos National Lab., NM (United States); Carty, J. [Dept. of Energy, Germantown, MD (United States). Office of Isotope Production and Distribution

    1997-12-31

    The US Department of Energy produces a number of neutron deficient radioisotopes by high energy proton induced spallation reactions in accelerators at Los Alamos National Laboratory in New Mexico and Brookhaven National Laboratory in New York. Research isotopes are also recovered from targets irradiated at TRIUMF in British Columbia, Canada. The radioisotopes recovered are distributed for use in nuclear medicine, environmental research, physics research, and industry worldwide. In addition to the main product line of Sr-82 from either Mo or Rb targets, Cu-67 from ZnO targets, and Ge-68 and RbBr targets, these irradiation facilities also produce some unique isotopes in quantities not available from any other source such as Al-26, Mg-28, Si-32, Ti-44, Fe-52, Gd-148, and Hg-194. The authors will describe the accelerator irradiation facilities at the Los Alamos and Brookhaven National Laboratories. The high level radiochemical processing facilities at Los Alamos and brief chemical processes will be described.

  16. Environmental assessment for radioisotope heat source fuel processing and fabrication

    International Nuclear Information System (INIS)

    DOE has prepared an Environmental Assessment (EA) for radioisotope heat source fuel processing and fabrication involving existing facilities at the Savannah River Site (SRS) near Aiken, South Carolina and the Los Alamos National Laboratory (LANL) near Los Alamos, New Mexico. The proposed action is needed to provide Radioisotope Thermoelectric Generators (RTG) to support the National Aeronautics and Space Administration's (NASA) CRAF and Cassini Missions. Based on the analysis in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an Environmental Impact Statement is not required. 30 refs., 5 figs

  17. Production of radioisotopes within a plasma focus device

    International Nuclear Information System (INIS)

    In recent years, research conducted in the US and in Italy has demonstrated production of radioisotopes in Plasma Focus (PF) devices, and particularly, on what could be termed 'endogenous' production, to wit, production within the plasma itself, as opposed to irradiation of targets. This technique relies on the formation of localized small plasma zones characterized by very high densities and fairly high temperatures. The conditions prevailing in these zones lead to high nuclear reaction rates, as pointed out in previous work by several authors. Further investigation of the cross sections involved has proven necessary to model the phenomena involved. In this paper, the present status of research in this field is reviewed, both with regards to cross section models and to experimental production of radioisotopes. Possible outcomes and further development are discussed. (author)

  18. Process for radioisotope recovery and system for implementing same

    Science.gov (United States)

    Meikrantz, David H.; Todd, Terry A.; Tranter, Troy J.; Horwitz, E. Philip

    2007-01-02

    A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.

  19. Radioisotope production at JYFL Accelerator Laboratory in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Kumpulainen, J.; Hiltunen, J. [MAP Medical Technologies, Inc., Tikkakoski (Finland); Aeystoe, J.; Julin, R.; Liukkonen, E.; Nieminen, V.; Poikolainen, T. [Univ. of Jyvaeskylae (Finland)

    1994-12-31

    MAP Medical Technologies Inc. is a private, research oriented high-tech company, which produces radiopharmaceuticals for both diagnostic and therapeutical purposes. MAP has one nuclear reactor and one high-energy cyclotron at its disposal for research and production. The new production plant was completed in 1992, which was specially designed to fulfil the highest new requirements and standards for production and products. High-energy machines, like the new K130-cyclotron in the University of Jyvaeskylae, have a great potential for producing some special radioisotopes. Thus a solid target station for radioisotope production was planned into the new accelerator laboratory in collaboration between the Department of Physics (JYFL) and MAP. The target station is designed for high-energy intensive light-ion beams delivered from the K130-cyclotron.

  20. Overview on radioisotope production at TRIGA-SSR 14 MW

    International Nuclear Information System (INIS)

    The paper presents the technical support provided at Institute for Nuclear Research (INR) Pitesti to accomplish various services concerning isotope production. Also it is presented the study to produce, in collaboration with Institute for Physics and Nuclear Engineering (IFIN) Bucharest, I-131, Au-198, Mo-99, Ir-192 isotopes for medical uses. There is presented neutron physics computation for the TRIGA core to establish the proper experimental locations to accomplish the radioisotope production. (authors)

  1. Radio-isotope bone scanning in suspected osteomyelitis in children

    International Nuclear Information System (INIS)

    The usefulness of radio-isotope bone scanning in suspected osteomyelitis has been widely acclaimed. Fourteen children had rectilinear bone scans performed three hours after injection of Tcsup(99m) methylene diphosphonate. A diagnostic accuracy of 56% was achieved, which is lower than in other series. The reasons for this are discussed and the value of bone scanning in the evaluation of osteomyelitis is questioned. (orig.)

  2. Prospective production of radioisotopes and radiopharmaceuticals in divisions of IPPE

    International Nuclear Information System (INIS)

    The first reason to commence the work on production of radioisotope production in IPPE, was the requirement of Russia medicine for original generators of technetium. The essential extension of their production in conditions of Moscow city has met the declaiming of the Moscow urban authorities. The important moment was that, in IPPE were objective possibilities to deployment the production of radioisotope production. Nowadays, nomenclature of the radioisotopes which have been produced in IPPE, constitutes 29 positions. The profile of production of radioisotope production was generated also. Restricted possibilities of the ray base, from one side, and the needs(requirement) of domestic medicine with other, in main have spotted this profile. The raw isotopes constitute a minority - on sales volumes ∼ 20 % (in main abroad), the defining part is constituted the form ready for the use by ∼ 80 % (in main in Russia). All 'know-how' is conditionally possible to divide into 3 categories: Base. It is technologies provided with an operating production sector, guaranteeing stable on quality production having a rather wide seller's market; Perspective. It is those technologies, in which the main stages of RESEARCH and DEVELOPMENT are fulfilled with positive result, but the working sites yet are not generated, and on the market are delivered only some samples of production. Are guessed RESEARCH AND DEVELOPMENT on perfecting the technology; Preparative. The technology, on which there are no regular orders, is not required of an individual working site. Sometimes it is rather precision operations, bound with usage of unique raw material, with a very stiff price of production. (authors)

  3. Radioisotope Concentration in Lake Sediments of Maracaibo, Venezuela

    International Nuclear Information System (INIS)

    Maracaibo Lake is one of the most important water basing and oil producing regions in Venezuela. Changes in the local environment have been monitored for chemical pollution in the past. For this study we selected a set of sediment samples collected in the shore and analyzed for its radioisotope content. Results show the gamma emitting isotopes distribution. Isotopes concentrations have been determined within the natural K, Th and U families

  4. Production, control and utilization of radioisotopes including radiopharmaceuticals

    International Nuclear Information System (INIS)

    From April 29th to May 5th, 1984 27 participants from 21 developing countries stayed within an IAEA Study Tour ('Production, Control and Utilization of Radioisotopes including Radiopharmaceuticals') in the GDR. In the CINR, Rossendorf the reactor, the cyclotron, the technological centre as well as the animal test laboratory were visited. The participants were made familiar by 10 papers with the development, production and control of radiopharmaceuticals in the CINR, Rossendorf. (author)

  5. Radioisotope thermoelectric generator transportation system subsystem 143 software development plan

    International Nuclear Information System (INIS)

    This plan describes the activities to be performed and the controls to be applied to the process of specifying, developing, and qualifying the data acquisition software for the Radioisotope Thermoelectric Generator (RTG) Transportation System Subsystem 143 Instrumentation and Data Acquisition System (IDAS). This plan will serve as a software quality assurance plan, a verification and validation (V and V) plan, and a configuration management plan

  6. Cesium-137, a drama recounted; Cesio-137, um drama recontado

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, Suzane de Alencar

    2013-01-15

    The radiological accident with Cesium-137, which started on Goiania in 1987, did not stop with the end of radiological contamination and continues in a judicial, scientific and narrative process of identification and recognition of new victims. The drama occupies a central place on the dynamics of radiological event, as it extends its limits, inflects its intensity and updates the event. As a narrative of the event, the ethnography incorporates and brings up to date the drama as an analysis landmark and the description of the theme as it is absorbed by a dramatic process. Cesium-137, a drama recounted is a textual experimentation based on real events and characters picked out from statements reported in various narratives about the radiological accident. (author)

  7. Trapping and cooling cesium atoms in a speckle field

    International Nuclear Information System (INIS)

    We present the results of two experiments where cold cesium atoms are trapped in a speckle field. In the first experiment, a YAG laser creates the speckle pattern and induces a far-detuned dipole potential which is a nearly-conservative potential. Localization of atoms near the intensity maxima of the speckle field is observed. In a second experiment we use two counterpropagating laser beams tuned close to a resonance line of cesium and in the lin perpendicular to lin configuration, one of them being modulated by a holographic diffuser that creates the speckle field. Three-dimensional cooling is observed. Variations of the temperature and of the spatial diffusion coefficient with the size of a speckle grain are presented. (orig.)

  8. Kelvin Probe Studies of Cesium Telluride Photocathode for AWA Photoinjector

    CERN Document Server

    Wisniewski, Eric; Yusof, Zikri; Spentzouris, Linda; Terry, Jeff; Harkay, Katherine

    2012-01-01

    Cesium telluride is an important photocathode as an electron source for particle accelerators. It has a relatively high quantum efficiency (>1%), is sufficiently robust in a photoinjector, and has a long lifetime. This photocathode is grown in-house for a new Argonne Wakefield Accelerator (AWA) beamline to produce high charge per bunch (~50 nC) in a long bunch train. Here, we present a study of the work function of cesium telluride photocathode using the Kelvin Probe technique. The study includes an investigation of the correlation between the quantum efficiency and the work function, the effect of photocathode aging, the effect of UV exposure on the work function, and the evolution of the work function during and after photocathode rejuvenation via heating.

  9. Cesium exchange reaction on natural and modified clinoptilolite zeolites

    International Nuclear Information System (INIS)

    Cesium cation exchange reaction with K, Na, Ca and Mg ions on natural and modified clinoptilolite has been studied. Batch cation-exchange experiments were performed by placing 0.5 g of clinoptilolite into 10 ml or 20 ml of 1 x 10-3M CsCl solution for differing times. Two type deposits of clinoptilolite zeolites from, Nizny Hrabovec (NH), Slovakia and Metaxades (MX), Greece were used for ion-exchange study. The distribution coefficient (Kd) and sorption capacity (Γ) were evaluated. For the determination of K, Na, Ca and Mg isotachophoresis method, the most common cations in exchange reaction was used. Cesium sorption was studied using 137Cs tracer and measured by γ-spectrometry. (author)

  10. Spectrally selective optical pumping in Doppler-broadened cesium atoms

    International Nuclear Information System (INIS)

    The D1 line spectrally selective pumping process in Doppler-broadened cesium is analyzed by solving the optical Bloch equations. The process, described by a three-level model with the Λ scheme, shows that the saturation intensity of broadened atoms is three orders of magnitude larger than that of resting atoms. The |Fg = 3> → |Fe = 4> resonance pumping can result in the ground state |Fg = 4, mF = 4> sublevel having a maximum population of 0.157 and the population difference would be about 0.01 in two adjacent magnetic sublevels of the hyperfine (HF) state Fg = 4. To enhance the anisotropy in the ground state, we suggest employing dichromatic optical HF pumping by adding a laser to excite D1 line |Fg = 4> → |Fe = 3> transition, in which the cesium magnetometer sensitivity increases by half a magnitude and is unaffected by the nonlinear Zeeman effect even in Earth's average magnetic field. (atomic and molecular physics)

  11. Fiber laser system for cesium and rubidium atom interferometry

    CERN Document Server

    Diboune, Clément; Bidel, Yannick; Cadoret, Malo; Bresson, Alexandre

    2016-01-01

    We present an innovative fiber laser system for both cesium and rubidium manipulation. The architecture is based on frequency conversion of two lasers at 1560 nm and 1878 nm. By taking advantage of existing fiber components at these wavelengths, we demonstrate an all fiber laser system delivering 350 mW at 780 nm for rubidium and 210 mW at 852 nm for cesium. This result highlights the promising nature of such laser system especially for Cs manipulation for which no fiber laser system has been reported. It offers new perspectives for the development of atomic instruments dedicated to onboard applications and opens the way to a new generation of atom interferometers involving three atomic species $^{85}$Rb, $^{87}$Rb and $^{133}$Cs for which we propose an original laser architecture.

  12. Advanced radioisotope power source options for Pluto Express

    International Nuclear Information System (INIS)

    In the drive to reduce mass and cost, Pluto Express is investigating using an advanced power conversion technology in a small Radioisotope Power Source (RPS) to deliver the required mission power of 74 W(electric) at end of mission. Until this year the baseline power source under consideration has been a Radioisotope Thermoelectric Generator (RTG). This RTG would be a scaled down GPHS RTG with an inventory of 6 General Purpose Heat Sources (GPHS) and a mass of 17.8 kg. High efficiency, advanced technology conversion options are being examined to lower the power source mass and to reduce the amount of radioisotope needed. Three technologies are being considered as the advanced converter technology: the Alkali Metal Thermal-to-Electric Converter (AMTEC), Thermophotovoltaic (TPV) converters, and Stirling Engines. Conceptual designs for each of these options have been prepared. Each converter would require only 2 GPHSs to provide the mission power and would have a mass of 6.1, 7.2, and 12.4 kg for AMTEC, TPV, and Stirling Engines respectively. This paper reviews the status of each technology and the projected performance of an advanced RPS based on each technology. Based on the projected performance and spacecraft integration issues, Pluto Express would prefer to use the AMTEC based RPS. However, in addition to technical performance, selection of a power technology will be based on many other factors

  13. A comparative study of different contaminant radioisotopes in various materials

    International Nuclear Information System (INIS)

    An order was established between the various radioisotopes, in order to compare which of them are a major problem concerning the contamination they originate in the materials using during their process, transportation and protection, consequently a sampling of contaminated materials was realized. These materials were submitted to a decontamination process with different reagents (acids, bases and organic and inorganic salts) varying their concentration through dilution with water. Besides for the same kind of reagent two processes were used, one with turbulence in the reagent through mechanical stirring, and the other static maintaining similar volumes of liquid in the two processes as well as a similar material, form and size of the object during the processes, detection of radiation in the samples were realized through a Geiger-Muller detector in similar periods of time, establishing this way a parallel system of comparison which allowed us to observe gains in the necessary period of time for reaching the same grade of decontamination in the two processes, it was concluded that it is very difficult to reach an order of comparison in the contamination because the periods of treatment vary as a function of the chemical compound containing the radioisotope(s). Besides we can reduce considerably the period of time in a stirring process and predict this necessary period of time for reaching the determined decontamination, provided that there are not permanent contaminations. (author)

  14. NASA's Radioisotope Power Systems Planning and Potential Future Systems Overview

    Science.gov (United States)

    Zakrajsek, June F.; Woerner, Dave F.; Cairns-Gallimore, Dirk; Johnson, Stephen G.; Qualls, Louis

    2016-01-01

    The goal of NASA's Radioisotope Power Systems (RPS) Program is to make RPS ready and available to support the exploration of the solar system in environments where the use of conventional solar or chemical power generation is impractical or impossible to meet the needs of the missions. To meet this goal, the RPS Program, working closely with the Department of Energy, performs mission and system studies (such as the recently released Nuclear Power Assessment Study), assesses the readiness of promising technologies to infuse in future generators, assesses the sustainment of key RPS capabilities and knowledge, forecasts and tracks the Program's budgetary needs, and disseminates current information about RPS to the community of potential users. This process has been refined and used to determine the current content of the RPS Program's portfolio. This portfolio currently includes an effort to mature advanced thermoelectric technology for possible integration into an enhanced Multi-Mission Radioisotope Generator (eMMRTG), sustainment and production of the currently deployed MMRTG, and technology investments that could lead to a future Stirling Radioisotope Generator (SRG). This paper describes the program planning processes that have been used, the currently available MMRTG, and one of the potential future systems, the eMMRTG.

  15. The use of radioisotopes for the study of flotation processes

    International Nuclear Information System (INIS)

    The paper considers methods of studying flotation processes with radioisotopes and nuclear radiation. Radioisotopes can be used for studying the fixation of flotation reagents on the surface of minerals where monomolecular coverage of the surface is incomplete. Radiometric and microautoradiographic methods are used in this research. The use of collector reagents containing radioisotopes has explained why some sulphides are difficult to separate by flotation. This difficulty is related to the material composition and structure of these minerals and to the chemical bonds within their crystal lattices. The simultaneous use of radiometric and autoradiographic methods accompanied by solvent-washing of the mineral particles showed the conditions under which dixanthate and other products of the interaction of xanthates with sulphide minerals are formed. The use of radioactive kerosene, and also of kerosene in conjunction with other flotation reagents, made it possible to determine certain features of fixation on molybdenite depending on the kerosene concentration. Contrast and track microautoradiography were used to study the distribution of sulphydryl collector reagents on different particles of galenite in the flotation pulp. The combined effect of these reagents was also studied. Combinations of xanthates of various alcohols produce a more even distribution on the galenite particles, and permit a more efficient use of reagents. C14-labelled tridecylamine was used to study the interaction of a cationic collector with hlibnerite and wolframite. The investigation showed that tridecylamine, when introduced into the flotation process, is substantially absorbed by foaming products. Non-foaming products (quartz, fluorite, calcite) absorb insignificant quantities of reagent. (author)

  16. Studies on the Separation of Cesium From Fission Products

    Institute of Scientific and Technical Information of China (English)

    QIANLi-juan; ZHANGSheng-dong; GUOJing-ru; CUIAn-zhi; YANGLei; WUWang-suo

    2003-01-01

    135Cs is a long-life fission product. When measuring its thermal cross section, we must separate radiochemical purity cesium from fission products. Except for decontaminating radio- nuclides, others which can be activated must be avoided to come into solution. So ion exchanger is used. Inorganic ion exchangers have received increased attention because of their high resistance to radiation and their very efficient separation of alkali metal ions.

  17. Optimized production of a cesium Bose-Einstein condensate

    OpenAIRE

    Kraemer, Tobias; Herbig, Jens; Mark, Michael; Weber, Tino; Chin, Cheng; Naegerl, Hanns-Christoph; Grimm, Rudolf

    2004-01-01

    We report on the optimized production of a Bose-Einstein condensate of cesium atoms using an optical trapping approach. Based on an improved trap loading and evaporation scheme we obtain more than $10^5$ atoms in the condensed phase. To test the tunability of the interaction in the condensate we study the expansion of the condensate as a function of scattering length. We further excite strong oscillations of the trapped condensate by rapidly varying the interaction strength.

  18. Radioactive cesium. Dynamics and transport in forestal food-webs

    International Nuclear Information System (INIS)

    This report summarises results from a radioecological study during 1994-1995 concerning turnover, redistribution and loss of radioactive Cesium (134 and 137) in boreal forest ecosystems, as well as uptake and transfer in important food-chains over moose, vole and vegetation. The basis for this report are 9 publications published 1994-95. These reports are presented in summary form. 9 refs, 17 figs

  19. Electrically switched cesium ion exchange. FY 1997 annual report

    International Nuclear Information System (INIS)

    This paper describes the Electrically Switched Ion Exchange (ESIX) separation technology being developed as an alternative to ion exchange for removing radionuclides from high-level waste. Progress in FY 1997 for specific applications of ESIX is also outlined. The ESIX technology, which combines ion exchange and electrochemistry, is geared toward producing electroactive films that are highly selective, regenerable, and long lasting. During the process, ion uptake and elution can be controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto a high surface area electrode. This method adds little sodium to the waste stream and minimizes the secondary wastes associated with traditional ion exchange techniques. Development of the ESIX process is well underway for cesium removal using ferrocyanides as the electroactive films. Films having selectivity for perrhenate (a pertechnetate surrogate) over nitrate also have been deposited and tested. Based on the ferrocyanide film capacity, stability, rate of uptake, and selectivity shown during performance testing, it appears possible to retain a consistent rate of removal and elute cesium into the same elution solution over several load/unload cycles. In batch experiments, metal hexacyanoferrate films showed high selectivities for cesium in concentrated sodium solutions. Cesium uptake was unaffected by Na/Cs molar ratios of up to 2 x 104 , and reached equilibrium within 18 hours. During engineering design tests using 60 pores per inch, high surface area nickel electrodes, nickel ferrocyanide films displayed continued durability. losing less than 20% of their capacity after 1500 load/unload cycles. Bench-scale flow system studies showed no change in capacity or performance of the ESIX films at a flow rate up to 13 BV/h, the maximum flow rate tested, and breakthrough curves further supported once-through waste processing. 9 refs., 24 figs

  20. Corrections to our results for optical nanofiber traps in Cesium

    CERN Document Server

    Ding, D; Choi, K S; Kimble, H J

    2012-01-01

    Several errors in Refs. [1, 2] are corrected related to the optical trapping potentials for a state-insensitive, compensated nanofiber trap for the D2 transition of atomic Cesium. Section I corrects our basic formalism in Ref. [1] for calculating dipole-force potentials. Section II corrects erroneous values for a partial lifetime and a transition wavelength in Ref. [1]. Sections III and IV present corrected figures for various trapping configurations considered in Refs. [1] and [2], respectively.

  1. Test procedures and instructions for Hanford complexant concentrate supernatant cesium removal using CST

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, D.W.

    1997-01-08

    This document provides specific test procedures and instructions to implement the test plan for the preparation and conduct of a cesium removal test, using Hanford Complexant Concentrate supernatant liquor from tank 241-AN-107, in a bench-scale column. The cesium sorbent to be tested is crystalline silicotitanate. The test plan for which this provides instructions is WHC-SD-RE-TP-023, Hanford Complexant Concentrate Supernatant Cesium Removal Test Plan.

  2. Test procedures and instructions for Hanford tank waste supernatant cesium removal

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, D.W., Westinghouse Hanford

    1996-05-31

    This document provides specific test procedures and instructions to implement the test plan for the preparation and conduct of a cesium removal test using Hanford Double-Shell Slurry Feed supernatant liquor from tank 251-AW-101 in a bench-scale column.Cesium sorbents to be tested include resorcinol-formaldehyde resin and crystalline silicotitanate. The test plan for which this provides instructions is WHC-SD-RE-TP-022, Hanford Tank Waste Supernatant Cesium Removal Test Plan.

  3. MODELING RESULTS FROM CESIUM ION EXCHANGE PROCESSING WITH SPHERICAL RESINS

    Energy Technology Data Exchange (ETDEWEB)

    Nash, C.; Hang, T.; Aleman, S.

    2011-01-03

    Ion exchange modeling was conducted at the Savannah River National Laboratory to compare the performance of two organic resins in support of Small Column Ion Exchange (SCIX). In-tank ion exchange (IX) columns are being considered for cesium removal at Hanford and the Savannah River Site (SRS). The spherical forms of resorcinol formaldehyde ion exchange resin (sRF) as well as a hypothetical spherical SuperLig{reg_sign} 644 (SL644) are evaluated for decontamination of dissolved saltcake wastes (supernates). Both SuperLig{reg_sign} and resorcinol formaldehyde resin beds can exhibit hydraulic problems in their granular (nonspherical) forms. SRS waste is generally lower in potassium and organic components than Hanford waste. Using VERSE-LC Version 7.8 along with the cesium Freundlich/Langmuir isotherms to simulate the waste decontamination in ion exchange columns, spherical SL644 was found to reduce column cycling by 50% for high-potassium supernates, but sRF performed equally well for the lowest-potassium feeds. Reduced cycling results in reduction of nitric acid (resin elution) and sodium addition (resin regeneration), therefore, significantly reducing life-cycle operational costs. These findings motivate the development of a spherical form of SL644. This work demonstrates the versatility of the ion exchange modeling to study the effects of resin characteristics on processing cycles, rates, and cold chemical consumption. The value of a resin with increased selectivity for cesium over potassium can be assessed for further development.

  4. Some Techniques for Isolating and Using Short-Lived Radioisotopes

    International Nuclear Information System (INIS)

    Radioisotopes of a large number of elements have been used extensively at Oak Ridge National Laboratory in ion exchange,solubility and other physical-chemical studies. The use of short-lived radioisotopes in such studies has necessitated development not only of rapid methods of preparing and purifying radioisotopes but also of special techniques for obtaining pertinent information in a relatively short time, often within a few minutes. Some recently-developed methods are described for preparing and purifying short-lived isotopes, particularly those originating from neutron-irradiated materials, including fissionable elements. The latter, of course, are convenient sources of a number of useful short-lived radioisotopes, e. g., Mo99, Te132, and methods are described for rapidly isolating these and other fission products in a earner-free state by ion exchange. Methods of separating short-lived daughter activities from long-lived parents by 'milking' techniques, in which the parent is strongly adsorbed on organic or inorganic ion exchange materials, are also described and typical examples discussed, for example, milking of 1.7-h In113 (from Sn113) and 2.6-min Ba137 (from Cs197). Two applications involving the use of short-lived tracers in chemical studies are described. The first is a ''packed bed'' technique for rapidly measuring the solubilities of sparingly soluble salts which have been tagged with tracers. Some recent results obtained by the method on the solubility of LaF3 in HCl and HCIO4 solutions are described. The second is a rapid method for measuring diffusion coefficients in liquid systems. Thin, porous porcelain frits are saturated with solution containing a radioisotope, then rapidly eluted with solution not containing tracer. Diffusion coefficients may be calculated from the decrease of counting rate of the frit with time,after calibration with a material of known diffusion rate. Because of the short diffusion path used, die measurements may be completed

  5. A Review of the Production of ''Special'' Radioisotopes

    International Nuclear Information System (INIS)

    Six useful characteristics of radioisotopes and advantages which may be taken of them are cited briefly, with examples. The Information Sheet announcing this Seminar listed four advantages of short-lived over long-lived isotopes. Two other reasons why owners of small research reactors should concern themselves with short half- life isotopes are economy and particular suitability for production, the latter being due to the pronounced effect of half-life on the net rate of production. Besides short half-life, type and energy of emitted radiation should be of concern to producers of isotopes. Nine advantages of a nuclear reactor over a particle accelerator for radioisotope production are outlined. Following this general orientation, a survey of unusual or less frequently used production techniques is presented. These include: (n, p) reactions and secondary reactions such as (t, n) and (t, p) induced by thermal neutrons, various techniques for obtaining useful fluxes of fast neutrons with which to effect other reactions, recoil techniques including classic Szilard-Chalmers reactions, use of charged wires to collect short-lived daughters of gaseous parents, parent-daughter milking system, parasitic irradiations, possible use of ''knocked- on'' protons or deuterons (from the moderator) as a means of effecting reactions such as (p,n), (d,n), etc. and the possible use of circulating ''loops'' in reactors with which to utilize the radiation from ultra-short-lived radioisotopes such as Ag110, In114, 116, Dy155m, etc. Although not a production technique, the possibility of using certain stable isotopes (e. g. of silver) as tracers which can be readily detected via subsequent activation is mentioned. Production figures for Brookhaven's ''special'' radioisotopes are cited to show differences in long- and short-term fluctuations among these isotopes, which are also compared as a class to those in heavier demand supplied by Oak Ridge. Present production methods of all 'special

  6. Cesium Toxicity Alters MicroRNA Processing and AGO1 Expressions in Arabidopsis thaliana.

    Directory of Open Access Journals (Sweden)

    Il Lae Jung

    Full Text Available MicroRNAs (miRNAs are short RNA fragments that play important roles in controlled gene silencing, thus regulating many biological processes in plants. Recent studies have indicated that plants modulate miRNAs to sustain their survival in response to a variety of environmental stimuli, such as biotic stresses, cold, drought, nutritional starvation, and toxic heavy metals. Cesium and radio-cesium contaminations have arisen as serious problems that both impede plant growth and enter the food chain through contaminated plants. Many studies have been performed to define plant responses against cesium intoxication. However, the complete profile of miRNAs in plants during cesium intoxication has not been established. Here we show the differential expression of the miRNAs that are mostly down-regulated during cesium intoxication. Furthermore, we found that cesium toxicity disrupts both the processing of pri-miRNAs and AGONOUTE 1 (AGO1-mediated gene silencing. AGO 1 seems to be especially destabilized by cesium toxicity, possibly through a proteolytic regulatory pathway. Our study presents a comprehensive profile of cesium-responsive miRNAs, which is distinct from that of potassium, and suggests two possible mechanisms underlying the cesium toxicity on miRNA metabolism.

  7. Laboratory plant for the separation of cesium from waste solutions of the PUREX process

    International Nuclear Information System (INIS)

    A laboratory plant for the separation of cesium from a fission product waste solution of the fuel reprocessing is described. The plant consists of two stages. In the first stage cesium is adsorbed on ammonium molybdatophosphate (AMP). Then the adsorbent is dissolved. From the solution cesium is adsorbed on a cationic ion exchanger in the second stage. Then AMP can be reproduced from this solution. For the elution of cesium in the second stage a NH4NO3 solution (3 m) is used. Flow sheet, construction and the control device of the plant are described and the results of tests with a model solution are given. (author)

  8. Structure of cesium loaded iron phosphate glasses: An infrared and Raman spectroscopy study

    International Nuclear Information System (INIS)

    The structure of cesium loaded iron phosphate glasses (IPG) was investigated using infrared and Raman spectroscopy. The spectra of the cesium doped samples revealed a structural modification of the parent glass owing to the incorporation of cesium. The structural changes could be correlated with the variation observed in the glass transition temperature of these glasses. Increased Cs-mediated cationic cross linking appears to be the reason for the initial rise in glass transition temperature up to 21 mol% Cs2O in IPG; while, breakdown of the phosphate network with increasing cesium content, brings down the glass transition temperature.

  9. Mobility of cesium through the Callovo-Oxfordian claystones under partially saturated conditions

    International Nuclear Information System (INIS)

    The diffusion of cesium was studied in an unsaturated core of Callovo-Oxfordian claystone, which is a potential host rock for retrievable disposal of high-level radioactive wastes. In-diffusion laboratory experiments were performed on rock samples with water saturation degrees ranging from 81% to 100%. The analysis of both cesium concentration monitoring in the source reservoir and postmortem cesium rock concentration profile of the samples was carried out using a chemical-transport code where the sorption of cesium was described by a multi-site ion-exchange model. The results showed that cesium exhibited a clear trend related to the saturation degree of the sample. The more dehydrated the rock sample, the slower the decrease of cesium concentration, and the thinner the penetration depth of cesium was. The effective diffusion coefficient (De) for cesium decreased from 18.5 *10-11 m2 s-1 at full-saturation to 0.3 * 10-11 m2 s-1 for the more dehydrated sample. This decrease is almost 1 order of magnitude higher than that for tritiated water (HTO), although a similar behavior could have been expected, since cesium is known to diffuse in the same parts of the pore space as HTO in fully saturated claystones. (authors)

  10. Cesium transport in Four Mile Creek of the Savannah River Plant

    International Nuclear Information System (INIS)

    The behavior of a large radioactive cesium release to a Savannah River Plant (SRP) stream was examined using a stable cesium release to Four Mile Creek. Measurements following the release show that most of the cesium released was transported downstream; however, sorption and desorption decreased the maximum concentration and increased the travel time and duration, relative to a dye tracer, at sampling stations downstream. The study was made possible by the development of an analytical technique using ammonium molybdophosphate and neutron activation that permitted the measurement of stable cesium concentrations as low as 0.2 μg/L

  11. Preparation of Modified Kaolin Filler with Cesium and Its Application in Security Paper

    OpenAIRE

    Houssni El-Saied; Samya El-Sherbiny; Omnia Ali; Wafaa El-Saied; Said Rohyem

    2013-01-01

    In this study, cesium was added intentionally during paper manufacture for protecting the papers against forgery and counterfeiting by sorbing cesium ions (Cs+) on kaolin, used as special filler in papermaking. The sorption of cesium from aqueous solution by kaolin was studied as a function of pH, shaking time, cesium initial concentration, and mass of kaolin using batch technique. The results showed that a solution containing 10 mg/L Cs+ and 250 mg of kaolin at pH 6 can be used to modify the...

  12. Radioisotope Sample Measurement Techniques in Medicine and Biology. Proceedings of the Symposium on Radioisotope Sample Measurement Techniques

    International Nuclear Information System (INIS)

    The medical and biological applications of radioisotopes depend on two basically different types of measurements, those on living subjects in vivo and those on samples in vitro. The International Atomic Energy Agency has in the past held several meetings on in vivo measurement techniques, notably whole-body counting and radioisotope scanning. The present volume contains the Proceedings of the first Symposium the Agency has organized to discuss the various aspects of techniques for sample measurement in vitro. The range of these sample measurement techniques is very wide. The sample may weigh a few milligrams or several hundred grams, and may be in the gaseous, liquid or solid state. Its radioactive content may consist of a single, known radioisotope or several unknown ones. The concentration of radioactivity may be low, medium or high. The measurements may be made manually or automatically and any one of the many radiation detectors now available may be used. The 53 papers presented at the Symposium illustrate the great variety of methods now in use for radioactive- sample measurements. The first topic discussed is gamma-ray spectrometry, which finds an increasing number of applications in sample measurements. Other sections of the Proceedings deal with: the use of computers in gamma-ray spectrometry and multiple tracer techniques; recent developments in activation analysis where both gamma-ray spectrometry and computing techniques are applied; thin-layer and paper radio chromatographic techniques for use with low energy beta-ray emitters; various aspects of liquid scintillation counting techniques in the measurement of alpha- and beta-ray emitters, including chemical and colour quenching; autoradiographic techniques; calibration of equipment; and standardization of radioisotopes. Finally, some applications of solid-state detectors are presented; this section may be regarded as a preview of important future developments. The meeting was attended by 203 participants

  13. Radioisotopic methods for quality control of works and studies while constructing foundations and underground structures

    International Nuclear Information System (INIS)

    The data on the use of radioisotope methods of quality control of various kinds of construction works when building foundations and underground constructions and when carrying out scientific research, are presented. Devices and equipment are described, their block diagrams are presented. The experience in using radioisotope devices to control the quality of construction works, is presented. The problems of economic effectivenes of works using radioisotope devices are solved

  14. SIDA - System for importation distribution and acquisition of radioisotope - User manual

    International Nuclear Information System (INIS)

    The SIDA manual (system for importation, distribution and acquisition of radioisotopes) is presented. The SIDA is a system of consult and update to control importation and distribution of radioisotopes in the country. It allows to accompany processes from importation requirement to distribution of radioisotopes, executing the accountancy of I-125, which is distributed for several interprises. The system was developed in CLIPPER87 using DBASE III PLUS data base management. (M.C.K.)

  15. Cesium-137, a tool for the assessment and the management of erosion risks

    International Nuclear Information System (INIS)

    Cesium-137 (137Cs) is a radioisotope that was artificially introduced in the environment through the extensive high-atmosphere bomb tests that took place in the 1950s and 1960s. Due to its environmental behavior in soils, this isotope is a particularly interesting soil movement indicator. Its spatial redistribution reveals global soil movements that were initiated some 35 years ago. The rates and spatial extent of soil loss and deposition areas can be established, and thus soil movement budgets are easily estimated, at scales ranging from small plots to watersheds. Generally, soil movements are estimated by comparing the activity of 137Cs (expressed in Bq.m-2) of cultivated soils to that of so-called reference sites (old prairie or forest soils) assumed to be uneroded. Different models to translate soil 137Cs variations into soil movements have been suggested over the years (equations 3 to 5). The authors used this technique in Quebec and France. The sampling of 63 cultivated fields near Quebec City, led to an average soil loss estimate of nearly 6 Mg.ha-1.yr-1. The erosion rates varied according the land use and slope steepness (Table 2). The results of this study also suggest that redeposition is an important component of the overall erosive process, particularly under low grade slopes and protective plant cover conditions. From 137Cs measurements obtained on a 180 ha unit watershed near Vierzy (France), it was estimated that 45% and 14% of the watershed area had experienced a net soil loss and gain respectively (Figure 4). The net sediment output was evaluated at less than 1.9 Mg.ha-1.yr-1. In a still on-going study, 137Cs is used to shed some light on the origins of the sedimentation problem impairing the waters of Boyer River (Québec). Soils from cultivated fields, stream bank soils and sediments from the river bed are counted for 137Cs. It was estimated that 78% of the counted bottom sediments originated from cultivated fields, while the other 22% was from

  16. Radioisotope Stirling Generator Options for Pluto Fast Flyby Mission

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    2012-01-19

    The preceding paper described conceptual designs and analytical results for five Radioisotope Thermoelectric Generator (RTG) options for the Pluto Fast Flyby (PFF) mission, and the present paper describes three Radioisotope Stirling Generator (RSG) options for the same mission. The RSG options are based on essentially the same radioisotope heat source modules used in previously flown RTGs and on designs and analyses of a 75-watt free-piston Stirling engine produced by Mechanical Technology Incorporated (MTI) for NASA's Lewis Research Center. The integrated system design options presented were generated in a Fairchild Space study sponsored by the Department of Energy's Office of Special Applications, in support of ongoing PFF mission and spacecraft studies that the Jet Propulsion Laboratory (JPL) is conducting for the National Aeronautics and Space Administration (NASA). That study's NASA-directed goal is to reduce the spacecraft mass from its baseline value of 166 kg to ~110 kg, which implies a mass goal of less than 10 kg for a power source able to deliver 69 watts(e) at the end of the 9.2-year mission. In general, the Stirling options were found to be lighter than the thermoelectric options described in the preceding paper. But they are less mature, requiring more development, and entailing greater programmatic risk. The Stirling power system mass ranged from 7.3 kg (well below the 10-kg goal) for a non-redundant system to 11.3 kg for a redundant system able to maintain full power if one of its engines fails. In fact, the latter system could deliver as much as 115 watts(e) if desired by the mission planners. There are 2 copies in the file.

  17. Development of Next Generation Segmented Thermoelectric Radioisotope Power Systems

    Science.gov (United States)

    Fleurial, J.; Caillat, T.; Ewell, R. C.

    2005-12-01

    Radioisotope thermoelectric generators have been used for space-based applications since 1961 with a total of 22 space missions that have successfully used RTGs for electrical power production. The key advantages of radioisotope thermoelectric generators (RTGs) are their long life, robustness, compact size, and high reliability. Thermoelectric converters are easily scalable, and possess a linear current-voltage curve, making power generation easy to control via a shunt regulator and shunt radiator. They produce no noise, vibration or torque during operation. These properties have made RTGs ideally suitable for autonomous missions in the extreme environments of outer space and on planetary surfaces. More advanced radioisotope power systems (RPS) with higher specific power (W/kg) and/or power output are desirable for future NASA missions, including the Europa Geophysical Orbiter mission. For the past few years, the Jet Propulsion Laboratory (JPL) has been developing more efficient thermoelectric materials and has demonstrated significant increases in the conversion efficiency of high temperature thermocouples, up to 14% when operated across a 975K to 300K temperature differential. In collaboration with NASA Glenn Research Center, universities (USC and UNM), Ceramic and Metal Composites Corporation and industrial partners, JPL is now planning to lead the research and development of advanced thermoelectric technology for integration into the next generations of RPS. Preliminary studies indicate that this technology has the potential for improving the RPS specific power by more than 50% over the current state-of-the-art multi-mission RTG being built for the Mars Science Laboratory mission. A second generation advanced RPS is projected at more than doubling the specific power.

  18. Some Uses of Radioisotopes and Radiations in Entomology

    International Nuclear Information System (INIS)

    The paper reviews the applications of radioisotopes in entomology that have been developed at our two centres during the last few years. Early work (Au198-labelling) related to the bee and more particularly to the radius of dispersion of worker bees from a colony. After investigations on the individual dose received in tagging of this kind, the radioresistance of the bee was determined, the lethal dose being estimated at about 90 kr. Au198 was also used to study exchange of food within a bee-hive. On the other hand, P32 was used for studies of exchange of food, in small hives, between individuals of different functions (males, workers and queens) or different colonies. Similar trophallaxic studies have recently been performed on wasps. Au198 was likewise the basic radioisotope used in work on ant's nests. The most interesting finding from one of the early studies was that exchange of food takes place between nests more than 50 m apart and belonging to different species (Formica rufa and Formica polyctena). A later study, in which an ant run and not the nest itself was labelled, revealed a division of responsibility within the nests the tagged ants were found invariably to explore the same run and to have little contact with other individuals of the same colony. In the same experiment abnormal radioactivity was noted in the ants before labelling, due in particular to (Sr+Nb)95 . This discovery would seem to point to accumulation of radioactive fall-out in ant's nests. At a period of low fall-out, natural radioactivity attributed to K40 was observed and was used for purposes of potassium determination in ants and bees. An attempt was made to label acridians with Ir192 and the findings are described in the paper. Lastly, an autoradiographic study has been made of the distribution of certain radioisotopes (P32 and S35) in the body of the bee. (author)

  19. A radioisotope powered cryobot for penetrating the Europan ice shell

    Science.gov (United States)

    Zimmerman, Wayne; Bryant, Scott; Zitzelberger, John; Nesmith, Bill

    2001-02-01

    The Cryobot team at JPL has been working on the design of a Cryo-Hydro Integrated Robotic Penetrator System (CHIRPS), which can be used to penetrate the Mars North Polar Cap or the thick sheet ice surrounding Jupiter's moon, Europa. The science for either one of these missions is compelling. For both Mars and Europa the major scientific interest is to reach regions where there is a reservoir of water that may yield signs of past or extant life. Additionally, a Mars polar cap penetration would help us understand both climatic and depositional histories for perhaps as far back as 20 million years. Similarly, penetration of the Europa ice sheet would allow scientists to unravel the mysteries surrounding the thick ice crust, its chemical composition, and subsurface ocean properties. Extreme mass and power constraints make deep drilling/coring impractical. The best way to explore either one of these environments is a cryobot mole penetrator vehicle, which carries a suite of instruments suitable for sampling and analyzing the ice or ocean environments. This paper concentrates on a Europa deep ice (i.e., kilometers thick) application of the CHIRPS, and introduces the reader to the vehicle design with focus on the use of radioisotope thermoelectric generator (RTG) technology as the primary heat (1 kW total) and power source for the robotic vehicle. Radioisotope heater unit (RHU) milli-watt power systems (120 mW total) are also employed to power the mini-radiowave ice transceivers, which are used to relay data through the ice up to the surface lander. The results of modeling and design work for both of these areas are discussed in this paper. Although radioisotope power is baselined for the Europa flight version of the cyrobot, no decision on the final design of the cryobot will be made until the environmental review process is complete. Any use of the cryobot for Mars or Europa will conform to all environmental and planetary protection requirements. .

  20. Milliwatt radioisotope power supply for the PASCAL Mars surface stations

    Science.gov (United States)

    Allen, Daniel T.; Murbach, Marcus S.

    2001-02-01

    A milliwatt power supply is being developed based on the 1 watt Light-Weight Radioisotope Heater Unit (RHU), which has already been used to provide heating alone on numerous spacecraft. In the past year the power supply has been integrated into the design of the proposed PASCAL Mars Network Mission, which is intended to place 24 surface climate monitoring stations on Mars. The PASCAL Mars mission calls for the individual surface stations to be transported together in one spacecraft on a trajectory direct from launch to orbit around Mars. From orbit around Mars each surface station will be deployed on a SCRAMP (slotted compression ramp) probe and, after aerodynamic and parachute deceleration, land at a preselected location on the planet. During descent sounding data and still images will be accumulated, and, once on the surface, the station will take measurements of pressure, temperature and overhead atmospheric optical depth for a period of 10 Mars years (18.8 Earth years). Power for periodic data acquisition and transmission to orbital then to Earth relay will come from a bank of ultracapacitors which will be continuously recharged by the radioisotope power supply. This electronic system has been designed and a breadboard built. In the ultimate design the electronics will be arrayed on the exterior surface of the radioisotope power supply in order to take advantage of the reject heat. This assembly in turn is packaged within the SCRAMP, and that assembly comprises the surface station. An electrically heated but otherwise prototypical power supply was operated in combination with the surface station breadboard system, which included the ultracapacitors. Other issues addressed in this work have been the capability of the generator to withstand the mechanical shock of the landing on Mars and the effectiveness of the generator's multi-foil vacuum thermal insulation. .

  1. Research reactor production of radioisotopes for medical use

    International Nuclear Information System (INIS)

    More than 70% of all radioisotopes applied in medical diagnosis and research are currently produced in research reactors. Research reactors are also an important source of certain radioisotopes, such as 60Co, 90Y, 137Cs and 198Au, which are employed in teletherapy and brachytherapy. For regular medical applications, mainly 29 radionuclides produced in research reactors are used. These are now produced on an 'industrial scale' by many leading commercial manufacturers in industrialized countries as well as by national atomic energy establishments in developing countries. Five main neutron-induced reactions have been employed for the regular production of these radionuclides, namely: (n,γ), (n,p), (n,α), (n,γ) followed by decay, and (n, fission). In addition, the Szilard-Chalmers process has been used in low- and medium-flux research reactors to enrich the specific activity of a few radionuclides (mainly 51Cr) produced by the (n,γ) reaction. Extensive work done over the last three decades has resulted in the development of reliable and economic large-scale production methods for most of these radioisotopes and in the establishment of rigorous specifications and purity criteria for their manifold applications in medicine. A useful spectrum of other radionuclides with suitable half-lives and low to medium toxicity can be produced in research reactors, with the requisite purity and specific activity and at a reasonable cost, to be used as tracers. Thanks to the systematic work done in recent years by many radiopharmaceutical scientists, the radionuclides of several elements, such as arsenic, selenium, rhenium, ruthenium, palladium, cadmium, tellurium, antimony, platinum, lead and the rare earth elements, which until recently were considered 'exotic' in the biomedical field, are now gaining attention. (author)

  2. Rhenium-188--a generator-derived radioisotope for cancer therapy.

    Science.gov (United States)

    Knapp, F F

    1998-10-01

    Rhenium-188 (188Re) is an important therapeutic radioisotope which is obtained on demand as carrier-free sodium perrhenate by saline elution of the tungsten-188/rhenium-188 generator system. With a half-life of 16.9 hours and emission of a high energy beta particle (maximal energy of 2.12 MeV) and a gamma photon (155 keV, 15%) for imaging, 188Re can be provided at reasonable costs for routine preparation of radiopharmaceuticals for cancer treatment. PMID:10851424

  3. Career opportunities in the applications of radiation and radioisotopes

    International Nuclear Information System (INIS)

    The application of radiation and radioisotopes is finally coming into its own after a long and hesitant gestation period. Overshadowed since the inception of the ''Nuclear Age'' by nuclear power generation, this area nevertheless provides real and challenging opportunities involving many different technical specialties and professional skills. Career opportunities are becoming available in those areas involving the use of radioactive isotopes in research, medicine, and industrial process control, and the employment of large radiation outputs, from either accelerator or isotopes, for industrial process applications

  4. Electronic structure of polycrystalline Cd metal using 241Am radioisotope

    Science.gov (United States)

    Dhaka, M. S.; Sharma, G.; Mishra, M. C.; Sharma, B. K.

    2014-04-01

    Electronic structure study of the polycrystalline cadmium metal is reported. The experimental measurement is undertaken on a polycrystalline sheet sample using 59.54 keV radioisotope of 241Am. These results are compared with the ab initio calculations. The theoretical calculations are performed using linear combination of atomic orbitals (LCAO) method employing the density functional theories (DFT) and Hartree-Fock (HF) and augmented plane wave (APW) methods. The spherically averaged APW and LCAO based theoretical Compton profiles are in good agreement with the experimental measurement however the APW based theoretical calculations show best agreement.

  5. REVISS / MAYAK: A new partnership in radioisotope supply

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, N. [REVISS Services Limited, Chesham (United Kingdom); Chikshov, A.I.; Malykh, Y.A. [MAYAK Production Association, Ozyorsk (Russian Federation)

    1997-10-01

    REVISS Services (UK) Limited, the joint venture company formed between Amersham International plc, Production Association MAYAK and Techsnabexport brings together the scientific, manufacturing, marketing and distribution skills and facilities which enable REVISS to be not just a major supplier of radioisotopes and other associated products and services, but the supplier with the largest product range. The paper describes the history and the development of MAYAK and reviews its manufacturing facilities and capabilities and also how MAYAK has moved from being a secret military organisation to become a major and successful commercial organisation

  6. REVISS / MAYAK: A new partnership in radioisotope supply

    International Nuclear Information System (INIS)

    REVISS Services (UK) Limited, the joint venture company formed between Amersham International plc, Production Association MAYAK and Techsnabexport brings together the scientific, manufacturing, marketing and distribution skills and facilities which enable REVISS to be not just a major supplier of radioisotopes and other associated products and services, but the supplier with the largest product range. The paper describes the history and the development of MAYAK and reviews its manufacturing facilities and capabilities and also how MAYAK has moved from being a secret military organisation to become a major and successful commercial organisation

  7. Parametric System Model for a Stirling Radioisotope Generator

    Science.gov (United States)

    Schmitz, Paul C.

    2015-01-01

    A Parametric System Model (PSM) was created in order to explore conceptual designs, the impact of component changes and power level on the performance of the Stirling Radioisotope Generator (SRG). Using the General Purpose Heat Source (GPHS approximately 250 Wth) modules as the thermal building block from which a SRG is conceptualized, trade studies are performed to understand the importance of individual component scaling on isotope usage. Mathematical relationships based on heat and power throughput, temperature, mass, and volume were developed for each of the required subsystems. The PSM uses these relationships to perform component- and system-level trades.

  8. ADVANCED RADIOISOTOPE HEAT SOURCE AND PROPULSION SYSTEMS FOR PLANETARY EXPLORATION

    Energy Technology Data Exchange (ETDEWEB)

    R. C. O' Brien; S. D. Howe; J. E. Werner

    2010-09-01

    The exploration of planetary surfaces and atmospheres may be enhanced by increasing the range and mobility of a science platform. Fundamentally, power production and availability of resources are limiting factors that must be considered for all science and exploration missions. A novel power and propulsion system is considered and discussed with reference to a long-range Mars surface exploration mission with in-situ resource utilization. Significance to applications such as sample return missions is also considered. Key material selections for radioisotope encapsulation techniques are presented.

  9. A new access control system by fingerprint for radioisotope facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, Hiroko; Hirata, Yasuki [Kyushu Univ., Fukuoka (Japan). Radioisotope Center; Kondo, Takahiro; Takatsuki, Katsuhiro

    1998-04-01

    We applied a new fingerprint checker for complete access control to the radiation controlled area and to the radioisotope storage room, and prepared softwares for the best use of this checker. This system consists of a personal computer, access controllers, a fingerprint register, fingerprint checkers, a tenkey and mat sensors, permits ten thousand users to register their fingerprints and its hard disk to keep more than a million records of user`s access. Only 1% of users could not register their fingerprints worn-out, registered four numbers for a fingerprint. The softwares automatically provide varieties of reports, caused a large reduction in manual works. (author)

  10. Radioisotope measurement of the velocity of tracheal mucus

    International Nuclear Information System (INIS)

    A radioisotope scanning technique for measuring the velocity of tracheal mucus has been developed utilizing a canine model. A solution of stannous phytate labeled with /sup 99m/Tc is introduced percutaneously into the lower trachea and the upward movement of the leading edge of the radioactivity is followed by repeat scanning at 2-minute intervals using a modified rectilinear scanner, thus allowing calculation of the velocity of the mucus. It is believed that this technique may be of value in studying the effect of experimentally induced tracheal injuries on mucus velocity. Possible applications of the technique for the study of the velocity of mucus in the human trachea are discussed

  11. Radioisotope measurement of the velocity of tracheal mucus.

    Science.gov (United States)

    Russo, K J; Palmer, D W; Beste, D J; Carl, G A; Belson, T P; Pelc, L R; Toohill, R J

    1985-04-01

    A radioisotope scanning technique for measuring the velocity of tracheal mucus has been developed utilizing a canine model. A solution of stannous phytate labeled with 99mTc is introduced percutaneously into the lower trachea and the upward movement of the leading edge of the radioactivity is followed by repeat scanning at 2-minute intervals using a modified rectilinear scanner, thus allowing calculation of the velocity of the mucus. It is believed that this technique may be of value in studying the effect of experimentally induced tracheal injuries on mucus velocity. Possible applications of the technique for the study of the velocity of mucus in the human trachea are discussed. PMID:3921912

  12. Radioisotope measurement of the velocity of tracheal mucus

    Energy Technology Data Exchange (ETDEWEB)

    Russo, K.J.; Palmer, D.W.; Beste, D.J.; Carl, G.A.; Belson, T.P.; Pelc, L.R.; Toohill, R.J.

    1985-04-01

    A radioisotope scanning technique for measuring the velocity of tracheal mucus has been developed utilizing a canine model. A solution of stannous phytate labeled with /sup 99m/Tc is introduced percutaneously into the lower trachea and the upward movement of the leading edge of the radioactivity is followed by repeat scanning at 2-minute intervals using a modified rectilinear scanner, thus allowing calculation of the velocity of the mucus. It is believed that this technique may be of value in studying the effect of experimentally induced tracheal injuries on mucus velocity. Possible applications of the technique for the study of the velocity of mucus in the human trachea are discussed.

  13. Cesium-137 inventories in undisturbed areas in different regions of Brazil

    International Nuclear Information System (INIS)

    Cesium-137 is an anthropogenic radionuclide introduced in the environment in the early of 1960s to the end of 1970s. The Cesium-137 has very used to assess soil redistribution in the landscape because this is very tight in the fine soil particles and its movement in the landscape is due to soil redistribution. To use Cesium-137 to assess soil redistribution is need to known the Cesium-137 inventory in an area that not has experimented soil erosion neither soil deposition. So, this work present Cesium-137 inventories in undisturbed areas in different regions of Brazil, from South to Northeast of Brazil. The inventories in these areas represent the variational deposition of Cesium-137 in the whole national territory of Brazil. The inventories of Cesium-137 varied from 200 ± 15 Bq.m-2 for South region to 15 ± 2 Bq.m-2 for Northeast region. Moreover, was verified that the Cesium- 137 inventories depend on latitude and altitude of the area. (author)

  14. Peculiarities of presence of cesium-137 in soil at Azgir test site grounds

    International Nuclear Information System (INIS)

    The granulometric composition of soil and the distribution of cesium-137 by soil fractions at the Azgir test site was determined. The characterization of cesium-137 presence in the layer of the thickness of 1 cm of the surface soil was gave. (author)

  15. Velocity Distribution of Effective Atoms in a Small Optically Pumped Cesium Beam Frequency Standard

    Institute of Scientific and Technical Information of China (English)

    CHEN Jingbiao; WANG Fengzhi; YANG Donghai; WANG YiQiu

    2001-01-01

    In this paper, the velocity distribution of effective atoms in a small optically pumped cesium beam frequency standard has been achieved from the Fourier transforms of the experimentally recorded Ramsey patterns. The result fits well with the theoretical calculation. The second order Doppler shift correction of the small cesium atomic clock is obtained from the velocity distribution of effective atoms.

  16. Vacuum squeezed light for atomic memories at the D2 cesium line

    CERN Document Server

    Burks, Sidney; Giacobino, Elisabeth; Laurat, Julien; Ortalo, Jérémie; Jia, Xiaojun; Villa, Fabrizio; Chuimmo, Antonino

    2008-01-01

    We report the experimental generation of squeezed light at 852 nm, locked on the Cesium D2 line. 50% of noise reduction down to 50 kHz has been obtained with a doubly resonant optical parametric oscillator operating below threshold, using a periodically-polled KTP crystal. This light is directly utilizable with Cesium atomic ensembles for quantum networking applications

  17. Ionizing mechanisms in a cesium plasma irradiated with a ruby laser

    Science.gov (United States)

    Shimada, K.; Robinson, L. B.

    1975-01-01

    A cesium filled diode--laser plasmadynamic converter was built to investigate the feasibility of converting laser energy to electrical energy at large power levels. Experiments were performed with a pulsed ruby laser to determine the quantity of electrons and cesium ions generated per pulse of laser beam and to determine the output voltage. A current density as high as 200 amp/sq cm from a spot of approximately 1 sq mm area and an open circuit voltage as high as 1.5 volts were recorded. A qualitative theory was developed to explain these results. In the operation of the device, the laser beam evaporates some of the cesium and ionizes the cesium gas. A dense cesium plasma is formed to absorb further the laser energy. Results suggest that the simultaneous absorption of two ruby laser photons by the cesium atoms plays an important role in the initial ionization of cesium. Inverse bremsstrahlung absorption appears to be the dominant mechanism in subsequent processes. Recombinations of electrons and cesium ions appear to compete favorably with the simultaneous absorption of two photons.

  18. Sorption of iodine, chlorine, technetium and cesium in soil

    International Nuclear Information System (INIS)

    The safety assessment of final disposal of spent nuclear fuel will include an estimate for the behavior of waste nuclides in the biosphere. As a part of this estimate also the sorption of radioactive iodine, chlorine, technetium and cesium in soil is to be considered. The chemistry and the sorption of these radionuclides in soils are described in this literature survey. Behavior of I-129, Cl-36 and Tc-99 in the environment is of great interest because of their long half-lives and relatively high mobilities. The importance of Cs-135 arises from its high content in spent nuclear fuel and long physical half-life, even though it is considered relatively immobile in soil. Factors affecting the migration and sorption of radionuclides in soils can be divided into elemental and soil specific parameters. The most important elemental factor is the speciation of the element, which is influenced by the soil redox potential, pH and complex forming ligands. Soil micro-organisms can either serve as sorbents for radionuclides or affect their speciation by altering the prevailing soil redox conditions. Soil organic matter content and mineral properties have a marked influence on the retention of radionuclides. The sorption of anionic radionuclides such as I-, Cl- and TcO4 - is pronounced in the presence of organic matter. Clay minerals are known to bound cesium effectively. The effect of speciation of radioactive iodine, chlorine, technetium and cesium in soil is considered in this study, as well as the effect of soil micro-organisms, organic matter and mineral properties. (orig.)

  19. Cesium-137 inventory of the undisturbed soil areas in the Londrina Region, Parana, Brazil

    International Nuclear Information System (INIS)

    Cesium-137 is an artificial radionuclide introduced in the environment through the radioactive fallout of the superficial tests of nuclear weapons. The cesium-137 deposition occurred to middles of the 1980-decade and, due to the Chernobyl accident, great part of Europe had a additional fallout of cesium-137. The contaminations of this accident do not have reached Southern Hemisphere. Cesium-137 is an alkaline metal, high electropositive, that in contact with the soil is strongly adsorbed to the clay in the FES (Frayed Edge Sites) and RES (Regular Edge Sites) positions, and it movement by chemical processes in the soil is insignificant. Because of this, cesium-137 became a good soil marker, and its movement is related to the soil movement particles, so that the cesium-137 have been used in the study of the soil redistribution processes, as a tool of quantifying the rates of soil losses and gain. To use this methodology, it is necessary the knowledge of the reference inventory of cesium-137, that is given as function of the total concentration of cesium-137 deposited in an area by the radioactive fallout. If a sampling point presents less cesium-137 than the reference inventory, this point is considered a point with soil loss; otherwise, the point is considered a point with soil deposition. To evaluate the cesium-137 inventory in the Londrina region, four areas of the undisturbed soil were sampling in grid of 3x3, with a distance of 9 meters among the points. Of these four sampling areas, three areas were of native forest (labeled Mata1, Mata2 and Mata UEL), and one was a pasture area. Cesium-137 inventory was 223 ± 41 Bq m-2, 240 ± 65 Bq m-2 and 305 ± 36 Bq m-2 for Mata UEL, Mata1 and Mata2, respectively, and of 211 ± 28 Bq m-2 for the native pasture. Considering the deviation in each value, it is not possible to conclude that there are differences among the values of cesium-137 inventory, so that the average reference inventory of cesium-137 for the Londrina

  20. SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION-EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATIONS-12092

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L.; Martin, K.; Hobbs, D.

    2011-11-10

    Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate (MST) and crystalline silicotitanate (CST) laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both Sr-85 and Cs-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor (D{sub F}) for Sr-85 with MST impregnated filter membrane cartridges measured 26, representing 96% Sr-85 removal efficiency. On the other hand, the Sr-85 instantaneous D{sub F} with co-sintered active MST cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the MST impregnated membrane cartridges and CST impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active MST cartridges and co-sintered active CST cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of Cs-137 with co-sintered CST cartridges. Tests results with CST impregnated membrane cartridges for Cs-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating MST and CST sorbents into membranes represent a promising method for the semi-continuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.

  1. Rational Design of Cesium-Selective Ionophores and Chemosensors: Dihydrocalix[4]arene Crown-6 Ethers

    Energy Technology Data Exchange (ETDEWEB)

    Sachleben, Richard A.; Bryan, Jeffrey C.; Brown, Gilbert M.; Engle, Nancy L.; Haverlock, Tamara J.; Hay, Benjamin P.; Urvoas, Agathe; Moyer, Bruce A.

    2003-12-15

    Molecular mechanics calculations performed on calix[4]arene crown-6 ethers predict that the 1,3-dihydro derivatives will exhibit greater complementarity for potassium and cesium ions than the parent 1,3-dialkoxy calix crowns. The X-ray crystal structures of 1,3-alt bis-octyloxycalix[4]arene benzocrown-6 ether, dihydrocalix[4]arene benzocrown-6 ether, and the cesium nitrate complex of dihydrocalix[4]arene benzocrown-6 ether were determined. The cesium complex structure corresponds closely to the structure predicted by molecular mechanics. The dihydrocalix[4]arene crown-6 ethers exhibit enhanced cesium selectivity in the extraction of alkali metal salts and provide a platform for a highly sensitive and selective cesium chemosensor.

  2. [Variation in amount of radioactive cesium before and after cooking dry shiitake and beef].

    Science.gov (United States)

    Nabeshi, Hiromi; Tsutsumi, Tomoaki; Hachisuka, Akiko; Matsuda, Rieko

    2013-01-01

    We investigated the change of radioactive cesium content in food due to cooking in order to estimate the internal radiation exposure due to from radioactive materials in food. Our results revealed that soaking dry shiitake in water decreased the radioactive cesium content by about 50%, compared with that present in uncooked shiitake. Radioactive cesium in beef was decreased by about 10%, 12%, 60-65% and 80% by grilling, frying, boiling and stewing, respectively, compared to uncooked beef. For cooked beef, the decrease in the ratio of radioactive cesium was significantly different among the types of cooking. The decrease ratio of radioactive cesium in boiled and stewed beef was 8 times higher than that in grilled and fried beef.

  3. Sensitive Detection of Cold Cesium Molecules by Radiative Feshbach Spectroscopy

    OpenAIRE

    Chin, Cheng; Kerman, Andrew J.; Vuletić, Vladan; Chu, Steven

    2002-01-01

    We observe the dynamic formation of $Cs_2$ molecules near Feshbach resonances in a cold sample of atomic cesium using an external probe beam. This method is 300 times more sensitive than previous atomic collision rate methods, and allows us to detect more than 20 weakly-coupled molecular states, with collisional formation cross sections as small as $\\sigma =3\\times 10^{-16}$cm$^2$. We propose a model to describe the atom-molecule coupling, and estimate that more than $2 \\times 10^5$ $Cs_2$ mo...

  4. Characterizing optical dipole trap via fluorescence of trapped cesium atoms

    Institute of Scientific and Technical Information of China (English)

    LIU; Tao; GENG; Tao; YAN; Shubin; LI; Gang; ZHANG; Jing; WANG; Junmin; PENG; Kunchi; ZHANG; Tiancai

    2006-01-01

    Optical dipole trap (ODT) is becoming an important tool of manipulating neutral atoms. In this paper ODT is realized with a far-off resonant laser beam strongly focused in the magneto-optical trap (MOT) of cesium atoms. The light shift is measured by simply monitoring the fluorescence of the atoms in the magneto-optical trap and the optical dipole trap simultaneously. The advantages of our experimental scheme are discussed, and the effect of the beam waist and power on the potential of dipole trap as well as heating rate is analyzed.

  5. Cesium fallout in Norway after the Chernobyl accident

    International Nuclear Information System (INIS)

    Results of country-wide measurements of 137Cs and 134 Cs in soil samples in Norway after the Chernobyl accident are reported. The results clearly demonstrates that municipalities in the central part of southern Norway, Troendelag and the southern part of Nordland, have been rather heavily contaminated. The total fallout of 137Cs and 134Cs from the Chernobyl accident in Norway is estimated to 2300 TBq and 1200 TBq, respectively. This is approximately 6% of the cesium activity released from the reactor

  6. Dynamic Studies with Radioisotopes in Medicine. Proceedings of the Symposium on Dynamics Studies with Radioisotopes in Clinical Medicine and Research

    International Nuclear Information System (INIS)

    Observations on the temporal patterns of uptake, metabolism, clearance or excretion of administered radioactive materials form the basis of many important applications of radioisotopes in clinical medicine and research. Such applications include studies of organ function, of regional blood flow and of the turnover of various substances in the human body. Newly available radioisotopes, new instruments such as gamma came ras, new techniques and new methods of data analysis based on the use of analogue and digital computers are continually enlarging the scope of the applications. Progress in these matters was discussed at the Symposium on Dynamic Studies with Radioisotopes in Clinical Medicine and Research, organized by the lnternational Atomic Energy Agency and held in Rotterdam, The Netherlands, from 31 August to 4 September 1970. A total of 315 participants nominated by 39 countries and 4 international organizations attended, and the 70 papers presented cove r the theoretical aspects of dynamic studies, the development of techniques and instruments for such studies, and specific applications in studies of thyroid, renal, hepatic and splenic function, mineral metabolism, regional blood flow, and cardiac and pulmonary function. The proceedings include the full texts of all the papers presented together with the edited discussions. Invited review papers deal with the general aspects of the various main groups of applications covered. Many of the applications described have already reached the stage of routine use; others are still in the developmental stage. Of particular note in the latter connection are applications based on the quantitative analysis of scintillation camera data. The many papers presented on these topics and the ensuing discussions indicate the great interest now shown in this promising area of development. It is hoped that the proceedings will provide a valuable guide to the present status of the subject

  7. Particle-beam accelerators for radiotherapy and radioisotopes

    International Nuclear Information System (INIS)

    The philosophy used in developing the new PIGMI technology was that the parameters chosen for physics research machines are not necessarily the right ones for a dedicated therapy or radioisotope machine. In particular, the beam current and energy can be optimized, and the design should emphasize minimum size, simplicity and reliability of operation, and economy in capital and operating costs. A major part of achieving these goals lay in raising the operating frequency and voltage gradient of the accelerator, which shrinks the diameter and length of the components. Several other technical innovations resulted in major system improvements. One of these is a radically new type of accelerator structure named the radio-frequency quadrupole (RFQ) accelerator. This allowed us to eliminate the large, complicated ion source used in previous ion accelerators, and to achieve a very high quality accelerated beam. Also, by using advanced permanent magnet materials to make the focusing elements, the system becomes much simpler. Other improvements have been made in all of the accelerator components and in the methods for operating them. These will be described, and design and costing information examples given for several possible therapy and radioisotope production machines

  8. Radioisotope Thermoelectric Generator Options for Pluto Fast Flyby Mission

    Science.gov (United States)

    Schock, Alfred

    1994-07-01

    A small spacecraft design for the Pluto Fast Flyby (PFF) mission is under study by the Jet Propulsion Laboratory (PL) for the National Aeronautics and Space Administration (NASA), for a possible launch as early as 1998. JPL's 1992 baseline design calls for a power source able to furnish an energy output of 3963 kWh and a power output of 69 Watts(e) at the end of the 9.2-year mission. Satisfying those demands is made difficult because NASA management has set a goal of reducing the spacecraft mass from a baseline value of 166 kg to ~110 kg, which implies a mass goal of less than 10 kg for the power source. To support the ongoing NASA/JPL studies, the Department of Energy's Office of Special Applications (DOE/OSA) commissioned Fairchild Space to prepare and analyze conceptual designs of radioisotope power systems for the PFF mission. Thus far, a total of eight options employing essentially the same radioisotope heat source modules were designed and subjected to thermal, electrical, structural, and mass analyses by Fairchild. Five of these - employing thermoelectric converters - are described in the present paper, and three - employing free-piston Stirling converters - are described in the companion paper presented next. The system masses of the thermoelectric options ranged from 19.3 kg to 10.2 kg. In general, the options requiring least development are the heaviest, and the lighter options require more development with greater programmatic risk.

  9. Multi-Watt Small Radioisotope Thermoelectric Generator Conceptual Design Study

    Science.gov (United States)

    Determan, William R.; Otting, William; Frye, Patrick; Abelson, Robert; Ewell, Richard; Miyake, Bob; Synder, Jeff

    2007-01-01

    A need has been identified for a small, light-weight, reliable power source using a radioisotope heat source, to power the next generation of NASA's small surface rovers and exploration probes. Unit performance, development costs, and technical risk are key criteria to be used to select the best design approach. Because safety can be a major program cost and schedule driver, RTG designs should utilize the DOE radioisotope safety program's data base to the maximum extent possible. Other aspects important to the conceptual design include: 1) a multi-mission capable design for atmospheric and vacuum environments, 2) a module size based on one GPHS Step 2 module, 3) use of flight proven thermoelectric converter technologies, 4) a long service lifetime of up to 14 years, 5) maximize unit specific power consistent with all other requirements, and 6) be ready by 2013. Another critical aspect of the design is the thermal integration of the RTG with the rover or probe's heat rejection subsystem and the descent vehicle's heat rejection subsystem. This paper describes two multi-watt RTG design concepts and their integration with a MER-class rover.

  10. Sodium Variable Conductance Heat Pipe for Radioisotope Stirling Systems

    Science.gov (United States)

    Tarau, Calin; Anderson, William G.; Walker, Kara

    2009-01-01

    In a Stirling radioisotope system, heat must continually be removed from the General Purpose Heat Source (GPHS) modules to maintain the modules and surrounding insulation at acceptable temperatures. Normally, the Stirling convertor provides this cooling. If the converter stops in the current system, the insulation is designed to spoil, preventing damage to the GPHS, and also ending the mission. An alkali-metal Variable Conductance Heat Pipe (VCHP) has been designed to allow multiple stops and restarts of the Stirling convertor in an Advanced Stirling Radioisotope Generator (ASRG). When the Stirling convertor is turned off, the VCHP will activate when the temperatures rises 30 C above the setpoint temperature. A prototype VCHP with sodium as the working fluid was fabricated and tested in both gravity aided and against gravity conditions for a nominal heater head temperature of 790 C. The results show very good agreement with the predictions and validate the model. The gas front was located at the exit of the reservoir when heater head temperature was 790 C while cooling was ON, simulating an operating Advanced Stirling Converter (ASC). When cooling stopped, the temperature increased by 30 C, allowing the gas front to move past the radiator, which transferred the heat to the case. After resuming the cooling flow, the front returned at the initial location turning OFF the VCHP. The against gravity working conditions showed a colder reservoir and faster transients.

  11. Radioisotope flaw detection during the inspection of the NPS equipment

    International Nuclear Information System (INIS)

    The radioisotope method for non-destructive inspection is widely used in the USSR because of its specific features and advantages, namely, the possibility to inspect the items made of various materials, with a wide range of thickness, or located in places access to which is difficult, in the case of absence of power supply, under the effect of high level radiation background, etc. The methods and means of radioisotope flaw detection are used for the following fields of nuclear power engineering: inspection of the equipments during the scheduled preventive and major repairs of nuclear power stations (NPS); during the mounting and assembling of nuclear reactors; and during the manufacture of NPS equipments on the shop scale. Some features and specifications of such facilities are described briefly. The All-Union Scientific Research Institute of Radiation Engineering carries out the investigations connected not only with the apparatuses for flaw detection, but also with their effective applications. As the results of the performed investigations, a method of optimizing instrumental parameters based on the sensitivity and expense, the influence of different factors upon the selected criteria, the radiation exposure dose rate, etc., were suggested. It must be noted that the economical effect produced by the optimization of the technical characteristics of the instruments intended for the inspection has been obtained, as a rule, without additional capital expenses. (Wakatsuki, Y.)

  12. The radioisotope osteogram: Kinetic studies of skeletal disorders in humans

    Energy Technology Data Exchange (ETDEWEB)

    MacDonald, N.S.

    1959-10-16

    Radioactive strontium can serve as a tracer to gain information concerning calcium metabolism in human subjects. Gamma-emitting Sr{sup 85} is used rather than the much more hazardous, beta-emitting Sr{sup 89} and Sr{sup 90}. (ca{sup 47} -- the ideal tracer for normal calcium -- is quite expensive and difficult to procure.) Very significant information may be obtained merely by measuring and recording the changes in radioactivity in various body areas during the first hour after intravenous injection of the bone-seeking radioisotope. This is accomplished by placing a lead-shielded gamma-scintillation detector in contact with the skin over the sites of interest and recording the activities on a scaler or ratemeter. The activity versus time curves so obtained are called radioisotope osteograms. Data were presented which indicated that Sr{sup 85} osteograms for patients afflicted with osteoporosis, Paget`s disease, tumor metastases to bone, and possibly multiple myeloma, differ significantly from those obtained from subjects with no skeletal abnormalities. Some interpretations of these deviations were discussed. The value of conducting double-tracer tests (e.g. -- Sr{sup 85} plus radio-iodinated serum albumin) was demonstrated, and correlations with excretion data were made. With further refinements the technique may ultimately become useful for certain diagnostic problems in the clinic and.for evaluating the efficacy of treatment of these disorders.

  13. Preliminary studies of Brazilian wood using different radioisotopic sources

    International Nuclear Information System (INIS)

    Due to availability and particular features, wood was one of the first materials used by mankind with a wide variety of applications. It can be used as raw material for paper and cellulose manufacturing; in industries such as chemical, naval, furniture, sports goods, toys, and musical instrument; in building construction and in the distribution of electric energy. Wood has been widely researched; therefore, wood researchers know that several aspects such as temperature, latitude, longitude, altitude, sunlight, soil, and rainfall index interfere with the growth of trees. This behavior explains why average physical-chemical properties are important when wood is studied. The majority of researchers consider density to be the most important wood property because of its straight relationship with the physical and mechanical properties of wood. There are three types of wood density: basic, apparent and green. The apparent density was used here at 12% of moisture content. In this study, four different types of wood were used: 'freijo', 'jequetiba', 'muiracatiara' and 'ipe'. For wood density determination by non-conventional method, Am-241, Ba-133 and Cs-137 radioisotopic sources; a NaI scintillation detector and a counter were used. The results demonstrated this technique to be quick and accurate. By considering the nuclear parameters obtained as half value layers and linear absorption coefficients, Cs-137 radioisotopic source demonstrated to be the best option to be used for inspection of the physical integrity of electric wooden poles and live trees for future works. (author)

  14. [Clinical study of radioisotopic splenoportography in portal hypertension].

    Science.gov (United States)

    Yokoyama, Y

    1990-02-01

    Radioisotopic splenoportography was performed in 55 patients with portal hypertension, in whom 52 had various degrees of esophagogastric varices, and in 20 patients without portal hypertension. In the patients with varices, collateral images were obtained in 50 patients (96%) by this method and no image was obtained in the patients without varices. The rate of positively imaged collaterals was as follows: Esophageal varices 69%, the left gastric vein 85%, the short gastric veins 48%, RI stasis in esophagogastric region 65%, the azygos vein 46%, the subclavian vein 25%, the para-umbilical veins 46%, splenorenal /gastrorenal shunts 19%, the inferior mesenteric vein 17%, the left intercostal veins 6%, and Arantius's duct 4%. These rates were superior to that obtained from the conventional transarterial portography. There were some correlations between RI-images by this method and clinical and laboratory findings; patients with ascending collaterals alone tended to have extensive and severe varices and higher rate of bleeding, on the other hand, variceal bleeding was not found and episodes of portosystemic encephalopathy frequently occurred in patients with descending collaterals alone. After successful sclerotherapy, RI-images of esophageal varices disappeared in 92% of the patients. Radioisotopic splenoportography appears to be a useful diagnostic and follow-up modality for patients with portal hypertension and esophagogastric varices. PMID:2325608

  15. Radioisotope Electric Propulsion for Deep Space Sample Return

    Energy Technology Data Exchange (ETDEWEB)

    Noble, Robert J.; /SLAC

    2009-07-14

    The need to answer basic questions regarding the origin of the Solar System will motivate robotic sample return missions to destinations like Pluto, its satellite Charon, and objects in the Kuiper belt. To keep the mission duration short enough to be of interest, sample return from objects farther out in the Solar System requires increasingly higher return velocities. A sample return mission involves several complicated steps to reach an object and obtain a sample, but only the interplanetary return phase of the mission is addressed in this paper. Radioisotope electric propulsion is explored in this parametric study as a means to propel small, dedicated return vehicles for transferring kilogram-size samples from deep space to Earth. Return times for both Earth orbital rendezvous and faster, direct atmospheric re-entry trajectories are calculated for objects as far away as 100 AU. Chemical retro-rocket braking at Earth is compared to radioisotope electric propulsion but the limited deceleration capability of chemical rockets forces the return trajectories to be much slower.

  16. Evaluation of radioisotopic angiocardiography in patent ductus arteriosus

    International Nuclear Information System (INIS)

    Dynamic images and curves obtained from radioisotopic angiocardiography (RI-ACG) using video recording system were studied in 5 patients with patent ductus arteriosus (PDA), to disclose any characteristic findings of PDA on this radioisotopic examination. And, the examination was evaluated with referance to diagnosis and assessment of status of PDA, comparing with other radiological examinations including angiocardiography and catheterization. Both the dynamic images and the dynamic curves of RI-ACG showed some characteristic findings of PDA, which was considered to be valuable to differentiate the intracardiac left to right shunt in atrial or ventricular septal defect. It was very characteristic of PDA that dynamic images showed regional dilution and recirculation patterns in the region of the main pulmonary artery to its periphery, and dynamic curves presented shunt waves on the descending limbs of the first circulation waves of both the pulmonary and the left ventricular region of interest. The Degrees of appearance of these characteristic findings showed a tendency to well correlate with the value of the left to right shunt fraction calculated by cathetelization technique. On the other hand, RI-ACG showed useful findings to diagnose pulmonary hypertension or heart failure associated with PDA. And, RI-ACG was very useful to detect an abrupt change of the central circulation dynamics in a patient with PDA, in whom continuous murmur characteristic of PDA desappeared intermittently. (author)

  17. Characterization of the Advanced Stirling Radioisotope Generator Engineering Unit 2

    Science.gov (United States)

    Lewandowski, Edward J.; Oriti, Salvatore M.; Schifer, Niholas A.

    2016-01-01

    Significant progress was made developing the Advanced Stirling Radioisotope Generator (ASRG) 140-W radioisotope power system. While the ASRG flight development project has ended, the hardware that was designed and built under the project is continuing to be tested to support future Stirling-based power system development. NASA Glenn Research Center recently completed the assembly of the ASRG Engineering Unit 2 (EU2). The ASRG EU2 consists of the first pair of Sunpower's Advanced Stirling Convertor E3 (ASC-E3) Stirling convertors mounted in an aluminum housing, and Lockheed Martin's Engineering Development Unit (EDU) 4 controller (a fourth-generation controller). The ASC-E3 convertors and Generator Housing Assembly (GHA) closely match the intended ASRG Qualification Unit flight design. A series of tests were conducted to characterize the EU2, its controller, and the convertors in the flight-like GHA. The GHA contained an argon cover gas for these tests. The tests included measurement of convertor, controller, and generator performance and efficiency; quantification of control authority of the controller; disturbance force measurement with varying piston phase and piston amplitude; and measurement of the effect of spacecraft direct current (DC) bus voltage on EU2 performance. The results of these tests are discussed and summarized, providing a basic understanding of EU2 characteristics and the performance and capability of the EDU 4 controller.

  18. Industrial applications of radioisotopes: techniques and procedures of (NTIS) Nuclear Techniques Industrial Service

    International Nuclear Information System (INIS)

    Radioisotope handling procedures followed by personnel of the Nuclear Techniques Industrial Service (NTIS) during the conduction of investigations in industry are described. Possible radiological implications as a result of the various measuring techniques and different types of plants are discussed. Conditions under which permanent authorization has been granted for the use of radioisotopes are mentioned

  19. Economical and technical feasibility study of some radioisotopes production for medical application

    International Nuclear Information System (INIS)

    The economical and technical feasibility study of the production in reactors of some radioisotopes most used in medicine, are presented. The clinical applications of each radioisotope as well as its radioactive concentrations and specific activities are related. Irradiation procedures based in the foregoing data are given. Part of the study is dedicated to quality control. (M.A.C.)

  20. First collinear laser spectroscopy measurements of radioisotopes from an IGISOL ion source

    NARCIS (Netherlands)

    Billowes, J; Campbell, P; Cochrane, ECA; Cooke, JL; Dendooven, P; Evans, DE; Grant, IS; Griffith, JAR; Honkanen, A; Huhta, M; Levins, JMG; Liukkonen, E; Oinonen, M; Pearson, MR; Penttila, H; Persson, B.L.; Richardson, DS; Tungate, G; Wheeler, P; Zybert, L; Aysto, J

    1997-01-01

    The standard Doppler-free technique of collinear laser spectroscopy has been successfully applied to radioisotopes from the ion-guide isotope separator (IGISOL) at the Universiry of Jyvaskyla. The laser resonance fluorescence signals for the Ba-140.142,Ba-144 radioisotopes show that the ion beam ene

  1. Practice of the safe handling of radioisotopes using naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    We proposed a practical protocol for the safe handling of radiation and radioisotopes using the naturally occurring radioactive materials (NORMs) 87Rb and 40K. The protocol can be utilized for the education and training course for radiation handling workers. Rubidium chloride solutions were used for the practice of dilution of unsealed radioisotopes instead of 32P. Rubidium chloride and potassium chloride solid radiation sources were used for the practice of monitoring of the surface contamination using the GM survey meter instead of 32P and 14C. Rubidium chloride solutions were also used for the practice of the contamination check by the smear method. Substitution of the radioisotopes under the Laws Concerning the Prevention from Radiation Hazards due to Radioisotope and others to NORMs can be successfully achieved without notable demerits. We supposed that most of the practice for the safe handling of radioisotopes could be carried out outside a controlled area. (author)

  2. Systems for control of weighting out with radioisotope measuring transducers for light industry enterprises

    International Nuclear Information System (INIS)

    The works of the Riga scientific research institute of radioisotope instrument making in the field of development of radioisotope systems for control of weighting out of textiles and synthetic leather are described. Radioisotope transducers have been constructed on the basis of the effect of attenuation of β-radiation used for raying the controlled material. Examples are given of radioisotope devices created at the Institute for control of woolen cloth humidity, surface density of fibrous base of synthetic leather, for control of weighting out of non-woven fabrics, for control of linear density of flaxen and kenaf bands etc. The problems of metrological provision of radioisotope devices and automatic control systems, and economic efficiency of their application are considered

  3. Morphological and electrical properties of zirconium vanadate doped with cesium

    Directory of Open Access Journals (Sweden)

    Marwa F. Elkady

    2014-09-01

    Full Text Available Cesium doped zirconium vanadate ZrV2O7 with different Cs dopant content (Cs/Zr varied from 0 to 0.5 in weight ratio were fabricated by hydrothermal technique at 120 °C for 60 min. The synthesized materials are thermally treated using microwave technique. The structural and morphological properties of the synthesized materials and thermally treated samples were investigated using XRD and SEM respectively. It was evident that all synthesized specimens have cubic phase structural without any extra phase but after heat treatment Orthorhombic phase appear with doped samples. However, the morphological structure of the doped synthesized materials has transferred from nanoparticles into rods aspect with heat treatment for the different dopant ratio. Moreover, the electrical properties of both the synthesized and thermally treated materials are studied by AC impedance measurements. The results indicated that the ionic conductivity of Cs-doped ZrV2O7 materials decreased by increasing the dopant ratio while that thermally treated samples the ionic conductivity increase by increasing the dopant ratio. Finally, the concentration of cesium dopants is found to play crucial role in tuning the morphology and electrical properties of nanostructures.

  4. Transportable cesium irradiator (TPCI): Final safety analysis report: Revision 1

    International Nuclear Information System (INIS)

    This Final Safety Analysis Report describes the Transportable Cesium Irradiator (TPCI) and assesses the hazards associated with its operation. The TPCI consists of a mobile, lead-shielded, irradiation unit with support equipment mounted within an enclosed trailer. The irradiation unit has two basic compartments; a source chamber sized to mate with the transportation cask which houses the source capsules, and an irradiation chamber formed as a large shielded cylinder (drum) with a window. The irradiation chamber is mounted on a large diameter support bearing. As this chamber is rotated its window moves from the product access door, where produce is inserted or extracted, to a position in line with a similar window in the source chamber. When the windows are aligned the produce is irradiated, while the back wall of the irradiation chamber shields the product access door. The TPCI is designed to be transported throughout the continental United States. The transportation cask containing the cesium source capsules is transported separately from the irradiation unit and is installed when the TPCI unit has been readied for operation at a particular site. The transportation cask is a separate unit and is documented in a separate FSAR

  5. Kelvin probe studies of cesium telluride photocathode for AWA photoinjector

    Energy Technology Data Exchange (ETDEWEB)

    Wisniewski, Eric E., E-mail: ewisniew@anl.gov [High Energy Physics Division, Argonne National Laboratory, 9700 S. Cass, Lemont, IL 60439 (United States); Physics Department, Illinois Institute of Technology, 3300 South Federal Street, Chicago, IL 60616 (United States); Velazquez, Daniel [High Energy Physics Division, Argonne National Laboratory, 9700 S. Cass, Lemont, IL 60439 (United States); Physics Department, Illinois Institute of Technology, 3300 South Federal Street, Chicago, IL 60616 (United States); Yusof, Zikri, E-mail: zyusof@hawk.iit.edu [High Energy Physics Division, Argonne National Laboratory, 9700 S. Cass, Lemont, IL 60439 (United States); Physics Department, Illinois Institute of Technology, 3300 South Federal Street, Chicago, IL 60616 (United States); Spentzouris, Linda; Terry, Jeff [Physics Department, Illinois Institute of Technology, 3300 South Federal Street, Chicago, IL 60616 (United States); Sarkar, Tapash J. [Rice University, 6100 Main, Houston, TX 77005 (United States); Harkay, Katherine [Accelerator Science Division, Argonne National Laboratory, 9700 S. Cass, Lemont, IL 60439 (United States)

    2013-05-21

    Cesium telluride is an important photocathode as an electron source for particle accelerators. It has a relatively high quantum efficiency (>1%), is sufficiently robust in a photoinjector, and has a long lifetime. This photocathode is grown in-house for a new Argonne Wakefield Accelerator (AWA) beamline to produce high charge per bunch (≈50nC) in a long bunch train. Here, we present a study of the work function of cesium telluride photocathode using the Kelvin probe technique. The study includes an investigation of the correlation between the quantum efficiency and the work function, the effect of photocathode aging, the effect of UV exposure on the work function, and the evolution of the work function during and after photocathode rejuvenation via heating. -- Highlights: ► The correlation between Quantum Efficiency (QE) and work function. ► How QE and work function evolve together. ► Rejuvenation of the photocathode via heating and the effect on work function. ► The effects on the work function due to exposure to UV light.

  6. Structure and bonding in crystalline cesium uranyl tetrachloride under pressure.

    Science.gov (United States)

    Osman, Hussien H; Pertierra, Pilar; Salvadó, Miguel A; Izquierdo-Ruiz, F; Recio, J M

    2016-07-21

    A thorough investigation of pressure effects on the structural properties of crystalline cesium uranyl chloride was performed by means of first-principles calculations within the density functional theory framework. Total energies, equilibrium geometries and vibrational frequencies were computed at selected pressures up to 50 GPa. Zero pressure results present good agreement with available experimental and theoretical data. Our calculated equation of state parameters reveal that Cs2UO2Cl4 is a high compressible material, similar to other ionic compounds with cesium cations, and displays a structural anisotropic behavior guided by the uranyl moiety. An unexpected variation of the U-O bond length, dUO, is detected as pressure is applied. It leads to a dUO-stretching frequency relationship that cannot be described by the traditional Badger's rule. Interestingly enough, it can be explained in terms of a change in the main factor controlling dUO. At low pressure, the charge transferred to the uranyl cation induces an increase of the bond length and a red shift of the stretching frequencies, whereas it is the mechanical effect of the applied pressure above 10 GPa that is the dominant factor that leads to a shortening of dUO and a blue shift of the stretching frequencies. PMID:27340008

  7. Spectrally selective optical pumping in Doppler-broadened cesium atoms

    Institute of Scientific and Technical Information of China (English)

    Zhang Jun-Hai; Zeng Xian-Jin; Li Qing-Meng; Huang Qiang; Sun Wei-Min

    2013-01-01

    The D1 line spectrally selective pumping process in Doppler-broadened cesium is analyzed by solving the optical Bloch equations.The process,described by a three-level model with the A scheme,shows that the saturation intensity of broadened atoms is three orders of magnitude larger than that of resting atoms.The |Fg =3> → |Fe-4> resonance pumping can result in the ground state |Fg =4,mF =4> sublevel having a maximum population of 0.157 and the population difference would be about 0.01 in two adjacent magnetic sublevels of the hyperfine (HF) state Fg =4.To enhance the anisotropy in the ground state,we suggest employing dichromatic optical HF pumping by adding a laser to excite D1 line |Fg =4> → |Fe =3>transition,in which the cesium magnetometer sensitivity increases by half a magnitude and is unaffected by the nonlinear Zeeman effect even in Earth's average magnetic field.

  8. Structure and bonding in crystalline cesium uranyl tetrachloride under pressure.

    Science.gov (United States)

    Osman, Hussien H; Pertierra, Pilar; Salvadó, Miguel A; Izquierdo-Ruiz, F; Recio, J M

    2016-07-21

    A thorough investigation of pressure effects on the structural properties of crystalline cesium uranyl chloride was performed by means of first-principles calculations within the density functional theory framework. Total energies, equilibrium geometries and vibrational frequencies were computed at selected pressures up to 50 GPa. Zero pressure results present good agreement with available experimental and theoretical data. Our calculated equation of state parameters reveal that Cs2UO2Cl4 is a high compressible material, similar to other ionic compounds with cesium cations, and displays a structural anisotropic behavior guided by the uranyl moiety. An unexpected variation of the U-O bond length, dUO, is detected as pressure is applied. It leads to a dUO-stretching frequency relationship that cannot be described by the traditional Badger's rule. Interestingly enough, it can be explained in terms of a change in the main factor controlling dUO. At low pressure, the charge transferred to the uranyl cation induces an increase of the bond length and a red shift of the stretching frequencies, whereas it is the mechanical effect of the applied pressure above 10 GPa that is the dominant factor that leads to a shortening of dUO and a blue shift of the stretching frequencies.

  9. A study of strontium and cesium sorption on granite

    International Nuclear Information System (INIS)

    The diffusion and sorption of cesium and strontium in crushed granite particles is discussed. Sorption experiments have been performed with one granite from Finnsjoen outside Forsmark on the east coast of Sweden and one granite from the Stripa mine in central Sweden. Granite samples have been crushed and screened, and six different particle size fractions from 0.10-0.12 mm to 4-5 mm of each rock have been used in the experiments. The initial concentrations of inactive cesium and strontium were 10-15 ppm. The experimental data indicate that the amount of sorption is dependent not only on the mass of granite particles, but also to some extent on the size of the particles. An attempt has been made to distinguish between sorption on external surfaces and inner surfaces. The amount of external surface adsorption was found to vary from 15-40 % of the total adsorption capacity for the particle size fraction 0.10-0.12 mm to a few percent or less for the largest particles used. (Auth.)

  10. Diffusion of strontium, technetium, iodine and cesium in granitic rock

    International Nuclear Information System (INIS)

    The migration of strontium, technetium, iodine and cesium in granitic rock has been studied. Rock samples were taken from drilling cores in granitic and granodioritic rock, and small (2x2x2 cm) rock tablets from the drilling cores were exposed to a groundwater solution containing one of the studied elements at trace levels. The concentration of the element versus penetration depth in the rock tablet was measured radiometrically. The sorption on the mineral faces and the diffusion into the rock were studied by an autoradiographic technique. The cationic strontium and cesium have apparent diffusivities of 10-13 - 10-14 m2/s. The migration is confined to microfissures or filled fractures containing e.g., calcite, epidote or chlorite or in veins with high capacity minerals (e.g. biotite). The anionic iodine and technetium have apparent diffusivities of about 10-14 m2/s. These species migrate along mineral boundaries and in open fractures and to a minor extent in high capacity mineral veins. (orig.)

  11. High purity materials as targets for radioisotope production: Needs and challenges

    Indian Academy of Sciences (India)

    V Shivarudrappa; K V Vimalnath

    2005-07-01

    Radionuclides have become powerful and indispensable tools in many endeavours of human activities, most importantly in medicine, industry, biology and agriculture, apart from R&D activities. Ready availability of radionuclides in suitable radiochemical form, its facile detection and elegant tracer concepts are responsible for their unprecedented use. Application of radioisotopes in medicine has given birth to a new branch, viz. nuclear medicine, wherein radioisotopes are used extensively in the diagnosis and treatment of variety of diseases including cancer. Artificial transmutation of an element employing thermal neutrons in a reactor or high energy particle accelerators (cyclotrons) are the routes of radioisotope production world over. Availability of high purity target materials, natural or enriched, are crucial for any successful radioisotope programme. Selection of stable nuclides in suitable chemical form as targets with desired isotopic and chemical purity are among the important considerations in radioisotope production. Mostly the oxide, carbonate or the metal itself are the preferred target forms for neutron activation in a research reactor. Chemical impurities, particularly from the elements of the same group, put a limitation on the purity of the final radioisotope product. Whereas the isotopic impurities result in the production of undesirable radionuclidic impurities, which affect their effective utilization. Isotope Group, BARC, is in the forefront of radioisotope production and supply in the country, meeting demands for gamut of radioisotope applications indigenously for over four decades now. Radioisotopes such as 131I, 99Mo, 32P, 51Cr, 153Sm, 82Br, 203Hg, 198Au etc are produced in TBq quantities every month and supplied to several users and to Board of Radiation and Isotope Technology (BRIT). Such a large production programme puts a huge demand on the reliable sources of availability of high purity target materials which are at present mostly met

  12. Active Radiation Level Measurement on New Laboratory Instrument for Evaluating the Antibacterial Activity of Radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Joh, Eunha; Park, Jang Guen [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    A disc method has been widely used to measure the antibacterial effect of chemical agents. However, it is difficult to measure the antibacterial effect of radioisotopes using a disc method. A disc method is a method for diffusing a drug by placing the drug containing disc on the medium. In this method, radioisotopes are diffused on the medium and it is difficult to measure the exact effect by radiation. Thus, new laboratory equipment needs to evaluate the antibacterial activity by the radioisotopes. In this study, we measured the radiation level of radioisotopes on a new laboratory instrument using a MCNP. A disc method has been widely used to measure the antibacterial effect of chemical agents. This method uses a drug diffusion system for the measurement of anti-bacterial antibiotics. To measure the antimicrobial activity of a radioisotope, a new type of laboratory instrument is necessary to prevent the drug from spreading. The radioisotopes are used to diagnose and treat cancer. However, studies for anti-biotical use have not progressed. The radiation of radioisotopes has the effect of killing bacteria. Before this study proceeds further, it is necessary to be able to measure the antimicrobial activity of the radioisotope easily in the laboratory. However, in this study, it was possible to measure the antimicrobial activity of the radioisotope in the laboratory using a new laboratory instrument. We intend to start evaluation studies of the antibacterial activity of specific radioisotopes. In addition, it will be possible to develop research to overcome diseases caused by bacteria in the future.

  13. Radioisotopes and Radiation in Animal and Plant Insect Pest Control

    International Nuclear Information System (INIS)

    Crop-pest control is of major economic importance and demands the aid of the latest advances in science. Radioisotopes and radiation are being employed to increase the efficiency of existing insect pest control. They are extremely valuable, since improvements to existing methods depend on having detailed data on the bioecology, toxicology, and so on. Radioactive labelling of insects has been extremely promising in bioecology; the labelling of grain pests (Eurygaster integriceps Put., Hadena sordida Skh.) and grain-pest parasites (Meniscus agnatus Crow, Pseudogonia cinerascens Rond.) has provided information about their areas of migration, habitats, sizes of population and the feeding habits. The same technique was used to determine the rate of propagation of the Colorado beetle (Leptinotarsa decemlineota Say), which is subject to quarantine controls; subsequently an extermination programme was carried out on the basis of the data obtained. It also provides a valuable means of studying the extremely complex problems of parasitism and predaceousness, in particular intermediate feeding cycles and chemotaxis. The feeding areas of field rodents have been mapped out with the help of a self-labelling, radioactive-bait technique. Pesticides synthesized with radioisotopes have been used in conjunction with radiochromatography, fluorimetry and other techniques to study the highly complex biochemical processes caused to toxicants in plants and insects. It has also been possible to determine the rate of hydrolysis of organic-phosphorus insecticide compounds of the thiphos and metaphos type as a function of the degree of development and the physiological state of plants as well as of environmental conditions. Data have been obtained on the length of time residual quantities of toxicants are retained in agriculture products following different periods of chemical treatment. Radioisotope techniques have yielded information on various metabolic processes exhibiting different

  14. Equilibrium, kinetic and thermodynamic study of cesium adsorption onto nanocrystalline mordenite from high-salt solution.

    Science.gov (United States)

    Lee, Keun-Young; Park, Minsung; Kim, Jimin; Oh, Maengkyo; Lee, Eil-Hee; Kim, Kwang-Wook; Chung, Dong-Yong; Moon, Jei-Kwon

    2016-05-01

    In this study, the equilibrium, kinetics and thermodynamics of cesium adsorption by nanocrystalline mordenite were investigated under cesium contamination with high-salt solution, simulating the case of an operation and decommissioning of nuclear facilities or an accident during the processes. The adsorption rate constants were determined using a pseudo second-order kinetic model. The kinetic results strongly demonstrated that the cesium adsorption rate of nano mordenite is extremely fast, even in a high-salt solution, and much faster than that of micro mordenite. In the equilibrium study, the Langmuir isotherm model fit the cesium adsorption data of nano mordenite better than the Freundlich model, which suggests that cesium adsorption onto nano mordenite is a monolayer homogeneous adsorption process. The obtained thermodynamic parameters indicated that the adsorption involved a very stable chemical reaction. In particular, the combination of rapid particle dispersion and rapid cesium adsorption of the nano mordenite in the solution resulted in a rapid and effective process for cesium removal without stirring, which may offer great advantages for low energy consumption and simple operation. PMID:26683820

  15. Preliminary Evaluation of Cesium Distribution for Wet Sieving Process Planned for Soil Decontamination in Japan - 13104

    Energy Technology Data Exchange (ETDEWEB)

    Enokida, Y.; Tanada, Y.; Hirabayashi, D. [Graduate School of Engineering, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan); Sawada, K. [EcoTopia Science Institute, Nagoya University, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan)

    2013-07-01

    For the purpose of decontaminating radioactive cesium from a huge amount of soil, which has been estimated to be 1.2x10{sup 8} m{sup 3} by excavating to a 5-cm depth from the surface of Fukushima Prefecture where a severe nuclear accident occurred at TEPCO's power generating site and has emitted a significant amount of radioactive materials, mainly radioactive cesium, a wet sieving process was selected as one of effective methods available in Japan. Some private companies have demonstrated this process for soil treatment in the Fukushima area by testing at their plants. The results were very promising, and a full-fledged application is expected to follow. In the present study, we spiked several aqueous samples containing soil collected from an industrial wet sieving plant located near our university for the recycling of construction wastes with non-radioactive cesium hydroxide. The present study provides scientific data concerning the effectiveness in volume reduction of the contaminated soil by a wet sieving process as well as the cesium distribution between the liquid phase and clay minerals for each sub-process of the full-scale one, but a simulating plant equipped with a process of coagulating sedimentation and operational safety fundamentals for the plant. Especially for the latter aspect, the study showed that clay minerals of submicron size strongly bind a high content of cesium, which was only slightly removed by coagulation with natural sedimentation (1 G) nor centrifugal sedimentation (3,700 G) and some of the cesium may be transferred to the effluent or recycled water. By applying ultracentrifugation (257,000 G), most of submicron clay minerals containing cesium was removed, and the cesium amount which might be transferred to the effluent or recycled water, could be reduced to less than 2.3 % of the original design by the addition of a cesium barrier consisting of ultracentrifugation or a hollow fiber membrane. (authors)

  16. Radioisotope thermoelectric generator/thin fragment impact test

    Science.gov (United States)

    Reimus, M. A. H.; Hinckley, J. E.

    1998-01-01

    The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of 238Pu decay to an array of thermoelectric elements in a radioisotope thermoelectric generator (RTG). Because the potential for a launch abort or return from orbit exists for any space mission, the heat source response to credible accident scenarios is being evaluated. This test was designed to provide information on the response of a loaded RTG to impact by a fragment similar to the type of fragment produced by breakup of the spacecraft propulsion module system (PMS). The results of this test indicated that impact of the RTG by a thin aluminum fragment traveling at 306 m/s may result in significant damage to the converter housing, failure of one fueled clad, and release of a small quantity of fuel.

  17. End-on radioisotope thermoelectric generator impact tests

    Science.gov (United States)

    Reimus, M. A. H.; Hinckley, J. E.

    1997-01-01

    The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of 238Pu decay to an array of thermoelectric elements in a radioisotope thermoelectric generator (RTG). The modular GPHS design was developed to address both survivability during launch abort and return from orbit. The first two RTG Impact Tests were designed to provide information on the response of a fully loaded RTG to end-on impact against a concrete target. The results of these tests indicated that at impact velocities up to 57 m/s the converter shell and internal components protect the GPHS capsules from excessive deformation. At higher velocities, some of the internal components of the RTG interact with the GPHS capsules to cause excessive localized deformation and failure.

  18. AMTEC radioisotope power system for the Pluto Express mission

    International Nuclear Information System (INIS)

    The Alkali Metal Thermal to Electric Converter (AMTEC) technology has made substantial advances in the last 3 years through design improvements and technical innovations. In 1993 programs began to produce an AMTEC cell specifically for the NASA Pluto Express Mission. A set of efficiency goals was established for this series of cells to be developed. According to this plan, cell number-sign 8 would be 17% efficient but was actually 18% efficient. Achieving this goal, as well as design advances that allow the cell to be compact, has resulted in pushing the cell from an unexciting 2 W/kg and 2% efficiency to very attractive 40 W/kg and 18% measured efficiency. This paper will describe the design and predict the performance of a radioisotope powered AMTEC system for the Pluto Express mission

  19. Multimodality Therapy: Bone-Targeted Radioisotope Therapy of Prostate Cancer

    Science.gov (United States)

    Tu, Shi-Ming; Lin, Sue-Hwa; Podoloff, Donald A.; Logothetis, Christopher J.

    2016-01-01

    Accumulating data suggest that bone-seeking radiopharmaceuticals can be used to treat prostate cancer bone metastasis and improve the clinical outcome of patients with advanced prostate cancer. It remains to be elucidated whether radiopharmaceuticals enhance the disruption of the onco-niche or the eradication of micrometastatic cells in the bone marrow. The purpose of this review is to investigate the role of bone-targeted radioisotope therapy in the setting of multimodality therapy for advanced prostate cancer. We examine available data and evaluate whether dose escalation, newer generations, or repeated dosing of radiopharmaceuticals enhance their antitumor effects and whether their combination with hormone ablative therapy, chemotherapy, or novel targeted therapy can improve clinical efficacy. PMID:20551894

  20. A new adrenal computer imaging technique using dual-radioisotopes.

    Directory of Open Access Journals (Sweden)

    Ohashi,Teruhisa

    1981-06-01

    Full Text Available Computer processed adrenal imaging using dual-radioisotopes, 6 beta-iodomethyl-19-nor-cholest-5(10-en-3 beta-ol-131I and 99mTc-phytate was performed in 12 patients with primary aldosteronism and 4 with Cushing's syndrome due to adrenocortical tumor. Adreno-photoscanning and hepato-photoscanning were performed in the same position 2-4 days following intravenous administration of radiocholesterol. The scintigraphic information was stored on cassettes and scan subtraction and a digital-computer method for data smoothing were performed on an oscilloscope. The tumor site could be determined in all cases until day 4 by this computer processed image.

  1. Contribution of radioisotopes in the diagnosis of lung tumours

    International Nuclear Information System (INIS)

    197Hg, a radioisotope of half life 65 h, injected as acetate builds up in malignant tumours and evolutive inflammatory lesions. In spite of a high proportion of false positives it can lead to a lung cancer diagnosis under well-defined circumstances such as: round lung images, X-ray tuberculosis images persisting after prolonged therapy, treated cancers where it can detect relapses before X-rays and in the difficult case of benign tumours. In man the uptake kinetics of carrier-free 67Cu (half-life 58 h), injected as citrate, are apparently not the same in cancers as in evolutive inflammatory lesions. The false positive yield, through much lower than that observed with 197Hg, is still too high in this preliminary study

  2. Fabrication of light weight radioisotope heater unit hardware components

    Science.gov (United States)

    McNeil, Dennis C.

    1996-03-01

    The Light Weight Radioisotope Heater Unit (LWRHU) is planned to be used on the National Aeronautics and Space Administration (NASA) Cassini Mission, to provide localized thermal energy as strategic locations on the spacecraft. These one watt heater units will support the operation of many on-board instruments that require a specific temperature range to function properly. The system incorporates a fuel pellet encapsulated in a vented metallic clad fabricated from platinum-30% rhodium (Pt-30%Rh) tubing, sheet and foil materials. To complete the package, the clad assemblies are placed inside a combination of graphite components. This report describes the techniques employed by Mound related to the fabrication and sub assembly processes of the LWRHU clad hardware components. Included are details concerning configuration control systems, material procurement and certification, hardware fabrication specifics, and special processes that are utilized.

  3. Development of stable isotope separation technology for radioisotope production

    International Nuclear Information System (INIS)

    The ultimate goal of this project is to construct the domestic production system of stable isotopes O-18 and Tl-203 used as target materials in accelerator for the production of medical radioisotopes F-18 and Tl-201, respectively. In order to achieve this goal, diode laser spectroscopic analytical system was constructed and automatic measurement computer software for the direct analysis of H216O/H218O ratio were developed. Distillation process, laser process, and membrane diffusion process were analyzed for the evaluation of O-18 production. And electromagnetic process, plasma process, and laser process were analyzed for the evaluation of Tl-203 production. UV laser system, IR laser system, and detailed system Tl-203 production were designed. Finally, current and future worldwide demand/supply of stable isotopes O-18 and Tl-203 were estimated

  4. Applications of radiations, radioisotopes and nuclear techniques in biotechnology

    International Nuclear Information System (INIS)

    Applications of radiations, radioisotopes and other nuclear techniques has contributed a great deal in our understanding of microbial plant and animal biochemistry and molecular biology. Electron microscopy has provided visual evidence for molecular events. Developments in cell tissue culture of both plants and animals and immunology have contributed to advances in what we now refer as biotechnology. This paper focuses on the applications in the high-tech end of biotechnology, limited to the use of recombinant-DNA techniques. Molecular identification of the genes, their cloning and horizontal transfer across the species of microbes, plants and animals and expression of the transferred genes is the major strength of modern biotechnology. The techniques described in this paper have played a significant role in the development of biotechnology. 6 refs

  5. Research on medical applications of radioisotopes and radiation in Australia

    International Nuclear Information System (INIS)

    The Australian Atomic Energy Commission (AAEC) produces and distributes commercially in Australia and abroad a range of radioisotopes and radiopharmaceuticals for medical applications. The AAEC carries out research and development on new and improved processes and procucts is collaboration with medical specialists in hospitals and research workers in other organisations. Examples of these processes and products are: a gel generator for production of 99mTc; radiopharmaceuticals for diagnosis of tumours and brain disease and therapy for arthritis; 64Cu for study of copper metabolism; and monoclonal antibodies for tumour diagnosis and therapy. New medical applications in Australia of neutron irradiation include the measurement of total body nitrogen and neutron capture in boron-labelled compounds in vivo for melanoma therapy. (author)

  6. Radioisotopic studies on pulmonary function in experimental burn shock

    International Nuclear Information System (INIS)

    Disturbances in pulmonary ventilation and perfusion, which can initiate severe complications, often lead to many therapeutic failures in burn shock. Early recognition of respiratory disturbances is often required to improve results of treatment of burn shock. The authors investigated changes in pulmonary ventilation and perfusion in napalm-burnt rabbits using 133Xe. Simultaneously, they determined effect of treatment with cytochrome C on pulmonary ventilation and perfusion in animals burnt with napalm. It was found that in napalm-burnt rabbits burn shock was accompanied by a significant deterioration in pulmonary ventilation and perfusion. The most marked changes were observed one and two days after burn. It was also found a beneficial effect of treatment with cytochrome C on alveolar ventilation. The authors pointed out the usefulness of radioisotopic investigations of pulmonary ventilation and perfusion in burn shock. (author)

  7. Studies of radioisotope production with an AVF cyclotron in TIARA

    Energy Technology Data Exchange (ETDEWEB)

    Sekine, Toshiaki [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    1997-03-01

    The production of radioisotopes to be used mainly for nuclear medicine and biology is studied with an AVF cyclotron in TIARA. A production method of no-carrier-added {sup 186}Re with the {sup 186}W(p,n){sup 186}Re reaction has been developed; this product may be used as a therapeutic agent in radioimmunotherapy due to the adequate nuclear and chemical properties. For the study of the function of plants using a positron-emitter two-dimensional imaging system, a simple method of producing the positron emitter {sup 18}F in water was developed by taking advantage of a highly-energetic {alpha} beam from the AVF cyclotron. (author)

  8. End-on radioisotope thermoelectric generator impact tests

    Energy Technology Data Exchange (ETDEWEB)

    Reimus, M.A.H.; Hhinckley, J.E.

    1997-01-01

    The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of [sup 238]Pu decay to an array of thermoelectric elements in a radioisotope thermoelectric generator (RTG). The modular GPHS design was developed to address both survivability during launch abort and return from orbit. The first two RTG Impact Tests were designed to provide information on the response of a fully loaded RTG to end-on impact against a concrete target. The results of these tests indicated that at impact velocities up to 57 m/s the converter shell and internal components protect the GPHS capsules from excessive deformation. At higher velocities, some of the internal components of the RTG interact with the GPHS capsules to cause excessive localized deformation and failure.

  9. Hydrogen and Cesium Monitor for H- Magnetron Sources

    Energy Technology Data Exchange (ETDEWEB)

    Tan, Cheng-Yang [Fermilab; Bollinger, Dan [Fermilab; Schupbach, Brian [Fermilab; Seiya, Kiyomi [Fermilab

    2014-07-01

    The relative concentration of cesium to hydrogen in the plasma of a H- magnetron source is an important parameter for reliable operations. If there is too much cesium, the surfaces of the source become contaminated with it and sparking occurs. If there is too little cesium then the plasma cannot be sustained. In order to monitor these two elements, a spectrometer has been built and installed on a test and operating source that looks at the plasma. It is hypothesized that the concentration of each element in the plasma is proportional to the intensity of their spectral lines.

  10. Effect of Rare Earth Elements on Exchange Performances of Cesium Ion-Sieve

    Institute of Scientific and Technical Information of China (English)

    张惠源; 王榕树; 林灿生; 张先业

    2003-01-01

    The exchange performances and the distribution coefficient of Cesium Ion-Sieve (Cs-IS) for cesium and for some rare earth elements were compared. In particular, the effects of neodymium on the cesium ion exchange and the Cs+ selectivity variation on Cs-IS owing to introduction of rare earth elements into HLLW were studied. Though rare earth elements exhibit a small influence on the distribution coefficient for Cs+, they impair Cs-exchange capacity of Cs-IS to some extent. This interruption on the selectivity to Cs+ can be significantly eliminated provided an appropriate ratio of liquid to solid V:m is used.

  11. High voltage holding in the negative ion sources with cesium deposition

    Energy Technology Data Exchange (ETDEWEB)

    Belchenko, Yu.; Abdrashitov, G.; Ivanov, A.; Sanin, A.; Sotnikov, O., E-mail: O.Z.Sotnikov@inp.nsk.su [Budker Institute of Nuclear Physics, Siberian Branch of Russian Academy of Sciences, Novosibirsk (Russian Federation)

    2016-02-15

    High voltage holding of the large surface-plasma negative ion source with cesium deposition was studied. It was found that heating of ion-optical system electrodes to temperature >100 °C facilitates the source conditioning by high voltage pulses in vacuum and by beam shots. The procedure of electrode conditioning and the data on high-voltage holding in the negative ion source with small cesium seed are described. The mechanism of high voltage holding improvement by depletion of cesium coverage is discussed.

  12. Specific interaction of cesium with the surface of calcium silicate hydrates

    International Nuclear Information System (INIS)

    The sorption of cesium at the calcium silicate hydrates (CSH) surface was investigated, both through sorption isotherm data and by solid-state NMR experiments. The sorption ability of CSH towards cesium is favored for low solid Ca/Si molar ratios, in agreement with the negative surface charge they develop then. A significant proportion of these sorbed cesium cations remains tightly bound to the surface sites forming, in dehydrated CSH, inner-sphere complexes, which can not be removed by alcohol washing. Chloride seems to present a lower affinity for CSH, even for high Ca/Si molar ratios, where the surface charge becomes positive. (orig.)

  13. First-principles study of cesium adsorption to weathered micaceous clay minerals

    Science.gov (United States)

    Okumura, Masahiko; Nakamura, Hiroki; Machida, Masahiko

    2014-05-01

    A large amount of radioactive nuclides was produced into environment due to the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. Residents near FDNPP were suffering from radioactive cesium and then evacuated, because which has long half-life and is retained by surface soil for long time. The Japanese government has been decontaminating the cesium by removing the surface soil in order to return them to their home. This decontamination method is very effective, but which produces huge amount of waste soil. This becomes another big problem in Fukushima, because it is not easy to find large storage sites. Then effective and economical methods to reduce the volume of the waste soil are needed. However, it has not been invented yet. One of the reasons is lack of knowledge about microscopic process of adsorption/desorption of cesium to/from soil. It is known that weathered micaceous clay minerals play crucial role on adsorption and retention of cesium. They are expected to have special sorption sites, called frayed edge sites (FESs), which adsorb cesium selectively and irreversibly. Properties of FES have been intensely investigated by experiments. But microscopic details of the adsorption process on FES are still unclear. Because direct observation of the process with current experimental techniques is quite difficult. We investigated the adsorption of cesium to FES in muscovite, which is a typical micaceous clay mineral, via first-principles calculations (density functional theory). We made a minimal model of FES and evaluate the energy difference before and after cesium adsorption to FES. This is the first numerical modeling of FES. It was shown that FES does adsorb cesium if the weathering of muscovite has been weathered. In addition, we revealed the mechanism of cesium adsorption to FES, which is competition between ion radius of cesium and the degree of weathering. I plan to discuss volume reduction of the waste soil based on our result. Reference M. Okumura

  14. Test procedures and instructions for single shell tank saltcake cesium removal with crystalline silicotitanate

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, J.B.

    1997-01-07

    This document provides specific test procedures and instructions to implement the test plan for the preparation and conduct of a cesium removal test, using Hanford Single Shell Tank Saltcake from tanks 24 t -BY- I 10, 24 1 -U- 108, 24 1 -U- 109, 24 1 -A- I 0 1, and 24 t - S-102, in a bench-scale column. The cesium sorbent to be tested is crystalline siticotitanate. The test plan for which this provides instructions is WHC-SD-RE-TP-024, Hanford Single Shell Tank Saltcake Cesium Removal Test Plan.

  15. A New Pumping-Probing Scheme for the Optically Pumped Cesium Beam Frequency Standard

    Institute of Scientific and Technical Information of China (English)

    陈景标; 朱程锦; 王凤芝; 杨东海

    2001-01-01

    A new pumping-probing scheme for the optically pumped cesium beam frequency standard has been experimentally tested in our laboratory. The stability of the optically pumped cesium beam frequency standard was measured by comparing its 10 MHz output with an HP5071A commercial cesium atomic clock. The result shows that the frequency stability for the 1 s and 30000s sample times are 1.2 × 10-11 and 3.7 × 10-13, respectively. It was proved that the new pumping scheme works well.

  16. Investigation of adsorption and wetting of 3He on cesium and cesiated glass

    International Nuclear Information System (INIS)

    Experiments have been carried out to investigate the binding of 3He on cesium substrates, using optical pumping to spin-polarize the atoms. The behavior of 3He on the walls at low temperature can be analyzed through the evolution of the nuclear magnetization of the sample. Preliminary results are presented, including: (1) adsorption studies of gaseous 3He on cesiated glass; (2) magnetic relaxation time of polarized liquid 3He on cesium and cesiated glass; (3) evidence for wetting of liquid 3He on cesium. 8 refs., 2 figs

  17. Dynamic radioisotopic study of the salivary glands. Quantification test

    International Nuclear Information System (INIS)

    Quantified dynamic radioisotopic exploration, a new and rational examination, should find its place in a thorough check-up of the salivary glands together with clinical, immunological, anatomopathological and sialographic investigations. The object of this work was to standardise the test procedure with a view to routine use on patients and to define certain quantified parameters representing objectively the different aspects of the salivary functions. Our procedure through reeding sophisticated equipment, is simple to perform and relies on use of: radiotechnetium employed at activities which allow repetitive exlorations whereby pathological changes may be followed; the gamma camera and its data processing system which records all radioactive information obtained on the patient's head. These results will supply the data needed to judge the salivary functions as a whole. The apparatus used provides a remarkable pictorial record made up not only of morphological and functional images at each stage of the examination but also of ciphered radioactivity versus time curves for each of the main salivary glands and for any other zone of interest. From these curves it is then possible to define quantified parameters, reproducible and expressing functional activity. This procedure, safe and painless, seems to suit the patients who lie still without complaint for 60 minutes, 45 minutes for the concentration study and 15 minutes for the post-stimulus excretion study. The dynamic radioisotopic examination of the salivary glands, by the comparison of concentration and excretion images and by the study of parameters, separately and as a whole, is thus a useful complement to other paraclinical examinations and contributes essential information in most salivary diseases

  18. Pathway of radioisotopes from land surface to sewage sludge

    Science.gov (United States)

    Fischer, Helmut W.; Yokoo, Yoshiyuki

    2014-05-01

    Radioactive surface contaminations will only partially remain at the original location - a fraction of the inventory will take part in (mainly terrestrial and aquatic) environmental transport processes. The probably best known and most important process comprises the food chain. Besides, the translocation of dissolved and particle-bound radioisotopes with surface waters plays an important role. These processes can have the effect of displacing large radioisotope amounts over considerable distances and of creating new sinks and hot spots, as it is already known for sewage sludge. We are reporting on a combined modeling and experimental project concerning the transport of I-131 and Cs-134/Cs-137 FDNPP 2011 depositions in the Fukushima Prefecture. Well-documented experimental data sets are available for surface deposition and sewage sludge concentrations. The goal is to model the pathway in between, involving surface runoff, transport in the sewer system and processes in the sewage treatment plant. Watershed runoff and sewer transport will be treated with models developed recently by us in other projects. For sewage treatment processes a new model is currently being constructed. For comparison and further validation, historical data from Chernobyl depositions and tracer data from natural and artificial, e.g. medical, isotopes will be used. First results for 2011 data from Fukushima Prefecture will be presented. The benefits of the study are expected to be two-fold: on one hand, the abundant recent and historical data will help to develop and improve environmental transport models; on the other hand, both data and models will help in identifying the most critical points in the envisaged transport pathways in terms of radiation protection and waste management.

  19. A high power, Coated Particle Fuel Compact Radioisotope Heat Unit

    Science.gov (United States)

    King, Jeffrey C.; El-Genk, Mohamed S.

    2001-02-01

    A Coated Particle Fuel Compact, Radioisotope Heater Unit (CPFC-RHU) is proposed, which is capable of generating thermal power in excess of 27 W. This power output is more than four times that of a Hexa-RHU, which generates only six watts of thermal power. The design of the CPFC-RHU is identical to that of the Hexa-RHU, except that the six Pt-30Rh clad fuel pellets and the POCO graphite support in the latter are replaced with single-sized, ZrC coated, 238PuO2 fuel particles ~500 μm in diameter. In addition to fully retaining the helium gas generated by the radioactive decay of the fuel, the CPFC offers promise for enhanced safety. Thermal analyses of the CPFC-RHU show that while the Hexa-RHU is suitable for use in a radioisotope power system (RPS) operating at a converter hot-side temperature of 473 K, the CPFC-RHU could also be used at higher temperatures of 773 K and 973 K with a thermal efficiency >60%. Even at a 473 K converter hot-side temperature, the CPFC-RHU offers higher thermal efficiency (>90%) than the Hexa-RHU (~75%). The CPFC-RHU final design provides constant temperature, with almost uniform radial heat flux to the converter, for enhanced performance, better integration, and higher overall efficiency of the RPS. The present CPFC-RHU fills a gap in the power needs for future space missions requiring electric power of 1-15 W, from a single RPS. .

  20. Preliminary studies of Brazilian wood using different radioisotopic sources

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Gilberto; Silva, Leonardo Gondim de Andrade e, E-mail: gcarval@ipen.br, E-mail: ftgasilva@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    Due to availability and particular features, wood was one of the first materials used by mankind with a wide variety of applications. It can be used as raw material for paper and cellulose manufacturing; in industries such as chemical, naval, furniture, sports goods, toys, and musical instrument; in building construction and in the distribution of electric energy. Wood has been widely researched; therefore, wood researchers know that several aspects such as temperature, latitude, longitude, altitude, sunlight, soil, and rainfall index interfere with the growth of trees. This behavior explains why average physical-chemical properties are important when wood is studied. The majority of researchers consider density to be the most important wood property because of its straight relationship with the physical and mechanical properties of wood. There are three types of wood density: basic, apparent and green. The apparent density was used here at 12% of moisture content. In this study, four different types of wood were used: 'freijo', 'jequetiba', 'muiracatiara' and 'ipe'. For wood density determination by non-conventional method, Am-241, Ba-133 and Cs-137 radioisotopic sources; a NaI scintillation detector and a counter were used. The results demonstrated this technique to be quick and accurate. By considering the nuclear parameters obtained as half value layers and linear absorption coefficients, Cs-137 radioisotopic source demonstrated to be the best option to be used for inspection of the physical integrity of electric wooden poles and live trees for future works. (author)

  1. Determination of the radiological impact of radioisotope waste disposal

    International Nuclear Information System (INIS)

    The AECB commissioned this study to determine the doses to individuals working in municipal waste management systems and to populations of cities where small amounts of radioisotopes are disposed of through the municipal waste management systems. To carry out this study, it was necessary to select a city having: (1) a population size representative of many cities in Canada, (2) many different types of radioisotope users, (3) all the possible municipal waste management systems, (4) a well established data base on its waste management systems. Using this criteria, the Hamilton-Burlington area surrounding Hamilton Harbour was selected. The pathways and dosimetry models were put into a computer spread sheet, to give the model flexibility so that it could be easily modified to model other cities. The model was developed using conservative assumptions and conservative estimates for some parameter values so that the doses calculated by the model are over estimates. Within the occupational critical group, the maximum doses were calculated for the Hamilton sewage treatment plant sludge worker at 1.4E-6 Sv/a. If this individual were also a member of the critical group in the general population the maximum dose would be 2.2E-6 Sv/a. Individual doses to the critical group within the general population were calculated as 7.7E-7 Sv/a for adults and 6.8E-8 Sv/a for infants. These compare to AECB regulatory limits of 5.0E-2 Sv/a per person for atomic radiation workers and 5.0E-3 Sv/a per person for the general public. The collective population dose for the study area was 1.37E-1 person-Sv/a for the 525,000 population

  2. INTRACORPOREAL HEAT DISSIPATION FROM A RADIOISOTOPE-POWERED ARTIFICIAL HEART.

    Science.gov (United States)

    Huffman, Fred N.; Hagen, Kenneth G.; Whalen, Robert L.; Fuqua, John M.; Norman, John C.

    1974-01-01

    The feasibility of radioisotope-fueled circulatory support systems depends on the ability of the body to dissipate the reject heat from the power source driving the blood pump as well as to tolerate chronic intracorporeal radiation. Our studies have focused on the use of the circulating blood as a heat sink. Initial in vivo heat transfer studies utilized straight tube heat exchangers (electrically and radioisotope energized) to replace a segment of the descending aorta. More recent studies have used a left ventricular assist pump as a blood-cooled heat exchanger. This approach minimizes trauma, does not increase the area of prosthetic interface with the blood, and minimizes system volume. Heat rejected from the thermal engine (vapor or gas cycle) is transported from the nuclear power source in the abdomen to the pump in the thoracic cavity via hydraulic lines. Adjacent tissue is protected from the fuel capsule temperature (900 to 1200 degrees F) by vacuum foil insulation and polyurethane foam. The in vivo thermal management problems have been studied using a simulated thermal system (STS) which approximates the heat rejection and thermal transport mechanisms of the nuclear circulatory support systems under development by NHLI. Electric heaters simulate the reject heat from the thermal engines. These studies have been essential in establishing the location, suspension, surgical procedures, and postoperative care for implanting prototype nuclear heart assist systems in calves. The pump has a thermal impedance of 0.12 degrees C/watt. Analysis of the STS data in terms of an electrical analog model implies a heat transfer coefficient of 4.7 x 10(-3) watt/cm(2) degrees C in the abdomen compared to a value of 14.9 x 10(-3) watt/cm(2) degrees C from the heat exchanger plenum into the diaphragm.

  3. a Biokinetic Model for CESIUM-137 in the Fetus

    Science.gov (United States)

    Jones, Karen Lynn

    1995-01-01

    Previously, there was no method to determine the dose to the embryo, fetus, fetal organs or placenta from radionuclides within the embryo, fetus, or placenta. In the past, the dose to the fetus was assumed to be equivalent to the dose to the uterus. Watson estimated specific absorbed fractions from various maternal organs to the uterine contents which included the fetus, placenta, and amniotic fluid and Sikov estimated the absorbed dose to the embryo/fetus after assuming 1 uCi of radioactivity was made available to the maternal blood.^{1,2} However, this method did not allow for the calculation of a dose to individual fetal organs or the placenta. The radiation dose to the embryo or fetus from Cs-137 in the fetus and placenta due to a chronic ingestion by the mother was determined. The fraction of Cs-137 in the maternal plasma crossing the placenta to the fetal plasma was estimated. The absorbed dose from Cs-137 in each modelled fetal organ was estimated. Since there has been more research regarding potassium in the human body, and particularly in the pregnant woman, a biokinetic model for potassium was developed first and used as a basis and confirmation of the cesium model. Available pertinent information in physiology, embryology, biokinetics, and radiation dosimetry was utilized. Due to the rapid growth of the fetus and placenta, the pregnancy was divided into four gestational periods. The numerous physiological changes that occurred during pregnancy were considered and an appropriate biokinetic model was developed for each of the gestational periods. The amount of cesium in the placenta, embryo, and fetus was estimated for each period. The dose to the fetus from cesium deposited in the embryo or fetus and in the placenta was determined for each period using Medical Internal Radiation Dosimetry (MIRD) methodology. An uncertainty analysis was also performed to account for the variability of the parameters in the biokinetic model based on the experimental data

  4. Diffusion of water, cesium and neptunium in pores of rocks

    International Nuclear Information System (INIS)

    Teollisuuden Voima Oy (TVO) is investigating the feasibility to dispose of spent nuclear fuel within Finland. The present plan calls for the repository to be located in crystalline rock at a depth of several hundred meters. The safety assessment of the repository includes calculations of migration of waste nuclides. The flow of waste elements in groundwater will be retarded through sorption interaction with minerals and through diffusion into rock. Diffusion is the only mechanism retarding the migration of non-sorbing species and, it is expected to be the dominating retardation mechanism of many of the sorbing elements. In the investigation the simultaneous diffusion of tritiated water (HTO), cesium and neptunium in rocks of TVO investigation sites at Kivetty, Olkiluoto and Romuvaara were studied. (11 refs., 33 figs., 9 tabs.)

  5. Cesium-137 accident lessons in Goiania, Goias State, Brazil

    International Nuclear Information System (INIS)

    This document relates the experience obtained by several professionals which had an important role in the cesium-137 accident occurred in Goiania, Goias State, Brazil in September, 1987. It's divided into chapters, according to the action area - medical, nursing, social assistance, odontological and psychological. At first, some notions of radioprotection are explained, followed by the accident history and by the doctors and nurses action during the emergency phase and the medical, odontological, social and psychological assistance to the victims. The social assistance report shows some statistical data about the economic, occupational and social conditions of the accident victims. It is shown some information about the health institutions and the sanitary care in the ionizing radiation and about the occupational radiological protection in Goiania

  6. Coherence Properties of Nanofiber-Trapped Cesium Atoms

    Science.gov (United States)

    Reitz, D.; Sayrin, C.; Mitsch, R.; Schneeweiss, P.; Rauschenbeutel, A.

    2013-06-01

    We experimentally study the ground state coherence properties of cesium atoms in a nanofiber-based two-color dipole trap, localized ˜200nm away from the fiber surface. Using microwave radiation to coherently drive the clock transition, we record Ramsey fringes as well as spin echo signals and infer a reversible dephasing time of T2*=0.6ms and an irreversible dephasing time of T2'=3.7ms. By modeling the signals, we find that, for our experimental parameters, T2* and T2' are limited by the finite initial temperature of the atomic ensemble and the heating rate, respectively. Our results represent a fundamental step towards establishing nanofiber-based traps for cold atoms as a building block in an optical fiber quantum network.

  7. Norbadione A: synthetic approach and cesium complexation studies

    International Nuclear Information System (INIS)

    This work was dedicated to the study of the synthesis and complexation studies of norbadione A: a pigment originating from a mushroom. A synthetic approach, based on a double Suzuki-Miyaura coupling, was developed. This strategy was applied with high yields to the synthesis of various norbadione A analogues, as well as to the synthesis of simple pulvinic acids. Access to functionalized precursors of the molecule was also studied and the final coupling remains to be done. Besides, a speciation study based on electro-spray ionization mass spectrometry was conducted with norbadione A and one of the analogues. This study allowed the assessment of the cesium complexation abilities of each molecule. Structural data was also obtained and complexation constants were calculated. Finally, norbadione A and various synthetic products have been tested via high-throughput screening methods and strong antioxidant properties were observed. Other biological results are also reported. (author)

  8. Vector Cesium Magnetometer for the nEDM Experiment

    International Nuclear Information System (INIS)

    Full text: We use optical pumping combined with magnetic resonance in a Cesium vapor cell in order to measure the magnetic field. A Vector Cs Magnetometer uses multiple laser beams to follow the dynamics of the spin in 3D. The 3D signal is used to extract the Larmor frequency of the spins, and to extract the direction of the magnetic field through the path of the spins. The magnetometer was successfully tested in a proof of principle experiment. Its measured performance is ∼50 pT/Hz1/2 for the directions perpendicular to the magnetic field, and ∼500 fT/Hz1/2 for the direction parallel to the magnetic field. (author)

  9. Coherence properties of nanofiber-trapped cesium atoms

    CERN Document Server

    Reitz, D; Mitsch, R; Schneeweiss, P; Rauschenbeutel, A

    2013-01-01

    We experimentally study the ground state coherence properties of cesium atoms in a nanofiber-based two-color dipole trap, localized 200 nm away from the fiber surface. Using microwave radiation to coherently drive the clock transition, we record Ramsey fringes as well as spin echo signals and infer a reversible dephasing time $T_2^\\ast=0.6$ ms and an irreversible dephasing time $T_2^\\prime=3.7$ ms. By theoretically modelling the signals, we find that, for our experimental parameters, $T_2^\\ast$ and $T_2^\\prime$ are limited by the finite initial temperature of the atomic ensemble and the heating rate, respectively. Our results represent a fundamental step towards establishing nanofiber-based traps for cold atoms as a building block in an optical fiber quantum network.

  10. Quantitative analysis of cesium in synthetic lithium molten salts

    International Nuclear Information System (INIS)

    An analytical technique for fission products in lithium molten salts of spent PWR (Pressurized Water Reactor) fuels has been studied for the establishment of optimum chemical engineering process and the evaluation of process material balance in developing Direct Oxide Reduction Process with lithium metal. As part of the basic research, synthetic dissolver solutions of lithium chloride containing trace amounts of fission product elements (La, Ce, Pr, Nd, Sm, Eu, Gd, Y, Cs, Ru, Rh, Pd, Mo, Zr, Cd, Ba, Sr, Te and Se) was prepared and used in establishing the selective separation technique of cesium from lithium chloride matrix using cation exchange chromatography. Its recovery was measured by flame atomic absorption spectrometry and the reliability of this technique was evaluate

  11. Elastic scattering of sodium and cesium atoms at ultracold temperatures

    Institute of Scientific and Technical Information of China (English)

    Zhang Ji-Cai; Wang Ke-Dong; Liu Yu-Fang; Sun Jin-Feng

    2011-01-01

    The elastic scattering properties in a mixture of sodium and cesium atoms are investigated at cold and ultracold temperatures. Based on the accurate interatomic potential for the NaCs mixture,the interspecies s-wave scattering lengths,the effective ranges and the p-wave scattering lengths are calculated by the quantal method and the semiclassical method,respectively. The s-wave scattering lengths are 512.7ao for the singlet state and 33.4ao for the triplet state. In addition,the spin-change and elastic cross sections are also calculated,and the g-wave shape resonance is found in the total elastic cross sections.

  12. Characterization of front-end electronics for CZT based handheld radioisotope identifier

    Energy Technology Data Exchange (ETDEWEB)

    Lombigit, L., E-mail: lojius@nm.gov.my [Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia); Rahman, Nur Aira Abd; Mohamad, Glam Hadzir Patai; Ibrahim, Maslina Mohd; Yussup, Nolida; Yazid, Khairiah; Jaafar, Zainudin

    2016-01-22

    A radioisotope identifier device based on large volume Co-planar grid CZT detector is current under development at Malaysian Nuclear Agency. This device is planned to be used for in-situ identification of radioisotopes based on their unique energies. This work reports on electronics testing performed on the front-end electronics (FEE) analog section comprising charge sensitive preamplifier-pulse shaping amplifier chain. This test involves measurement of charge sensitivity, pulse parameters and electronics noise. This report also present some preliminary results on the spectral measurement obtained from gamma emitting radioisotopes.

  13. An in-cell alpha detection system for radioisotope component assembly operations

    International Nuclear Information System (INIS)

    A remotely operated alpha detection system is being developed for use at the Radioisotope Power Systems Facility at the US Department of Energy's Hanford Site. It will be used in hot cells being constructed to assemble components of Radioisotope Thermoelectric Generators for space power applications. The in-cell detection equipment will survey radiological swipe samples to determine smearable surface contamination levels on radioisotope fuel, fueled components, and hot-cell work areas. This system is potentially adaptable to other hot cell and glovebox applications where radiation dose rates and contamination levels are expected to be low. 2 figs

  14. Present status and future trends of industrial radioisotopes application in Sudan

    International Nuclear Information System (INIS)

    Radioisotopes continue to play an important role in better management of natural resources, industrial growth and environmental preservation. The success of radioisotope applications is due primarily to the ability, conferred by the unique properties of radioactive materials, to collect data, where conventional methods fail or become uneconomical. These are prompt, on-line, in-situ and do not disturb the main industrial process in any way. In Sudan, the application of these nuclear techniques has considerable economic and environmental impact. This paper casts light on the present application of radioisotopes and future trends in the country.(Author)

  15. Vitrification of cesium-contaminated organic ion exchange resin

    Energy Technology Data Exchange (ETDEWEB)

    Sargent, T.N. Jr. [Clemson Univ., SC (United States)

    1994-08-01

    Vitrification has been declared by the Environmental Protection Agency (USEPA) as the Best Demonstrated Available Technology (BDAT) for the permanent disposal of high-level radioactive waste. Savannah River Site currently uses a sodium tetraphenylborate (NaTPB) precipitation process to remove Cs-137 from a wastewater solution created from the processing of nuclear fuel. This process has several disadvantages such as the formation of a benzene waste stream. It has been proposed to replace the precipitation process with an ion exchange process using a new resorcinol-formaldehyde resin developed by Savannah River Technical Center (SRTC). Preliminary tests, however, showed that problems such as crust formation and a reduced final glass wasteform exist when the resin is placed in the melter environment. The newly developed stirred melter could be capable of overcoming these problems. This research explored the operational feasibility of using the stirred tank melter to vitrify an organic ion exchange resin. Preliminary tests included crucible studies to determine the reducing potential of the resin and the extent of oxygen consuming reactions and oxygen transfer tests to approximate the extent of oxygen transfer into the molten glass using an impeller and a combination of the impeller and an external oxygen transfer system. These preliminary studies were used as a basis for the final test which was using the stirred tank melter to vitrify nonradioactive cesium loaded organic ion exchange resin. Results from this test included a cesium mass balance, a characterization of the semi-volatile organic compounds present in the off gas as products of incomplete combustion (PIC), a qualitative analysis of other volatile metals, and observations relating to the effect the resin had on the final redox state of the glass.

  16. Candlestick oven with a silica wick provides an intense collimated cesium atomic beam

    Science.gov (United States)

    Pailloux, A.; Alpettaz, T.; Lizon, E.

    2007-02-01

    This article shows that readily available glass and silica fibers and braids are suitable capillary structure for recirculating ovens, such as candlestick ovens, becoming then an alternative wick material to conventional metal based capillary structures. In order to study wettability and capillarity of metallic liquid cesium on borosilicate and silica microstructures, samples were selected, prepared, and tested experimentally. The contact angle of cesium on silica glass was roughly measured: θ =35°±10°. A commercially available silica braid was then introduced inside a candlestick oven to transfer the metallic liquid cesium from the cold reservoir to the hot emission point of the candlestick. A collimated cesium atomic beam of intensity of 2×1016at./ssr was obtained, stable and reproducible. Furthermore, this modified oven is easy to handle daily.

  17. Preparation, structure and application of a new ecomaterials cesium ion-sieve

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    A new ecomaterials cesium ion-sieve (Cs-IS), which has high selectivity to cesium and excellent acid resistance, is prepared with zirconyl molybdopyrophosphate as its matrix by specific chemical sieve-making means. Cs-IS has large exchange capacity ( 1.83mmol@g-1) and high distribution coefficient (4.09 x 104 mL@ L-1) in the medium of 3 mol@ L- 1 HNO3. In the static exchange with strongly acidic high-level radioactive liquid waste (HLLW) (3 mol@ L-1 HNO3), Cs-IS exhibits high exchange rate for cesium (above 96.53 % ) and large separation factor (greater than 958.41). These indicate the possible use of Cs-IS in cesium-137 selective removal and recovery from highly saline acidic HLLW system.

  18. Prussian blue caged in spongiform adsorbents using diatomite and carbon nanotubes for elimination of cesium.

    Science.gov (United States)

    Hu, Baiyang; Fugetsu, Bunshi; Yu, Hongwen; Abe, Yoshiteru

    2012-05-30

    We developed a spongiform adsorbent that contains Prussian blue, which showed a high capacity for eliminating cesium. An in situ synthesizing approach was used to synthesize Prussian blue inside diatomite cavities. Highly dispersed carbon nanotubes (CNTs) were used to form CNT networks that coated the diatomite to seal in the Prussian blue particles. These ternary (CNT/diatomite/Prussian-blue) composites were mixed with polyurethane (PU) prepolymers to produce a quaternary (PU/CNT/diatomite/Prussian-blue), spongiform adsorbent with an in situ foaming procedure. Prussian blue was permanently immobilized in the cell walls of the spongiform matrix and preferentially adsorbed cesium with a theoretical capacity of 167 mg/g cesium. Cesium was absorbed primarily by an ion-exchange mechanism, and the absorption was accomplished by self-uptake of radioactive water by the quaternary spongiform adsorbent. PMID:22464752

  19. Synthesis of novel calix[4]crown telomers and selective extraction of cesium ions

    Institute of Scientific and Technical Information of China (English)

    Hai Bing Li; Yuan Yin Chen; De Jun Xiong; Jun Yan Zhan; Cui Ping Han

    2007-01-01

    p-tert-Butylcalix[4]diazacrown-4 telomer, which contains hard and soft ion binding sites, was synthesized. It exhibited high selectivity toward cesium ions. The binding sites may complex alkali metal ions selectively.

  20. Total deposition of cesium-137 measured in Finland during the exercise `RESUME 95` in August 1995

    Energy Technology Data Exchange (ETDEWEB)

    Geer, L.E. De; Vintersved, I.; Arntsing, R. [National Defence Research Establisment, Nuclear Detection Group, Stockholm (Sweden)

    1997-12-31

    In the exercise called `RESUME 95` the Nuclear Detection Group from the National Defence Research Establishment in Stockholm participated with field gamma ray measurements combined with soil sampling and profile measurements. The results are presented in this report for the measurements of cesium-137. We considered the measurements of cesium-137 at the airfield the most important part of the in-situ exercise. Data was of course collected also for cesium-134 and natural radionuclides but time has not permitted a full analysis of these radionuclides. The methodology would, however, be the same as applied for cesium-137. Less attention was paid for area II and due to limited personnel resources the search exercise was not fully carried out. (au).

  1. Assessment of food calcium radioprotection effectiveness against cesium-137, added alone and with iodine-131

    International Nuclear Information System (INIS)

    New fish product with addition of food calcium had radioprotective properties, resulted in decreased cesium-137 content in organs and tissues of animals by 40-60% and lesser changes in differential blood count and biochemical indexes of blood serum

  2. Cold cesium molecules produced directly in a magneto-optical trap

    Institute of Scientific and Technical Information of China (English)

    Zhang Hong-Shan; Ji Zhong-Hua; Yuan Jin-Peng; Zhao Yan-Ting; Ma Jie; Wang Li-Rong; Xiao Lian-Tuan; Jia Suo-Tang

    2011-01-01

    We report on the observation of ultracold ground electric-state cesium molecules produced directly in a magnetooptical trap with a good signal-to-noise ratio.These molecules arise from the photoassociation of magneto-optical trap lasers and they are detected by resonantly enhanced multiphoton ionization technology.The production rate of ultracold cesium molecules is up to 4× 104 s-1.We measure the characteristic time of the ground electric-state cesium molecules generated in the experiment and investigate the Cs2+ molecular ion intensity as a function of the trapping laser intensity and the ionization pulse laser energy.We conclude that the production of cold cesium molecules may be enhanced by using appropriate experimental parameters,which is useful for future experiments involving the production and trapping of ultracold ground electric-state molecules.

  3. Cs2 ‘diffuse bands’ emission from superheated cesium vapor

    Science.gov (United States)

    Pichler, G.; Makdisi, Y.; Kokaj, J.; Thomas, N.; Mathew, J.; Beuc, R.

    2016-07-01

    Thermal emission from superheated cesium vapor was studied to very high temperatures from 700 °C to 1000 °C. This was performed in the vapor condition only and with no liquid cesium present in the all-sapphire cell. We observed a number of atomic and molecular spectral features simultaneously in emission and absorption, especially peculiar thermal emission of cesium dimer diffuse bands (2 3Πg → a 3∑u + transitions) around 710 nm coexisting with absorption bands around first resonance lines at 852 and 894 nm. We performed appropriate calculations of the diffuse band emission profiles and compared them with measured profiles. We also performed absorption measurements and compared observed diffuse band profiles with calculated ones. Possible applications of the observed phenomena will be discussed in terms of the solar energy conversion using dense cesium vapor.

  4. Fission of Multiply Charged Cesium and Potassium Clusters in Helium Droplets - Approaching the Rayleigh Limit

    CERN Document Server

    Renzler, Michael; Daxner, Matthias; Kranabetter, Lorenz; Kuhn, Martin; Scheier, Paul; Echt, Olof

    2016-01-01

    Electron ionization of helium droplets doped with cesium or potassium results in doubly and, for cesium, triply charged cluster ions. The smallest observable doubly charged clusters are $Cs_{9}^{2+}$ and $K_{11}^{2+}$; they are a factor two smaller than reported previously. The size of potassium dications approaches the Rayleigh limit nRay for which the fission barrier is calculated to vanish, i.e. their fissilities are close to 1. Cesium dications are even smaller than nRay, implying that their fissilities have been significantly overestimated. Triply charged cesium clusters as small as $Cs_{19}^{3+}$ are observed; they are a factor 2.6 smaller than previously reported. Mechanisms that may be responsible for enhanced formation of clusters with high fissilities are discussed.

  5. Fabrication and performance of fl y ash granule filter for trapping gaseous cesium

    Directory of Open Access Journals (Sweden)

    Park Jang Jin

    2015-09-01

    Full Text Available Although a disk-type fly ash filter has shown a good performance in trapping gaseous cesium, it has difficulty in charging filters into a filter container and discharging waste filters containing radioactive cesium from a container by remote action. To solve the difficulty of the disk-type fly ash filter, five types of granule filters, including a ball type, tube type, and sponge-structure type have been made. Among them, the best filter type was chosen through simple crucible tests. The five types of granule filters packed into containers were loaded into five alumina crucibles of 50 cc. Five grams of CsNO3 was used as a gaseous cesium source. They were then placed in a muffle furnace and heated to 900°C and maintained for 2 hours. After the experiment, the weights of the cesium trapped filters were measured. Among the five types of granule filters, the sponge-structure type granule filter was the best, which has the highest trapping capacity of cesium. Its capacity is 0.42 g-Cs/g-filter. The chosen sponge-structure type granule filters and disk-type filters have been tested using a two-zone tube furnace. Cs volatilization and Cs trapping zones were maintained at 900 and 1000°C, respectively. Sixteen grams of CsNO3 was used as a gaseous cesium source. The cesium trapping profile of the sponge-structure type granule filters was almost similar to that of the disk-type fly ash filters. For both cases, cesium was successfully trapped within the third filter.

  6. Enhanced electronic injection in organic light-emitting diodes by incorporating silver nanoclusters and cesium carbonate

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Ying-Chung; Gao, Chia-Yuan [Department of Electrical Engineering, National Sun Yat-Sen University, Kaohsiung, Taiwan (China); Chen, Kan-Lin [Department of Electronic Engineering, Fortune Institute of Technology, Kaohsiung, Taiwan (China); Sze, Po-Wen [Department of Electro-Optical Science and Engineering, Kao Yuan University, Kaohsiung, Taiwan (China); Huang, Chien-Jung, E-mail: chien@nuk.edu.tw [Department of Applied Physics, National University of Kaohsiung, Kaohsiung, Taiwan (China)

    2015-10-01

    Highlights: • The localized electric field around SNCs is enhanced. • When the cesium carbonate/silver nanoclusters/cesium carbonate electron-injection structure replaces the cesium carbonate electron-injection structure, higher electron-injection ability is obtained. • The structure for efficient electron injection is critical to characteristics of the device. - Abstract: The influence of the cesium carbonate/silver nanoclusters/cesium carbonate electron-injection structure (CSC-EIS) on the performance of organic light-emitting diodes is investigated in this study. The silver nanoclusters (SNCs) are introduced between the electron-injection layers by means of thermal evaporation. When the CSC-EIS replaces the cesium carbonate electron-injection structure, higher electron-injection ability is obtained because the electron-injection barrier between the cathode and the electron-transport layer is remarkably reduced from 1.2 to 0 eV. In addition, surface plasmon resonance effect will cause the enhanced localized electric field around the SNCs, resulting that electron-injection ability is further enhanced from the cathode to the emitting layer.

  7. Measurement of cesium emissions during the vitrification of simulated high level radioactive waste

    International Nuclear Information System (INIS)

    In the Defense Waste Processing Facility at the Savannah River Site, it is desired to eliminate a startup test that would involve adding small amounts of radioactive cesium-137 to simulated high-level waste. In order to eliminate this test, a reliable method for measuring non-radioactive cesium in the offgas system from the glass melter is required. From a pilot scale melter system, offgas particulate samples were taken on filter paper media and analyzed by Inductively Coupled Plasma-Mass Spectrometry (ICP-MS). The ICPMS method proved to be sufficiently sensitive to measure cesium quantities as low as 0.135 μg, with the sensitivity being limited by the background cesium present in the filter paper. Typical particulate loadings ranged from 800 μg of cesium. This sensitivity allowed determination of cesium decontamination factors for four of the five major components of the offgas system. The decontamination factors measured experimentally compared favorably with the process design basis values

  8. Modeling Ion-Exchange Processing With Spherical Resins For Cesium Removal

    Energy Technology Data Exchange (ETDEWEB)

    Hang, T.; Nash, C. A.; Aleman, S. E.

    2012-09-19

    The spherical Resorcinol-Formaldehyde and hypothetical spherical SuperLig(r) 644 ion-exchange resins are evaluated for cesium removal from radioactive waste solutions. Modeling results show that spherical SuperLig(r) 644 reduces column cycling by 50% for high-potassium solutions. Spherical Resorcinol Formaldehyde performs equally well for the lowest-potassium wastes. Less cycling reduces nitric acid usage during resin elution and sodium addition during resin regeneration, therefore, significantly decreasing life-cycle operational costs. A model assessment of the mechanism behind ''cesium bleed'' is also conducted. When a resin bed is eluted, a relatively small amount of cesium remains within resin particles. Cesium can bleed into otherwise decontaminated product in the next loading cycle. The bleed mechanism is shown to be fully isotherm-controlled vs. mass transfer controlled. Knowledge of residual post-elution cesium level and resin isotherm can be utilized to predict rate of cesium bleed in a mostly non-loaded column. Overall, this work demonstrates the versatility of the ion-exchange modeling to study the effects of resin characteristics on processing cycles, rates, and cold chemical consumption. This evaluation justifies further development of a spherical form of the SL644 resin.

  9. Prussian blue caged in spongiform adsorbents using diatomite and carbon nanotubes for elimination of cesium

    International Nuclear Information System (INIS)

    Highlights: ► Prussian blue was sealed in cavities of diatomite using carbon nanotubes. ► The caged Prussian blue after being permanently immobilized in polyurethane spongy showed a 167 mg/g capability for absorbing cesium. ► Cesium elimination was accomplished by simply adding the Prussian-blue based spongiform adsorbent to radioactive water. - Abstract: We developed a spongiform adsorbent that contains Prussian blue, which showed a high capacity for eliminating cesium. An in situ synthesizing approach was used to synthesize Prussian blue inside diatomite cavities. Highly dispersed carbon nanotubes (CNTs) were used to form CNT networks that coated the diatomite to seal in the Prussian blue particles. These ternary (CNT/diatomite/Prussian-blue) composites were mixed with polyurethane (PU) prepolymers to produce a quaternary (PU/CNT/diatomite/Prussian-blue), spongiform adsorbent with an in situ foaming procedure. Prussian blue was permanently immobilized in the cell walls of the spongiform matrix and preferentially adsorbed cesium with a theoretical capacity of 167 mg/g cesium. Cesium was absorbed primarily by an ion-exchange mechanism, and the absorption was accomplished by self-uptake of radioactive water by the quaternary spongiform adsorbent.

  10. Prussian blue caged in spongiform adsorbents using diatomite and carbon nanotubes for elimination of cesium

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Baiyang [Graduate School of Environmental Science, Hokkaido University, Sapporo 060-0810 (Japan); Fugetsu, Bunshi, E-mail: hu@ees.hokudai.ac.jp [Graduate School of Environmental Science, Hokkaido University, Sapporo 060-0810 (Japan); Yu, Hongwen [Graduate School of Environmental Science, Hokkaido University, Sapporo 060-0810 (Japan); Abe, Yoshiteru [Kyoei Engineering Corporation, Niigata 959-1961 (Japan)

    2012-05-30

    Highlights: Black-Right-Pointing-Pointer Prussian blue was sealed in cavities of diatomite using carbon nanotubes. Black-Right-Pointing-Pointer The caged Prussian blue after being permanently immobilized in polyurethane spongy showed a 167 mg/g capability for absorbing cesium. Black-Right-Pointing-Pointer Cesium elimination was accomplished by simply adding the Prussian-blue based spongiform adsorbent to radioactive water. - Abstract: We developed a spongiform adsorbent that contains Prussian blue, which showed a high capacity for eliminating cesium. An in situ synthesizing approach was used to synthesize Prussian blue inside diatomite cavities. Highly dispersed carbon nanotubes (CNTs) were used to form CNT networks that coated the diatomite to seal in the Prussian blue particles. These ternary (CNT/diatomite/Prussian-blue) composites were mixed with polyurethane (PU) prepolymers to produce a quaternary (PU/CNT/diatomite/Prussian-blue), spongiform adsorbent with an in situ foaming procedure. Prussian blue was permanently immobilized in the cell walls of the spongiform matrix and preferentially adsorbed cesium with a theoretical capacity of 167 mg/g cesium. Cesium was absorbed primarily by an ion-exchange mechanism, and the absorption was accomplished by self-uptake of radioactive water by the quaternary spongiform adsorbent.

  11. Radioisotope techniques for problem solving in the offshore oil and gas industry

    International Nuclear Information System (INIS)

    Radioisotope technology has been used for almost half a century by the oil and gas industry to solve problems and to help optimize process operations. The use of radioactive isotopes to investigate the effectiveness of well stimulation procedures and to measure the sweep-out patterns of oil and gas in secondary recovery process is well known. The applications of radioisotopes to study features of plant and process operation has been less widely reported though the economic benefits deriving from such applications are very great. Nevertheless, there has been continuous development in the range of application and in the design of equipment to facilitate the use of the technology at remote environments such as an oil or gas platform. Some indication of the current usage of radioisotope techniques may be obtained from examination of Table I, which lists projects carried out in the UK's North Sea fields by ICI Tracerco, which is the world's largest radioisotope applications service group

  12. Radioisotope electric propulsion (REP): A near-term approach to nuclear propulsion

    Science.gov (United States)

    Schmidt, George R.; Manzella, David H.; Kamhawi, Hani; Kremic, Tibor; Oleson, Steven R.; Dankanich, John W.; Dudzinski, Leonard A.

    2010-02-01

    Studies over the last decade have shown radioisotope-based nuclear electric propulsion to be enhancing and, in some cases, enabling for many potential robotic science missions. Also known as radioisotope electric propulsion (REP), the technology offers the performance advantages of traditional reactor-powered electric propulsion (i.e., high specific impulse propulsion at large distances from the Sun), but with much smaller, affordable spacecraft. Future use of REP requires development of radioisotope power sources with system specific powers well above that of current systems. The US Department of Energy and NASA have developed an advanced Stirling radioisotope generator (ASRG) engineering unit, which was subjected to rigorous flight qualification-level tests in 2008, and began extended lifetime testing later that year. This advancement, along with recent work on small ion thrusters and life extension technology for Hall thrusters, could enable missions using REP sometime during the next decade.

  13. Long Life 600W Hall Thruster System for Radioisotope Electric Propulsion Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Radioisotope Electric Propulsion (REP) offers the prospect for a variety of new science missions by enabling use of Hall Effect propulsion in the outer solar...

  14. Radioisotope Electric Propulsion (REP): A Near-Term Approach to Nuclear Propulsion

    Science.gov (United States)

    Schmidt, George R.; Manzella, David H.; Kamhawi, Hani; Kremic, Tibor; Oleson, Steven R.; Dankanich, John W.; Dudzinski, Leonard A.

    2009-01-01

    Studies over the last decade have shown radioisotope-based nuclear electric propulsion to be enhancing and, in some cases, enabling for many potential robotic science missions. Also known as radioisotope electric propulsion (REP), the technology offers the performance advantages of traditional reactor-powered electric propulsion (i.e., high specific impulse propulsion at large distances from the Sun), but with much smaller, affordable spacecraft. Future use of REP requires development of radioisotope power sources with system specific powers well above that of current systems. The US Department of Energy and NASA have developed an advanced Stirling radioisotope generator (ASRG) engineering unit, which was subjected to rigorous flight qualification-level tests in 2008, and began extended lifetime testing later that year. This advancement, along with recent work on small ion thrusters and life extension technology for Hall thrusters, could enable missions using REP sometime during the next decade.

  15. Working environment measurement of the radioisotope facilities at Kumamoto University and examination of problems

    International Nuclear Information System (INIS)

    The results of regular working environment measurements in our radioisotope facilities were about background levels. However, most of these are the data measured when unsealed radioisotopes were not used. High concentrations of radioisotopes were detected when measured during the time when unsealed 35S or 125I was used. These results were estimated far under the regulation levels. Thus, safety working environments are sufficiently guaranteed by suitable estimation and suitable handling under the strict regulation. Therefore, regulation would be relaxed in the field of education and research in such ways as estimation by calculation in place of the actual measurements, decrease of the number of monthly measurements, and measurements exemption for nonvolatile or low levels of isotopes. Working environment measurements would be still effective in cases where volatile radioisotopes are used in large quantities. They may provide a useful index if improvement of safe handling technique or equipments is required. (author)

  16. Industrial Applications of radioisotopes and radiation technology and Agency's role

    International Nuclear Information System (INIS)

    Applications of radioisotopes and radiation technology are contributing significantly in many areas of science and technology, industry and environment, towards sustainable development, improving the quality of life and cleaner and safer national industries. There are three major classes impacting industrial scale operations, namely, (a) radiation processing/treatment, (b) radiotracer and sealed source techniques to monitor industrial processes/columns/vessels and (c) industrial gamma radiography and tomography. Radiation processing applying gamma sources and electron accelerators for material treatment/modification is an established technology. There are over 160 gamma industrial irradiators and 1300 industrial electron accelerators in operation worldwide. Development of new materials, especially for health care and environment protection, and advanced products (for electronics, solar energy systems, biotechnology etc) are the main objectives of R and D activity in radiation processing technology. The International Atomic Energy Agency (IAEA, Agency) is involved in supporting both the development and transfer of radiation technology. Thanks to Agency's efforts, advanced radiation processing centres have been established in many Member States (MS), e.g. Malaysia, Egypt, Iran, Poland, Brazil, Hungary. Hydrogel dressing for wounds, radiation vulcanised latex, degraded natural polymer are examples of useful product outcomes. Demonstration of effective treatment of flue gas in pilot plant as well as industrial scale and industrial wastewater in pilot plant scale has shown promise for tackling industrial emissions/effluents using electron beam machines. Industrial radiotracer and gamma sealed source techniques are largely used for analyzing industrial process systems. Initially used as trouble-shooting measures, they play a vital role in process parameter optimization, improved productivity, on-line monitoring and could lead to even pre-commissioning benchmarking. Gamma

  17. Cascaded Thermoelectric Converters for Advanced Radioisotope Power Systems

    Science.gov (United States)

    El-Genk, Mohamed S.; Saber, Hamed H.

    2004-02-01

    Three Cascaded Thermoelectric Converters (CTCs) are optimized for potential use in Multi-Mission Advanced Radioisotope Power Systems (MM-ARPS) for electrical powers up to 1 kWe, or even higher, in support of 7-10 year missions. The peak efficiencies of these CTCs of 9.43% to 14.32% are 40% to 110% higher than that of SiGe in State-of-the-Art (SOA) Radioisotope Thermoelectric Generators (RTGs). Such high efficiencies would significantly reduce the amount of 238PuO2 fuel and the total system mass for a lower mission cost. Each CTC is comprised of a SiGe top unicouple that is thermally, but not electrically, coupled to a bottom unicouple with one of the following three choices of thermoelectric materials: (a) p-leg of TAGS-85 and n-leg of 2N-PbTe (b) p-leg of CeFe3.5Co0.5Sb12 and n-leg of CoSb3; and (c) segmented p-leg of CeFe3.5Co0.5Sb12 and Zn4Sb3 and n-leg of CoSb3. The length of the top and bottom unicouples is 10 mm, but the cross-sectional areas of the n- and p-legs of the unicouples are optimized for maximum efficiency operation. They vary with the thermal power inputs of 1, 2, and 3 Wth per SiGe unicouple, and the heat rejection temperature of 375 K, 475 K, and 575 K, from the bottom unicouple. Such geometrical optimization is at nominal hot shoe temperature of 1273 K for the SiGe unicouple and cold shoe temperature of either 780 K or 980 K, depending on the materials of the bottom unicouples. The hot shoe temperature of the bottom unicouples is 20 K lower than the cold shoe of the top SiGe unicouple, but the rate of heat input is the same as the rate of heat rejection from the top unicouple. The present results are conservative as they assume a contact resistance of 150 μΩ-cm2 per leg for the top and the bottom unicouples in the CTCs; however, decreasing this resistance to 50 μΩ-cm2 per leg could increase the current efficiency estimates by an additional 1 - 2 percentage points.

  18. Organization of a radioisotope based molecular biology laboratory

    International Nuclear Information System (INIS)

    Polymerase chain reaction (PCR) has revolutionized the application of molecular techniques to medicine. Together with other molecular biology techniques it is being increasingly applied to human health for identifying prognostic markers and drug resistant profiles, developing diagnostic tests and genotyping systems and for treatment follow-up of certain diseases in developed countries. Developing Member States have expressed their need to also benefit from the dissemination of molecular advances. The use of radioisotopes, as a step in the detection process or for increased sensitivity and specificity is well established, making it ideally suitable for technology transfer. Many molecular based projects using isotopes for detecting and studying micro organisms, hereditary and neoplastic diseases are received for approval every year. In keeping with the IAEA's programme, several training activities and seminars have been organized to enhance the capabilities of developing Member States to employ in vitro nuclear medicine technologies for managing their important health problems and for undertaking related basic and clinical research. The background material for this publication was collected at training activities and from feedback received from participants at research and coordination meetings. In addition, a consultants' meeting was held in June 2004 to compile the first draft of this report. Previous IAEA TECDOCS, namely IAEA-TECDOC-748 and IAEA-TECDOC-1001, focused on molecular techniques and their application to medicine while the present publication provides information on organization of the laboratory, quality assurance and radio-safety. The technology has specific requirements of the way the laboratory is organized (e.g. for avoiding contamination and false positives in PCR) and of quality assurance in order to provide accurate information to decision makers. In addition while users of the technology accept the scientific rationale of using radio-isotopes

  19. RADIOISOTOPE IDENTIFICATION OF SHIELDED AND MASKED SNM RDD MATERIALS

    Energy Technology Data Exchange (ETDEWEB)

    Salaymeh, S.; Jeffcoat, R.

    2010-06-17

    Sonar and speech techniques have been investigated to improve functionality and enable handheld and other man-portable, mobile, and portal systems to positively detect and identify illicit nuclear materials, with minimal data and with minimal false positives and false negatives. RadSonar isotope detection and identification is an algorithm development project funded by NA-22 and employing the resources of Savannah River National Laboratory and three University Laboratories (JHU-APL, UT-ARL, and UW-APL). Algorithms have been developed that improve the probability of detection and decrease the number of false positives and negatives. Two algorithms have been developed and tested. The first algorithm uses support vector machine (SVM) classifiers to determine the most prevalent nuclide(s) in a spectrum. It then uses a constrained weighted least squares fit to estimate and remove the contribution of these nuclide(s) to the spectrum, iterating classification and fitting until there is nothing of significance left. If any Special Nuclear Materials (SNMs) were detected in this process, a second tier of more stringent classifiers are used to make the final SNM alert decision. The second algorithm is looking at identifying existing feature sets that would be relevant in the radioisotope identification context. The underlying philosophy here is to identify parallels between the physics and/or the structures present in the data for the two applications (speech analysis and gamma spectroscopy). The expectation is that similar approaches may work in both cases. The mel-frequency cepstral representation of spectra is widely used in speech, particularly for two reasons: approximation of the response of the human ear, and simplicity of channel effect separation (in this context, a 'channel' is a method of signal transport that affects the signal, examples being vocal tract shape, room echoes, and microphone response). Measured and simulated gamma-ray spectra from a hand

  20. Production of radioisotopes by 1.5 m cyclotron and their utilization

    International Nuclear Information System (INIS)

    Radioisotopes characterized by nuclear property and uses can be produced on the accelerator, especially those playing an important role in scientific researches and biomedical uses. The status of Radioisotopes produced by 1.5 m cyclotron and their applications in our institute are summarized in this paper. The details of preparation and the results of use for radioactive sources, radiochemicals, radiopharmaceuticals of 57Co, 109Cd, 68Ge- 68Ga, and 167Tm are given respectively. (author)

  1. The role of the chemist in the development and production of radioisotope preparations

    International Nuclear Information System (INIS)

    The Isotope Production Centre of the Atomic Energy Board manufactures and markets a large number of important radioisotopes for use in medical, industrial and research fields which, previously, had to be imported. The development and production of radioisotope products require a multi-disciplinary approach in which a team effort by chemists, physicists, engineers, biologists and physicians is applied. Radioisotopes are usually used in the form of sealed radiation sources, simple inorganic compounds or radioisotope-labelled molecules. Sealed radiation sources such as cobalt-60 and iridium-192 are applied widely in the industrial field in, for example, level-high and level- density measurements, radiation sterilisation of medical equipment, and gamma radiography of structures. For industrial tracer and research purposes sodium-24, argon-41, bromine-82, iodine-131 and gold-198 are regularly used in simple chemical form. There are some thousands of radioisotope-labelled compounds of which the largest group compromises compounds of tritium, carbon-14 and sulphur-35. Because the last-mentioned isotopes have long physical half-lives and poor detectability in in vivo systems, they are used in vitro mainly in biomedical research. Radioisotopes such as iodine-131, iodine-123, indium-111, technetium-99m, krypton-81m and gallium-67 are in great demand for in vivo medical examinations because of their suitably short half-lives and detectability by the gamma camera. Iodine-125, a radioisotope which is usually manufactured in a nuclear reactor, plays a very important role in radioimmuoassays(RIA). The latter technique is an unusually sensitive, spesific in vitro analytical method which enables scientists to determine nanogram to picogram amounts of chemical compounds in blood. The design, development and manufacture of radioisotope preparations for a variety of uses offer an interesting challenge to the chemist now as well as in the future

  2. Design of a Chemical Processing Apparatus for Radioisotopes of Short Half-Life

    International Nuclear Information System (INIS)

    It has appeared to us useful to make suggestions to radiochemists having at their disposal a small reactor (e. g., 1012 n/cm2s flux) regarding which radioisotopes they can prepare and the minimum equipment required. The paper comprises three main parts: 1. Possible radioisotopes, which may be divided into two categories: (a) radioisotopes for medical uses, including: Na24, K42, Br82, Cu64, As76, Hg197 and colloidal Au198; and (b) radioisotopes for scientific or industrial uses, including in addition to the above-named: Sb122, As77, Mn56 and Au198 (chloride). 2. Chemical processing, in which two categories of radioisotopes emerge: (a) the category involving simple solution, normally requiring either cold dissolution in water or dilute acid or hot dissolution in concentrated acids. This category includes: Na24, K42, Br12, Hg197, Sb122, Mn56 and Au198 (chloride). (b) The category involving complex separations or transformations, in which fall preparations by Szilard-Chalmers effect, reactions (n, p), (n, γ), followed by β-decay or formation of colloids. The following maybe mentioned: Cu54, As76, As77 and colloidal Au198 and 3. Preparation areas. It is essential that these radioisotopes be prepared in leak-tight and shielded areas and be grouped according to their affinities. We accordingly suggest an apparatus consisting of 3 cells 2 m in length by 1 m in depth, linked together by a conveyor and used, e.g., for the following processes: 1st cell: Introduction of containers, opening and preparation of Na24, K42, and Br82; 2nd cell: Preparation of two out of the following three radioisotopes : Cu64, As76 and colloidal Au198; and 3rd cell: Bringing into solution of radioisotopes for various uses and preparation of Hg197. (author)

  3. Feasibility study on polonium-209 as radioisotope fuel for space nuclear power

    International Nuclear Information System (INIS)

    We have investigated the performance and the production method of alternative isotopes of 238Pu as a radioisotope fuel for use in space radioisotope power generators. Polonium-209 has the possibility to be an alternative material of 238Pu. It has enough half-time of 102 years and the specific power of 490 W/kg. From the simulation, the beam current of 14 A with 40 MeV proton energy provides 1 kg/yr of 209Po annually. (author)

  4. Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

    OpenAIRE

    Gizem Bakır; Saltuk Buğra Selçuklu; Hüseyin Yapıcı

    2016-01-01

    This study presents the medical radioisotope production performance of a conceptual accelerator driven system (ADS). Lead-bismuth eutectic (LBE) is selected as target material. The subcritical fuel core is conceptually divided into ten equidistant subzones. The ceramic (natural U, Pu)O2 fuel mixture and the materials used for radioisotope production (copper, gold, cobalt, holmium, rhenium, thulium, mercury, palladium, thallium, molybdenum, and yttrium) are separately prepared as cylindrical r...

  5. The effects of K+ growth conditions on the accumulation of cesium by the bacterium Thermus sp. TibetanG6

    Institute of Scientific and Technical Information of China (English)

    WANG; Hailei; KONG; Fanjing; ZHENG; Mianping

    2006-01-01

    The accumulation of cesium by the bacterium Thermus sp. TibetanG6 was examined under different K+ growth conditions. The effects of external pH and Na+ on the accumulation of cesium were also studied, and the mechanism involved was discussed. K+ regimes played an important role in the accumulation of cesium by the strain TibetanG6. The quantity of cesium accumulated (24 h) was much higher in K+-deficient regime than that in K+-sufficient regime. The pH and Na+ had different effects on the accumulation of cesium in the two K+ regimes. IR spectra analyses indicated that the biosorption is a process of homeostasis with cesium initially accumulated on the cell wall.

  6. Monitoring of radionuclides in the environment. Part. 4. Factors influencing depth profiles of radioactive cesium in soils

    International Nuclear Information System (INIS)

    In order to evaluate the vertical migration behavior of radioactive cesium, which contaminated by the Fukushima Dai-ichi NPP accident, the distribution of radioactive cesium in different type of soils, e.g., bare ground, grass land, conifer forest floor were measured on October 2011, 2012, 2013, in Abiko, Chiba, Japan. Even three years after the deposition, most of radioactive cesium were deposited in the depths of within 5 cm at anywhere in this area. Depth profiles of radioactive cesium in soil was significantly correlated with organic matter content in soils (r=0.82; p<0.0001), whereas the factors such as potassium ion and ammonium ion in soil, stable cesium content, and clay mineral content were not correlated clearly. This indicates that the vertical migration rate of radioactive cesium is very slow and it would be influenced by organic matter in soil, not just clay. (author)

  7. Personal reflections on the highlights and changes in radiation and radioisotope measurement applications

    Science.gov (United States)

    Gardner, Robin P.; Lee, Kyoung O.

    2015-11-01

    This paper describes the recent changes that the authors have perceived in the use of radiation and radioisotope measurement applications. The first change is that due to the increased use of Monte Carlo simulation which has occurred from a normal evolutionary process. This is due in large part to the increased accuracy that is being obtained by the use of detector response functions (DRFs) and the simultaneous increased computational efficiency that has become available with these DRFs, the availability of a greatly improved weight windows variance reduction method, and the availability of inexpensive computer clusters. This first change is a happy one. The other change that is occurring is in response to recent terrorist activities. That change is the replacement or major change in the use of long-lived radioisotopes in radioisotope measurement and other radioisotope source applications. In general this can be done by improving the security of these radioisotope sources or by replacing them altogether by using machine sources of radiation. In either case one would like to preclude altogether or at least minimize the possibility of terrorists being able to obtain radioisotopes and use them for clandestine purposes.

  8. Use of radioisotopes in agriculture: DNA based molecular markers in crop improvement

    International Nuclear Information System (INIS)

    Agriculture has always benefited from the use of radioisotopes in many ways. In the beginning radioisotopes were mostly used for physiological studies to measure photosynthetic efficiency, nutrient uptake, and for mutation breeding. Radioisotopes have now become a part of the biotechnological tools that are being increasingly used in improving crops and production systems. The tools of biotechnology are being increasingly used to hasten breeding and address problems of biotic and abiotic stresses. Some of the non-radioactive methods have replaced radiotracer techniques and thus led to automation often at high cost. However, still there remain many applications where radioisotopes seem almost indispensable. For some of the applications like comparative genome mapping, the confirmation of transgenics, and establishment of gene copy number, use of RFLP with radioisotopes is essential. The following research areas at ICRISAT use radioisotopes: (1) physiological basis of adaptation to abiotic stresses (ii) development and use of appropriate DNA markers crop improvement; (iii) characterization of cytoplasmic male sterile systems and genetic diversity of breeding materials, land races and the wild relatives and (iv) molecular basis of disease resistance; (v) comparative genome mapping across cereals, (vi) isolation and characterization of genes of potential value to genetic improvement and (vii) verification of genetic transformation events. (author)

  9. Remedial measures against high levels of radioisotopes in aquatic ecosystems

    International Nuclear Information System (INIS)

    This Annex has been prepared within the framework of the Aquatic Working Group of the co-ordinated Research Programme on Validation of the Environmental Model Predictions (VAMP). The main objectives of this Annex are: (1) To provide an outline of a broad set of remedial measures and strategies tested and suggested for aquatic systems to speed up the recovery after the nuclear accident at Chernobyl in April 1986. This Report covers case studies from rivers and lakes and includes results from field and laboratory experiments, as well as measures directed at reducing radioisotopes in food by different food preparation procedures in the home. (2) To provide results from selected case studies, focusing on general, strategic results rather than site-specific details. (3) To provide conclusions which specifically address practical matters concerning how to select remedial measures in different situations, how to avoid inefficient measures, and to suggest important areas for future research. (4) To provide an analysis of the concept of lake sensitivity using both empirical and modelled data. One and the same fallout may give rise to very different radionuclide concentrations in water and biota depending on the characteristics of the lake and its catchment

  10. Monitoring of noble gas radioisotopes in nuclear power plant effluents

    International Nuclear Information System (INIS)

    Monitoring of gaseous radionuclides in the effluents of nuclear facilities is an essential requirement in effluent management programs. Since there is no practical way of removing noble gas radioisotopes from air at release pathways, their accurate monitoring is essential for providing appropriate environmental protection. Emitted γ dose-rate is the limiting factor for concentration-time integral of noble gas in gaseous effluents of reactor facilities. The external exposure to the public from a semi-infinite cloud is directly proportional to both the noble gas isotope concentration and the integrated γ energy per disintegration. Both can be directly measured in gaseous effluent pathways with a suitable detector. The capability of NaI(T1), CaF2(Eu) and plastic scintillation detectors to measure the γ-Ci.MeV content of noble gas releases was experimentally evaluated. The combination of CaF2(Eu) detector in a pressurized through-flow chamber, with a charge integrating scaler well complied with both γ energy response and detection sensitivity requirements. Noble gas source terms and effluent monitoring criteria are discussed, theoretical and experimental results are presented and a practical, on-line noble gas monitoring system is described

  11. Safe Handling of Radioisotopes. First Edition with Revised Appendix I

    International Nuclear Information System (INIS)

    Under its Statute the International Atomic Energy Agency is empowered to provide for the application of standards of safety for protection against radiation to its own operations and to operations making use of assistance provided by it or with which it is otherwise directly associated. To this end authorities receiving such assistance are required to observe relevant health and safety measures prescribed by the Agency. As a first step, it was considered an urgent task to provide users of radioisotopes with a manual of practice for the safe handling of these substances. The first edition of such a manual was published in 1958 and represented the first of the 'Safety Series', a series of manuals and codes on health and safety published by the Agency. It was prepared after careful consideration of existing national and international codes of radiation safety by a group of international experts and in consultation with other international bodies. This edition presents the first revision. It incorporates in the Appendices the latest recommendations of the International Commission on Radiological Protection and extracts from the report of the Committee II of the I.C.R.P. on permissible dose for internal radiation. The Health Physics and Medical Addenda to this Manual, published as No. 2 and No. 3 in the Safety Series in 1960, give more complete advice to the user on specialized topics.

  12. Assessment of dynamic energy conversion systems for radioisotope heat sources

    International Nuclear Information System (INIS)

    The use of dynamic conversion systems to convert the heat generated in a 7500 W(t) 90 Sr radioisotopic heat source to electricity is examined. The systems studies were Stirling; Brayton Cycle; three organic Rankines (ORCs) (Barber-Nichols/ORMAT, Sundstrand, and TRW); and an organic Rankine plus thermoelectrics. The systems were ranked for a North Warning System mission using a Los Alamos Multiattribute Decision Theory code. Three different heat source designs were used: case I with a beginning of life (BOL) source temperature of 640 C, case II with a BOL source temperature of 7450C, and case III with a BOL source temperature of 9450C. The Stirling engine system was the top-ranked system of cases I and II, closely followed by the ORC systems in case I and ORC plus thermoelectrics in case II. The Brayton cycle system was top-ranked for case III, with the Stirling engine system a close second. The use of 238Pu in heat source sizes of 7500 W(t) was examined and found to be questionable because of cost and material availability and because of additional requirements for analysis of safeguards and critical mass

  13. Radioisotopic splenoportography in pediatric patients with portal hypertension

    Energy Technology Data Exchange (ETDEWEB)

    Ohshima, Koji; Miyamoto, Kazutoshi; Yokoyama, Yasuhiro; Kubo, Yoshihiko; Samejima, Natsuki (Asahikawa Medical Coll., Hokkaido (Japan))

    1990-08-01

    Radioisotopic splenoportography (RI-splenoportography) was performed in 11 children (6 patients with biliary atresia, 3 with extrahepatic portal obstruction, 1 with congenital hepatic fibrosis and 1 with pediatric liver cirrhosis). Collateral pathways were found in 9 patients by RI-imaging, of whom 6 patients had ascending pathways alone, 1 had both ascending and descending pathways, and 2 had only descending pathways. Esophageal varices were found endoscopically in all 7 patients with ascending collateral pathways, but were not found in 2 patients with the descending collateral pathways alone or in 2 patients without collateral pathway images. Endoscopic injection sclerotherapy (EST) was performed in one patient with biliary atresia who had had episodes of rupture of esophageal varices. Ascending collateral pathways were recognized by RI-splenoportography before EST, but they disappeared completely after three sessions of EST. In two patients with extrahepatic portal obstruction and a patient with congenital hepatic fibrosis who underwent meso-caval shunt operations, shunt patency and disappearance of ascending collateral pathways were proved clearly by RI-splenoportography after the operations. RI-splenoportography is very useful for investigation of portal venous collateral circulation in portal hypertension or for confirming patency of portosystemic shunts. (author).

  14. An Advanced Turbo-Brayton Converter for Radioisotope Power Systems

    Science.gov (United States)

    Zagarola, Mark V.; Izenson, Michael G.; Breedlove, Jeffrey J.; O'Connor, George M.; Ketchum, Andrew C.; Jetley, Richard L.; Simons, James K.

    2005-02-01

    Past work has shown that Brayton power converters are an attractive option for high power, long-duration space missions. More recently, Creare has shown that Brayton technology could be scaled with high efficiency and specific power to lower power levels suitable for radioisotope power conversion systems. Creare is currently leading the development of an advanced turbo-Brayton converter under NASA's Prometheus Program. The converter design is based on space-proven cryocooler technologies that have been shown to be safe; to provide long, maintenance-free lifetimes; and to have high reliability, negligible vibration emittance, and low EMI/EMC. The predicted performance of a converter at the beginning of life is greater than 20% (including electronic inefficiencies and overhead) with a converter specific power of greater than 8 We/kg for a test unit and greater than 15 We/kg for a flight unit. The degradation in performance over a 14-year mission lifetime is predicted to be negligible, and the primary life limiting factor is not expected to be an issue for greater than twice the mission duration. Work during the last year focused on the material and fabrication issues associated with a high temperature turbine and a lightweight recuperator, and the performance issues associated with the high-temperature insulation and power conversion electronics. The development of the converter is on schedule. Thermal vacuum testing to demonstrate a technology readiness level of 5 is currently planned for 2006.

  15. Light-weight radioisotope heater unit (LWRHU) impact tests

    Science.gov (United States)

    Reimus, M. A. H.; Rinehart, G. H.; Herrera, A.; Lopez, B.; Lynch, C.; Moniz, P.

    1998-01-01

    The light-weight radioisotope heater unit (LWRHU) is a 238PuO2-fueled heat source designed to provide one thermal watt in each of various locations on a spacecraft. Los Alamos National Laboratory designed, fabricated, and safety tested the LWRHU. The heat source consists of a hot-pressed 238PuO2 fuel pellet, a Pt-30Rh vented capsule, a pyrolytic graphite insulator, and a fineweave-pierced fabric graphite aeroshell assembly. To compare the performance of the LWRHUs fabricated for the Cassini mission with the performance of those fabricated for the Galileo mission, and to determine a failure threshold, two types of impact tests were conducted. A post-reentry impact test was performed on one of 180 flight-quality units produced for the Cassini mission and a series of sequential impact tests using simulant-fueled LWRHU capsules were conducted respectively. The results showed that deformation and fuel containment of the impacted Cassini LWRHU was similar to that of a previously tested Galileo LWRHU. Both units sustained minimal deformation of the aeroshell and fueled capsule; the fuel was entirely contained by the platinum capsule. Sequential impacting, in both end-on and side-on orientations, resulted in increased damage with each subsequent impact. Sequential impacting of the LWRHU appears to result in slightly greater damage than a single impact at the final impact velocity of 50 m/s.

  16. The development of a milliwatt-level radioisotope power source

    Science.gov (United States)

    Bugby, David C.; McBirney, Thomas R.

    1998-01-01

    Future NASA spacecraft for unmanned planetary exploration will be much smaller and require much less power than the large systems used in prior missions. The ``Powerstick'', a miniaturized isotopic electrical power generator, uses a flight-qualified, DoE-manufactured, 1.1 W Radioisotope Heater Unit (RHU) to generate the high temperature sink for a thermoelectric converter (TEC). The TEC generates sufficient electrical power (~40 mW) to trickle-charge an external rechargeable battery pack, which can then be used in low duty cycle, low power applications. The original Powerstick concept (proposed by JPL) was refined at Swales Aerospace (SA), which has: repackaged it, constructed a prototype, and performed limited testing. The prototype Powerstick is 63.5 mm (2.500'') in diameter, 76.2 mm (3.000'') long, and weighs about 0.3 kg (0.66 lb). Structural analysis indicates the Powerstick can easily survive typical launch loads. Thermal analysis indicates that over 70% of the RHU energy enters the TEC. This paper will describe the design and analysis of the Powerstick prototype and present the key test results.

  17. MDS Nordion - a Canadian Radioisotope success story Science advancing health

    International Nuclear Information System (INIS)

    At MDS Nordion we use nuclear science and technology to advance human life and health through a wide range of applications. We could not do this without the strong partnerships we have formed with the Canadian nuclear power industry. Together, we have developed and applied radioisotope technology in ways that have saved millions of lives around the world. This is a success story of which we all can be proud. It is a success story that we should share with others. As an industry, we are often challenged by activists , who fear and attack anything nuclear and who do not care to understand how vital nuclear energy and nuclear science are to an environmentally sound, economically healthy future. MDS Nordion has not escaped this kind of public scrutiny, but much of this criticism is muted by the tremendous contributions we have made to medicine and health care generally. That is why it is so important for you to see MDS Nordion's story as a success story that everyone in the industry has contributed to, in the support they have provided, and in the products or services they supply

  18. Development of radioisotope tracer technology and nucleonic control system

    International Nuclear Information System (INIS)

    The purpose of this study is to develop the radioisotope tracer technology, which can be used in solving industrial and environmental problems and basic technology of nuclear control systems that are widely used for automation of industrial plants, and to build a strong tracer group to support the local industries. In relation to the tracer technology, the data acquisition system, the column scanning equipment and the detection pig for a leakage test have been developed. In order to use in analyzing data of tracer experiments, a computer program for the analysis of residence time distribution has been created as well. These results were utilized in developing the tracer technologies, such as the column scanning, the flow measurement using the dilution method, the simultaneous monitoring rotational movement of piston rings and the optimization of a waste water treatment facility, and the technologies were successfully demonstrated in the local industrial. The stripper of RFCC reactor has been examined to find an unwanted structure in it by imminent request from the industry. Related to the development of nucleonic control system, the state of art report on the technology has been written and an equipment for the analysis of asphalt content has been developed. (author)

  19. Development of radioisotope tracer technology and nucleonic control system

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Joon Ha; Lee, Myun Joo; Jung, Sung Hee and others

    1999-04-01

    The purpose of this study is to develop the radioisotope tracer technology, which can be used in solving industrial and environmental problems and basic technology of nuclear control systems that are widely used for automation of industrial plants, and to build a strong tracer group to support the local industries. In relation to the tracer technology, the data acquisition system, the column scanning equipment and the detection pig for a leakage test have been developed. In order to use in analyzing data of tracer experiments, a computer program for the analysis of residence time distribution has been created as well. These results were utilized in developing the tracer technologies, such as the column scanning, the flow measurement using the dilution method, the simultaneous monitoring rotational movement of piston rings and the optimization of a waste water treatment facility, and the technologies were successfully demonstrated in the local industrial. The stripper of RFCC reactor has been examined to find an unwanted structure in it by imminent request from the industry. Related to the development of nucleonic control system, the state of art report on the technology has been written and an equipment for the analysis of asphalt content has been developed. (author)

  20. Insurance of Radioisotopes and Ionizing Radiation Sources in France

    International Nuclear Information System (INIS)

    Since the early sixties, Assuratome has amassed quite a long experience in the insurance of radioisotopes and more generally of ionising radiation sources when they are used transported or stored outside a nuclear installation. Aware of the specific dangers of such devices, and having no experience in this domain French insurers were looking for a pragmatic solution which would permit to continue to provide cover for users or fabricants of small radioactive sources and in the meantime to keep a rigorous control on the claims and on the loss ratio which would be achieved over the years. Hence the decision was taken by the French Insurance market to entrust the French Nuclear Insurance Pool, Assuratome, as the recommended body for delivering specific 'nuclear policies' as an expert for this category of business. The next step was to make sure that the 'conventional policies' would not provide the same cover. Therefore, an appropriate exclusion clause was introduced in all the general conditions of the TPL Policies of the conventional market and consequently in the majority, if not all, the reinsurance treaties. Besides the obvious advantage resulting in the management of this category of business in a centralised body, a major benefit of this situation is based on the strict control by the insurer of the compulsory authorisation delivered by the authorities to the owner of the radioactive source. Unofficial sources having in principal no insurance possibilities in France their use would be virtually impossible.(author)

  1. Investigation of process equipment in petrochemical industry using radioisotope technology

    International Nuclear Information System (INIS)

    Applications of radioisotope technology have proved it self to be an effective techniques for troubleshooting and optimizing industrial process in petrochemical industry. In this study, Khartoum refinery was investigated by gamma scanning technique for better understanding of malfunctions, the scanning were carried out using 60C gamma radiation source with activity of 50 mCi on fractionator and stripper columns, obtained results showed that all trays of the fractionator column were in place but weeping was evident due to fouling or partial tray damage. For the stripper column, results obtained showed that all trays were on their positions and no process anomalies taking place. Heat exchanger was also examined using radiotracer technique with respect to leak detection and residence time distribution. The investigations were carried out using 82Br in the form of di-bromo-para-bensene (C6H4Br2) as a radiotracer. No leak was recorded and the residence time distribution results showed that the process functions were quite normal. Leak was examined using 99mTc as a radiotracer detection to demonstrate the potentials of the technique. The testing was conducted using reflux condenser. Obtained results proved that the technique is sensitive, reliable and can be adopted to investigate heat exchangers in industrial systems.(Author)

  2. Improvement of animal production through research using radioisotopes and radiation

    International Nuclear Information System (INIS)

    High birth rates coupled with greater longevity continue to increase the.world's population, especially in the less developed countries. The prevention of undernutrition and ultimately starvation will only be averted by increased food production and more efficient use of that food. At the same time people who have largely subsisted upon plant food diets and whose standards of living are rising, want to increase the use of animal products in order to upgrade their diets. To provide this high quality food animal scientists must find ways of increasing the supply especially in the less developed countries. Since most of the available pasture lands are presently being fully utilized or overgrazed, improved efficiency of the present herds and use of agroindustrial wastes are the only methods left to increase production significantly. The use of radioisotopes and radiation in research are making major contributions to the understanding of the processes necessary to achieve better animal production. In order to provide a forum for exchange of information in this field, the FAO/IAEA Joint Division of Atomic Energy in Food and Agriculture organized an international symposium, held in Vienna, from 2?6 February, on the use of nuclear techniques in animal production. Among the topics discussed at the symposium were: Soil-plant-animal relations regarding minerals, Trace elements in animal nutrition, Calcium, phosphorus and magnesium metabolism, Protein (nitrogen) metabolism - ruminants Protein (nitrogen) metabolism - non-ruminants Nuclear techniques in the control of parasitic infections Animal endocrinology with special emphasis on radioimmunoassays

  3. The Path to a Reliable Supply of Medical Radioisotopes

    International Nuclear Information System (INIS)

    Medical imaging techniques using technetium-99m account for roughly 80% of all nuclear medicine procedures, representing over 30 million examinations worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 (99Mo) and 6 hours for technetium-99m (99mTc), and thus must be produced continually - can lead to cancellations or delays in important medical testing services. Unfortunately, supply reliability has declined over the past decade, due to unexpected or extended shutdowns at the few ageing, 99Mo-producing, research reactors and processing facilities. These shutdowns have created global supply shortages. At the request of its member countries, the OECD Nuclear Energy Agency (NEA) established the High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) in 2009. During its two-year mandate, the HLG-MR assessed the factors rendering the supply chain vulnerable and identified practical measures - near, medium and long term - to ensure the security of supply of this important medical isotope. Building on its findings and assessments, the HLG-MR developed a comprehensive policy approach to encourage long-term supply security of 99Mo/'99mTc, detailing the essential steps to be taken by governments, industry and the health community to address the vulnerabilities within the supply chain, including changing an economic structure that does not support or reinforce reliable supply

  4. Radioisotope studies of mucociliary system function in otorhinolaryngology

    Energy Technology Data Exchange (ETDEWEB)

    De Rossi, G. [Istituto di Medicina Nucleare, Rome (Italy)

    1992-12-31

    An `excursus` on the Nuclear Medicine methods at present available for the study of mucociliary system function in otorhinolaryngology is reported. To this end, ostoscintigraphy and rhinosctinigraphy prove to be exquisitely sensitive techniques. Otoscintigraphy is useful for pre-operative studies in the patients who are planned to undergo tympanoplasty for dry tympanic perforations. Rhinoscintigraphy is regarded as the most affordable and sound method to evaluate mucociliary system function in rhinopathies. It is also suggested for the pre- and post-operative assessment of polypectomy. Hence, otorhinolaryngology radioisotope methods deserve to be extensively dealt with in Nuclear Medicine treatises. (orig.) [Deutsch] Der Autor gibt einen Ueberblick ueber nuklear-medizinische Verfahren, die heutzutage fuer funktionelle Untersuchungen des mukoziliaren Systems in der HNO-Heilkunde zur Verfuegung stehen. Die Otoszintigraphie sowie die Rhinoszintigraphie erweisen sich in diesem Zusammenhang als Methoden mit einer ueberaus hohen Empfindlichkeit. Bei Patienten, die wegen einer Trommelfellperforation zur Trommelfellplastik vorgesehen sind, bewaehrt sich die Otoszintigraphie fuer praeoperative Untersuchungen. Die Rhinoszintigraphie wird bei den unterschiedlichsten Nasenerkrankungen als die rationellste und wirksamste Methode zur funktionellen Beurteilung des mukoziliaren Systems angesehen. Darueber hinaus wird sie fuer die praeoperative und postoperative Untersuchung bei Polypenexstirpationen empfohlen. Deshalb sollte den Methoden der Radioisotopenuntersuchungen in der HNO-Heilkunde ein hoeherer Stellenwert eingeraeumt werden. (orig.)

  5. Determination of differential pulmonary function by the radioisotopic method

    International Nuclear Information System (INIS)

    A study of twenty-one patients with bronchogenic carcinoma which were submitted to lobectomy or pneumonectomy has been done, with the purpose of evaluation of regional and differential function of the lungs or parts of them. To accomplish this subject the patients underwent simple spirometry with FEV (forced expiratory volume in the first second) and FVC (forced vital capacity) measurements plus quantitative perfusional scintigraphy using 99 Tc-MAA (aggregated albumin). The relationship between these tests allowed the calculation of predictive values of FEV and FVC for the post-operative period through proposed equations. From the third month on after the operation, the patients were again submitted to spirometry with measurement of FEV and FVC to attest the hypothesis that these values were similar to those calculated. The statistical study of these results, utilizing the Student's t test, has demonstrated that the values of FEV and FVC were similar to those found in the postoperative period. These results allowed the conclusion that the radioisotopic method had predictive capacity of FEV and FVC in the lobectomized and pneumonectomized patients and it is a contribution in the evaluation of the differential pulmonary function. (author)

  6. Engineered Materials for Cesium and Strontium Storage Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Sean M. McDeavitt

    2010-04-14

    Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at

  7. Engineered Materials for Cesium and Strontium Storage. Final Technical Report

    International Nuclear Information System (INIS)

    Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at Purdue

  8. A small low energy cyclotron for radioisotope measurements

    International Nuclear Information System (INIS)

    Direct detection of 14C by accelerator mass spectrometry has proved to be a much more sensitive method for radiocarbon dating than the decay counting method invented earlier by Libby. A small cyclotron (the ''cyclotrino'') was proposed for direct detection of radiocarbon in 1980. This combined the suppression of background through the use of negative ions, which had been used effectively in tandem accelerators, with the high intrinsic mass resolution of a cyclotron. Development of a small electrostatically-focused cyclotron for use as a mass spectrometer was previously reported but the sensitivity needed for detection of 14C at natural abundance was not achieved. The major contributions of this work are the integration of a high current external ion source with a small flat-field, electrostatically-focused cyclotron to comprise a system capable of measuring 14C at natural levels, and the analysis of ion motion in such a cyclotron, including a detailed analysis of phase bunching and its effect on mass resolution. A high current cesium sputter negative ion source generates a beam of carbon ions which is pre-separated with a Wien filter and is transported to the cyclotron via a series of electrostatic lenses. Beam is injected radially into the cyclotron using electrostatic deflectors and an electrostatic mirror. Axial focusing is entirely electrostatic. A microchannel plate detector is used with a phase-grated output. In its present form the system is capable of improving the sensitivity of detecting 14C in some biomedical experiments by a factor of 104. Modifications are discussed which could bring about an additional factor of 100 in sensitivity, which is important for archaeological and geological applications. Possibilities for measurements of other isotopes, such as 3H, and 10Be, and 26Al, are discussed. 70 refs

  9. Preparation and characterization of cesium-137 aluminosilicate pellets for radioactive source applications

    International Nuclear Information System (INIS)

    Twenty-seven fully loaded 137Cs aluminosilicate pellets were fabricated in a hot cell by the vacuum hot pressing of a cesium carbonate/montmorillonite clay mixture at 15000C and 570 psig. Four pellets were selected for characterization studies which included calorimetric measurements, metallography, scanning electron microscope and electron backscattering (SEM-BSE), electron microprobe, x-ray diffraction, and cesium ion leachability measurements. Each test pellet contained 437 to 450 curies of 137Cs as determined by calorimetric measurements. Metallographic examinations revealed a two-phase system: a primary, granular, gray matrix phase containing large and small pores and small pore agglomerations, and a secondary fused phase interspersed throughout the gray matrix. SEM-BSE analyses showed that cesium and silicon were uniformly distributed throughout both phases of the pellet. This indicated that the cesium-silicon-clay reaction went to completion. Aluminum homogeneity was unconfirmed due to the high background noise associated with the inherent radioactivity of the test specimens. X-ray diffraction analyses of both radioactive and non-radioactive aluminosilicate pellets confirmed the crystal lattice structure to be pollucite. Cesium ion quasistatic leachability measurements determined the leach rates of fully loaded 137Cs sectioned pollucite pellets to date to be 4.61 to 34.4 x 10-10 kg m-2s-1, while static leach tests performed on unsectioned fully loaded pellets showed the leach rates of the cesium ion to date to be 2.25 to 3.41 x 10-12 kg m-2s-1. The cesium ion diffusion coefficients through the pollucite pellet were calculated using Fick's first and second laws of diffusion. The diffusion coefficients calculated for three tracer level 137Cs aluminosilicate pellets were 1.29 x 10-16m2s-1, 6.88 x 10-17m2s-1, and 1.35 x 10-17m2s-1, respectively

  10. Radioisotope Power System Delivery, Ground Support and Nuclear Safety Implementation: Use of the Multi-Mission Radioisotope Thermoelectric Generator for the NASA's Mars Science Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    S.G. Johnson; K.L. Lively; C.C. Dwight

    2014-07-01

    Radioisotope power systems have been used for over 50 years to enable missions in remote or hostile environments. They are a convenient means of supplying a few milliwatts up to a few hundred watts of useable, long-term electrical power. With regard to use of a radioisotope power system, the transportation, ground support and implementation of nuclear safety protocols in the field is a complex process that requires clear identification of needed technical and regulatory requirements. The appropriate care must be taken to provide high quality treatment of the item to be moved so it arrives in a condition to fulfill its missions in space. Similarly it must be transported and managed in a manner compliant with requirements for shipment and handling of special nuclear material. This presentation describes transportation, ground support operations and implementation of nuclear safety and security protocols for a radioisotope power system using recent experience involving the Multi-Mission Radioisotope Thermoelectric Generator for National Aeronautics and Space Administration’s Mars Science Laboratory, which launched in November of 2011.

  11. The crystal structures of potassium and cesium trivanadates

    Science.gov (United States)

    Evans, H.T.; Block, S.

    1966-01-01

    Potassium and cesium trivanadates are monoclinic and isomorphous, space group P21/m, with the following dimensions (Z = 2): KV3O8, a = 7.640 A, b = 8.380 A, c = 4.979 A, ??= 96?? 57???; CsV3O8, a = 8.176 A, b = 8.519 A, c = 4.988 A, ?? = 95?? 32???. The crystal structure of KV3O8 has been determined from hk0, 0kl, and h0l Weissenberg data with an R factor of 0.15. The structure of CsV3O8 has been refined with 1273 hkl Weissenberg data to an R factor of 0.089. The structures consist of corrugated sheets based on a linkage of distorted VO6, octahedra. Two of the vanadium atoms lie in double, square-pyramid groups V2O8, which are linked through opposite basal corners into chains along the b axis. The chains are joined laterally along the c axis into sheets by the third vanadium atom in VO groups, also forming part of a square-pyramid coordination. Various aspects of these structures are compared with other known oxovanadate structures.

  12. ATLAS tile calorimeter cesium calibration control and analysis software

    International Nuclear Information System (INIS)

    An online control system to calibrate and monitor ATLAS Barrel hadronic calorimeter (TileCal) with a movable radioactive source, driven by liquid flow, is described. To read out and control the system an online software has been developed, using ATLAS TDAQ components like DVS (Diagnostic and Verification System) to verify the hardware before running, IS (Information Server) for data and status exchange between networked computers, and other components like DDC (DCS to DAQ Connection), to connect to PVSS-based slow control systems of Tile Calorimeter, high voltage and low voltage. A system of scripting facilities, based on Python language, is used to handle all the calibration and monitoring processes from hardware perspective to final data storage, including various abnormal situations. A QT based graphical user interface to display the status of the calibration system during the cesium source scan is described. The software for analysis of the detector response, using online data, is discussed. Performance of the system and first experience from the ATLAS pit are presented

  13. Cesium sorption and desorption behavior of clay minerals

    International Nuclear Information System (INIS)

    Cesium sorption and desorption of clay minerals (montmorillonite, beidellite, nontronite, weathered biotite, rectorite and illite) were investigated by consecutive sorption-desorption (CSD) experiments. In batch sorption experiment, two solutions with different Cs concentration 10-3 and 10-7 mol/L) were used. In batch desorption experiments, Cs sorbed samples in sorption experiments were treated 5 times with 1 mol/L ammonium acetate solution. In the case of CSD experiments using 10-3 mol/L Cs solution, the exchangeable cations (Na, Ca, and K) in the clay samples affected to the sorption ratio of Cs, and this effect depended on the type of clay mineral. The desorption ratios of untreated, Na-exchanged and Ca-exchanged weathered biotite ranged from 23 to 33%, while that of other samples was over 80%. In the case of CSD experiments using 10-7 mol/L Cs solution, the sorption ratio of montmorillonite was smaller than that of the other clay samples. In desorption experiments, more than 10-9 mol sorbed Cs remained in 1.0 g of the sample after 5 extraction times. These results indicate that all examined clay samples are able to strongly adsorb Cs with a capacity of more than 10-9 mol/g. (author)

  14. Broadband Vibrational Cooling of Cold Cesium Molecules: Theory and Experiments

    Institute of Scientific and Technical Information of China (English)

    D. Sofikitis; A. Fioretti; S. Weber; M. Viteau; A. Chotia; R. Horchani; M. Allegrini; B. Chatel; D. Comparat; P. Pillet

    2009-01-01

    The use of a broadband, frequency shaped femtosecond laser on translationally cold cesium molecules has recently demonstrated to be a very efficient method of cooling also the vibrational degree of freedom. A sample of cold molecules, initially distributed over several vibrational levels, has thus been transfered into a single selected vibrational level of the singlet X1∑g ground electronic state. Our method is based on repeated optical pumping by laser light with a spectrum broad enough to excite all populated vibrational levels but limited in its frequency bandwidth with a spatial light modulator. In such a way we are able to eliminate transitions from the selected level, in which molecules accumulate. In this paper we briefly report the main experimental results and then address, in a detailed way by computer simulations, the perspectives for a "complete" cooling of the molecules, including also the rotational degree of freedom. Since the pumping process strongly depends on the rclative shape of the ground and excited potential curves, ro-vibrational cooling through different excited states is theoretically compared.

  15. Evaluation of a cesium adsorbent grafted with ammonium 12-molybdophosphate

    Science.gov (United States)

    Shibata, Takuya; Seko, Noriaki; Amada, Haruyo; Kasai, Noboru; Saiki, Seiichi; Hoshina, Hiroyuki; Ueki, Yuji

    2016-02-01

    A fibrous cesium (Cs) adsorbent was developed using radiation-induced graft polymerization with a cross-linked structure containing a highly stable adsorption ligand. The ligand, ammonium 12-molybdophosphate (AMP), was successfully introduced onto the fibrous polyethylene trunk material. The resulting Cs adsorbent contained 36% nonwoven fabric polyethylene (NFPE), 1% AMP, 2% triallyl isocyanurate (TAIC) and 61% glycidyl methacrylate (GMA). The adsorbent's Cs adsorption capacity was evaluated using batch and column tests. It was determined that the adsorbent could be used in a wide pH range. The amount of desorbed molybdenum, which can be used as an estimate for AMP stability on the Cs adsorbent, was minimized at the standard drinking water pH range of 5.8-8.6. Based from the inspection on the adherence of these results to the requirements set forth by the Food Sanitation Act by a third party organization, it can be concluded that the developed Cs adsorbent can be safely utilized for drinking water.

  16. Ion exchange performance of commercial crystalline silicotitanates for cesium removal

    Energy Technology Data Exchange (ETDEWEB)

    Braun, R.; Dangieri, T.J.; Fennelly, D.J. [and others

    1996-03-01

    A new class of inorganic ion exchangers called crystalline silicotitanates (CST), invented by researchers at Sandia National Laboratories and Texas A&M University, has been commercialized in a joint Sandia-UOP effort. The original developmental materials exhibited high selectivity for the ion exchange of cesium, strontium, and several other radionuclides from highly alkaline solutions containing molar concentrations of Na{sup +}. The materials also showed excellent chemical and radiation stability. Together, the high selectivity and stability of the CSTs made them excellent candidates for treatment of solutions such as the Hanford tank supernates and other DOE radwastes. Sandia National Laboratories and UOP have teamed under a Cooperative Research and Development Agreement (CRADA) to develop CSTs in the powdered form and in an engineered form suitable for column ion exchange use. A continuous-flow, column ion exchange process is expected to be used to remove Cs and other radionuclides from the Hanford supernatant. The powder material invented by the Sandia and Texas A&M team consists of submicron-size particles. It is not designed for column ion exchange but may be used in other applications.

  17. The separation of 65Zn from 113Sn and 207Bi radioisotopes by amalgam exchange and electro-analytical methods

    International Nuclear Information System (INIS)

    In this study, by using amalgam-exchange and electro-analytical methods, the separation of 65Zn radioisotope from a solution containing either one or both of the 113Sn and 207Bi radioisotopes were investigated. The radioisotopes were drawn into Zn-amalgam from the solution at first, and then 65Zn was recovered from the amalgam through back-electrolysis. No detectable contamination was observed and the recovery efficiency was found to be around 75%. (author)

  18. Using a non-radioisotopic, quantitative TRAP-based me thod detecting telomerase activities in human hepatoma cells

    Institute of Scientific and Technical Information of China (English)

    2000-01-01

    A non-radioisotopic, quantitative TRAP-based telom erase activity assay was established mainly by using SYBR Green-I staining instead of radioisotope. Comparing with conventional radioisotope based method, it was better in reproducibility and accuracy. Using this method, we found telomerase activities were absent in normal human liver cells, while detected in all of four human hepatoma cell lines (BEL-7404, SMMC-7721, QGY-7903 and HCCM) without significant differences.

  19. Current status of production and research of radioisotopes and radiopharmaceuticals in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Soenarjo, Sunarhadijoso; Tamat, Swasono R. [Center for Development of Radioisotopes and Radiopharmaceuticals, National Nuclear Energy Agency (BATAN), Kawasan Puspiptek, Serpong, Tangerang (Indonesia)

    2000-10-01

    The use of radioactive preparation in Indonesia has sharply increased during the past years, indicated by increase of the number of companies utilizing radioisotopes during 1985 to 1999. It has been clearly stressed in the BATAN's Strategic Plan for 1994-2014 that the production of radioisotopes and radiopharmaceuticals is one of five main industrial fields within the platform of the Indonesian nuclear industry. Research programs supporting the production of radioisotopes and radiopharmaceuticals as well as development of production technology are undertaken by the Research Center for Nuclear Techniques (RCNT) in Bandung and by the Radioisotope Production Center (RPC) in Serpong, involving cooperation with other research center within BATAN, universities and hospitals as well as overseas nuclear research institution. The presented paper describes production and research status of radioisotopes and radiopharmaceuticals in Indonesia after the establishment of P.T. Batan Teknologi in 1996, a government company assigned for activities related to the commercial application of nuclear technology. The reviewed status is divided into two short periods, i.e. before and after the Chairman Decree No. 73/KA/IV/1999 declaring new BATAN organizational structure. Subsequent to the Decree, all commercial requests for radioisotopes and radiopharmaceuticals are fulfilled by P.T. Batan Teknologi, while demands on novel radioactive preparations or new processing technology, as well as research and development activities should be fulfilled by the Center for the Development of Radioisotopes and Radiopharmaceuticals (CDRR) through non-commercial arrangement. The near-future strategic research programs to response to dynamic public demand are also discussed. The status of research cooperation with JAERI (Japan) is also reported. (author)

  20. Radioisotope studies for quantitative measurement of manganese absorption

    International Nuclear Information System (INIS)

    Purpose of the present study was to quantitatively determine the manganese absorption in growing rats by means of radioisotopes. First of all the following factors had to be investigated, which are significant for this determination: Measurability of stable and radioactive Mn in rat tissues; labelling of stable Mn and distribution of stable and radioactive Mn in the organism; verification of the isotope dilution method and of the comparative balance method with regard to its applicability for the determination of the true Mn absorption. We useed male and female Sprague-Dawley rats. The most important results are summarized in the following: in some separate tissues measurement of stable Mn was accompanied by difficulties. The measurement of radioactive Mn however, could be performed without any problems. 10 d after i.m. injection of 54Mn only 17% of the administered Mn was still detectable in the organism. However, there was no uniform tissue labelling found. Therefore it is possible to an only restricted extent to draw quantitative conclusions on the content of stable Mn. A high percentage of stable and radioactive Mn was found above all in the liver. The isotope dilution method permits by feces analysis to differentiate between unabsorbed Mn coming from the food and endogenic Mn coming from the organism itself. The effective Mn absorption was also determined by means of the comparative balance method. By means of the isotope dilution method we determined the quantitative Mn-absorption with staged Mn administration and the contribution of absorption and excretion to the homeostatic regulation mechanisms of Mn. We found that absorption and excretion help the organism to keep an almost constant Mn concentration even with a differing Mn supply. (orig./MG)

  1. Fundamental study on radioisotopic lymphography of the head and neck

    Energy Technology Data Exchange (ETDEWEB)

    Senda, K.; Sasaki, T. (Nagoya Univ. (Japan). Faculty of Medicine); Kaneko, M.

    1981-11-01

    The quality of the image was evaluated and improved using a scinticamera and three kinds of radiocolloid, /sup 198/Au colloid, sup(99m)Tc-phytate and sup(99m)Tc-Re colloid by radioisotopic lymphography. Intracutaneous injection of radiocolloid into the parietal scalp was able to take the image of the cervical node under a little influence of radioactivity remaining in the injection site because the site was significantly distant from the node and easily covered by a lead plate. Injecting the same radioactivity bilaterally into the scalp demonstrated symmetrically bilateral parotide or retroauricular node and its afferent vessel at about ten minutes and then this node to bilateral supraclavicular node in one to six hours after injection in patients with no evident lesion of the node. Difference of accumulated counts in the region of interest between both chains of these nodes was 12% on the average. Image of the node was obtained more clearly in three to six hours than at one though the time-activity curve of the neck revealed a peak in one hour after injection. Leakage of the agent out of the injection site was reduced to as lower as 3% of injected dose by means of skillful injection. Direct infusion of the agent into blood flow was recognized, so that image of the liver was demonstrated by either kind of radiocolloid, especially sup(99m)Tc-phytate, immediately after injection. A simultaneous injection of hyaluronidase, a tissue diffusing factor, enhanced slightly uptake of the agent in the lymph-node but it was not significant statistically (p < 0.05). Using reasonable dose, sup(99m)Tc-Re colloid obtained high accumulated count in the region of the node and showed the best quality of image in demonstrating the vessel and node separately and widely.

  2. The Texas A&M Radioisotope Production and Radiochemistry Program

    Energy Technology Data Exchange (ETDEWEB)

    Akabani, Gamal [Texas A & M Univ., College Station, TX (United States)

    2016-08-31

    The main motivation of the project at Texas A&M University was to carry out the production of critically needed radioisotopes used in medicine for diagnostic and therapy, and to establish an academic program in radionuclide production and separation methods. After a lengthy battle with the Texas A&M University Radiation Safety Office, the Texas Department of State Health Services granted us a license for the production of radionuclides in July 2015 allowing us to work in earnest in our project objectives. Experiments began immediately after licensing and we started the assembly and testing of our target systems. There were four analytical/theoretical projects and two experimental target systems. These were for At-211 production and for Zn- 62/Cu-62 production. The theoretical projects were related to the production of Mo-99/Tc-99m using a) a subcritical aqueous target system and b) production of Tc-99m from accelerator generated Mo-99 utilizing a photon-neutron interaction with enriched Mo-100 targets. The two experimental projects were the development of targetry systems and production of At-211 and Zn-62/Cu-62 generator. The targetry system for At-211 has been tested and production of At-211 is chronic depending of availability of beam time at the cyclotron. The installation and testing of the targetry system for the production of Zn-62/Cu-62 has not been finalized. A description of the systems is described. The academic program in radionuclide production and separation methods was initiated in the fall of 2011 and due to the lack of a radiochemistry laboratory it was suspended. We expect to re-start the academic program at the Texas A&M Institute for Preclinical Studies under the Molecular Imaging Program.

  3. Radioisotopic exploration of patients suffering from chronic Chagas' disease

    International Nuclear Information System (INIS)

    The importance of Chagas' disease - a histic and haematic parasitosis endemic in extensive areas of Latin America, with 60 million people exposed to it and 20 million infected - stems from the high sickness and mortality rates affecting mainly rural and fringe populations. Nevertheless, progressive urbanization of the disease due to population migration and blood transfusion is being observed. The authors studied 56 cases of patients with Chagas' disease, 45 of whom were detected asymptomatically when donating blood by immunoserological reactions involving complement fixation and haemagglutination. Radiotracers were used to explore ventricular function in 56 cases; oesophageal transit in 29 cases; the upper urinary tract in 25 cases; and bladder function in 22 cases. All four procedures were applied to 19 patients. In 40 patients a study was made of the left and right ventricular function, the left being found altered in 17% of the cases, the right ventricular function in 22% and both in 25%. In 26 cases (65%) anomalies were encountered in at least one of the two ventricles. Oesophageal transit was altered in 20 patients, 16 of them asymptomatically. In 6 of them it was prolonged, in 4 it was adynamic and in 10 cases uncoordinated. The upper urinary tract showed abnormalities (pyelic dilation, pyelo-ureteral dyskinesia, ureteral dyskinesia, ureteral dilation and/or vesico-ureteral reflux) in 22 patients, in all cases asymptomatically. Bladder function was abnormal in 18 asymptomatic patients, basically represented by a residual decompensated cystopathy with a hypotonicity of different degrees. Of the 45 patients without symptoms detected when donating blood, there was alteration of ventricular function in 49%, of oesophageal transit in 68%, of the upper urinary tract in 90%, and of bladder function in 78%, with an overall figure of 66% abnormal examinations from 106 radioisotopic studies

  4. Productivity of a nuclear chemical reactor with gamma radioisotopic sources

    International Nuclear Information System (INIS)

    According to an established mathematical model of successive Compton interaction processes the made calculations for major distances are extended checking the acceptability of the spheric geometry model for the experimental data for radioisotopic sources of Co-60 and Cs-137. Parameters such as the increasing factor and the absorbed dose served as comparative base. calculations for the case of a punctual source succession inside a determined volume cylinder are made to obtain the total dose, the deposited energy by each photons energetic group and the total absorbed energy inside the reactor. Varying adequately the height/radius relation for different cylinders, the distinct energy depositions are compared in each one of them once a time standardized toward a standard value of energy emitted by the reactor volume. A relation between the quantity of deposited energy in each point of the reactor and the conversion values of chemical species is established. They are induced by electromagnetic radiation and that are reported as ''G'' in the scientific literature (number of molecules formed or disappeared by each 100 e.v. of energy). Once obtained the molecular performance inside the reactor for each type of geometry, it is optimized the height/radius relation according to the maximum production of molecules by unity of time. It is completed a bibliographical review of ''G'' values reported by different types of aqueous solutions with the purpose to determine the maximum performance of molecular hydrogen as a function of pH of the solution and of the used type of solute among other factors. Calculations for the ethyl bromide production as an example of one of the industrial processes which actually work using the gamma radiation as reactions inductor are realized. (Author)

  5. Notification prescribing the quantities of radioisotopes and others

    International Nuclear Information System (INIS)

    The notification is wholly revised under the order and the regulations for enforcing the law concerning prevention from radiation hazards due to radioisotopes. The concentration of isotopes emitting radiation shall be 0.002 micro-curie per gram. When not tightly sealed, the quantity of such isotopes shall be 0.1 micro-curie for strontium 90 and isotopes emitting alpha rays, 1 micro-curie for isotopes emitting radiation with half-life of more than 30 days, 10 micro-curie for isotopes emitting radiation with half-life of less than 30 days and 100 micro-curie for Hydrogen 3, Beryllium 7, Carbon 14, Fluorine 18, etc. The quantity of isotopes shall be more than 10 curie for those with automatic indicators and more than 3,000 curie for those interlocked. In the controlled area the permissible dose of exterior radiation is 30 mili-rem for a week. The maximum permissible exposure dose for the workers engaged in radiation business is 3 rem for 3 months. The maximum permissible accumulative dose for such workers is a figure (unit rem) calculated by a formula D = 5(N-18), when D means the permissible accumulative dose and N number of the age. The permissible exposure dose is 12 rem for the urgent work and 1.5 rem for a year for the persons who enter into the controlled area on business. The maximum permissible density in the air, under water and on the surface, etc. are in detail prescribed with tables attached. (Okada, K.)

  6. Studies of copper transport in mammalian cells using copper radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Camakaris, J.; Voskoboinik, I.; Brooks, H.; Greenough, M. [University of Melbourne, Parkville, VIC (Australia). Department of Genetics; Smith, S. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia). Radiopharmaceuticals Division; Mercer, J. [Deakin University, Clayton, VIC (Australia). Centre of Cellular and Molecular Biology

    1998-12-31

    The trace element copper poses a major problem for all organisms. It is essential as a number of vital enzymes require it. Copper deficiency can lead to neurological disorders, osteoporosis and weakening of arteries. However Cu is also highly toxic and homeostatic mechanisms have evolved to maintain Cu at levels which satisfy requirements but do not cause toxicity. Toxicity is mediated by the oxidative capacity of Cu and its ability to generate toxic free radicals. There are several acquired and inherited diseases due to either Cu toxicity or Cu deficiency. The study of these diseases facilitates identification of genes and proteins involved in copper homeostasis, and this in turn will provide rational therapeutic approaches. Using the copper radioisotopes {sup 64}Cu (t1/2 = 12.8 hr) and {sup 67}Cu (t1/2 = 61 hr) we have developed a number of systems for studying copper transport in mammalian cells. These include investigation of copper uptake, copper efflux and ligand blot assays for Cu-binding proteins. Our studies have focused on Menkes disease which is an inherited and usually lethal copper deficiency disorder in humans. We have demonstrated that the Menkes protein is directly involved as a copper efflux pump in mammalian cells. Using cells overexpressing the Menkes protein we have provided the first biochemical evidence that this functions as a Cu translocating (across the membrane) P-type ATPase (Voskoboinik et al., FEBS Letters, in press). These studies were carried out using purified plasma membrane vesicles. We are now carrying out structure- function studies on this protein using targeted mutations and assaying using the radiocopper vesicle assay. Recently we have commenced studies on the role of amyloid precursor protein (APP) in copper transport and relationship of this to Alzheimers disease

  7. Use of copper radioisotopes in investigating disorders of copper metabolism

    Energy Technology Data Exchange (ETDEWEB)

    Camakaris, J.; Voskoboinik, I.; Brooks, H.; Greenough, M. [University of Melbourne, Parkville, VIC (Australia). Department of Genetics; Smith, S. [Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW (Australia). Radiopharmaceuticals Division; Mercer, J. [Deakin University, Rusden Campus, Clayton, VIC (Australia). Centre of Cellular and Molecular Biology

    1998-12-31

    Full text: Copper is an essential trace element for life as a number of vital enzymes require it. Copper deficiency can lead to neurological disorders, osteoporosis and weakening of arteries. However Cu is also highly toxic and homeostatic mechanisms have evolved to maintain Cu at levels which satisfy requirements but do not cause toxicity. Toxicity is mediated by the oxidative capacity of Cu and its ability to generate toxic free radicals. There are several acquired and inherited diseases due to either Cu toxicity or Cu deficiency. The study of these diseases facilitates identification of genes and proteins involved in copper homeostasis, and this in turn will provide rational therapeutic approaches. Our studies have focused on Menkes disease in humans which is an inherited and usually lethal copper deficiency. Using copper radioisotopes {sup 64}Cu (t 1/2 = 12.8 hr) and {sup 67}Cu (t 1/2 = 61 hr) we have studied the protein which is mutated in Menkes disease. This is a transmembrane copper pump which is responsible for absorption of copper into the body and also functions to pump out excess Cu from cells when Cu is elevated. It is therefore a vital component of normal Cu homeostasis. We have provided the first biochemical evidence that the Menkes protein functions as a P-type ATPase Cu pump (Voskoboinik et al., FEBS Letters, in press) and these data will be discussed. The assay involved pumping of radiocopper into purified membrane vesicles. Furthermore we have transfected normal and mutant Menkes genes into cells and are carrying out structure-function studies. We are also studying the role of amyloid precursor protein (APP) as a Cu transport protein in order to determine how Cu regulates this protein and its cleavage products. These studies will provide vital information on the relationship between Cu and APP and processes which lead to Alzheimers disease

  8. Misinterpretation on the risk of radioactive cesium contained in the disaster wastes

    International Nuclear Information System (INIS)

    Osaka Prefectural Government accepted the disaster wastes contained radioactive cesium after investigation them during one year. I explained the process and discussed about the risk management by people and the self-government body. The environmental pollution by radioactive cesium and Act on Special Measures concerning the Handling of Pollution by Radioactive Materials, the progress of treatment of debris, the concentration of radioactive cesium in debris, the acceptance conditions of debris contained small amount of radioactive cesium, evaluation of effects of radioactive materials in debris on the environment, and citizen's opinion of Osaka prefecture are described. The important investigation area of radioactive contamination on the basis of Act on Special Measures concerning the Handling of Pollution by Radioactive Materials, total amount of waste from Fukushima nuclear accident and debris in Miyagi, Iwate and Fukushima prefecture, the concentration of radioactive cesium in debris in Rikuzentakata and Miyako city as of September, 2011, and cumulative number of citizen's opinion to Osaka are illustrated. (S.Y.)

  9. Local mat-forming cyanobacteria effectively facilitate decontamination of radioactive cesium in rice fields

    International Nuclear Information System (INIS)

    The most effective and widespread method to decontaminate radioactive cesium from the Fukushima Daiichi Nuclear Power Plant Disaster was peeling topsoil. But the method had problems, such as large amounts of discarded soil and large-scale work. In nature, cyanobacteria formed biomats on the ground surface and facilitated peeling topsoil when the biomats dried. The cyanobacteria-facilitating peeling decontamination method utilized these cyanobacterial properties. Cyanobacteria are located all over Japan and 'local' cyanobacteria could be used for decontamination without introducing new species. Utilizing cyanobacteria could decrease the amount of discarded soil to about 30% and downsize the execution-scale to individual locations. Cyanobacterial biomats were easily cultivated, especially in rice fields, by maintaining wet conditions and exposure to 100 - 83% solar radiation. Shading by a thin net was helpful in maintaining an environment suitable for cyanobacteria. Nowadays, to prevent uptake of radioactive cesium into rice, K+ is usually added to fertilizer in rice fields. The K+ fertilization in rice fields might also enhance cyanobacterial capture of radioactive cesium, because high concentrations of K+ enhanced cyanobacterial uptake of Cs+. Cyanobacteria could also mitigate the risk of radioactive cesium moving away from a decontaminating rice field. Therefore, the cyanobacteria-facilitating peeling decontamination method was proposed as an easy and safe 'D.I.Y.' method for both farmers and the environment. Besides, plowing rice fields with water before peeling improved the efficiency of this method, because plowing increased the radioactive cesium concentration in the topsoil. (author)

  10. Development program for magnetically assisted chemical separation: Evaluation of cesium removal from Hanford tank supernatant

    International Nuclear Information System (INIS)

    Magnetic particles (MAG*SEPSM) coated with various absorbents were evaluated for the separation and recovery of low concentrations of cesium from nuclear waste solutions. The MAG*SEPSM particles were coated with (1) clinoptilolite, (2) transylvanian volcanic tuff, (3) resorcinol formaldehyde, and (4) crystalline silico-titanate, and then were contacted with a Hanford supernatant simulant. Particles coated with the crystalline silico-titanate were identified by Bradtec as having the highest capacity for cesium removal under the conditions tested (variation of pH, ionic strength, cesium concentration, and absorbent/solution ratio). The MAG*SEPSM particles coated with resorcinol formaldehyde had high distribution ratios values and could also be used to remove cesium from Hanford supernant simulant. Gamma irradiation studies were performed on the MAG*SEPSM particles with a gamma dose equivalent to 100 cycles of use. This irradiation decreased the loading capacity and distribution ratios for the particles by greater than 75%. The particles demonstrated high sensitivity to radiolytic damage due to the degradation of the polymeric regions. These results were supported by optical microscopy measurements. Overall, use of magnetic particles for cesium separation under nuclear waste conditions was found to be marginally effective

  11. Efficiency of fly ash belite cement and zeolite matrices for immobilizing cesium.

    Science.gov (United States)

    Goñi, S; Guerrero, A; Lorenzo, M P

    2006-10-11

    The efficiency of innovative matrices for immobilizing cesium is presented in this work. The matrix formulation included the use of fly ash belite cement (FABC-2-W) and gismondine-type Na-P1 zeolite, both of which are synthesized from fly ash of coal combustion. The efficiency for immobilizing cesium is evaluated from the leaching test ANSI/ANS 16.1-1986 at the temperature of 40 degrees C, from which the apparent diffusion coefficient of cesium is obtained. Matrices with 100% of FABC-2-W are used as a reference. The integrity of matrices is evaluated by porosity and pore-size distribution from mercury intrusion porosimetry, X-ray diffraction and nitrogen adsorption analyses. Both matrices can be classified as good solidify systems for cesium, specially the FABC-2-W/zeolite matrix in which the replacement of 50% of belite cement by the gismondine-type Na-P1 zeolite caused a decrease of two orders of magnitude of cesium mean Effective Diffusion Coefficient (D(e)) (2.8e-09 cm(2)/s versus 2.2e-07 cm(2)/s, for FABC-2-W/zeolite and FABC-2-W matrices, respectively). PMID:16759800

  12. Preparation of Modified Kaolin Filler with Cesium and Its Application in Security Paper

    Directory of Open Access Journals (Sweden)

    Houssni El-Saied

    2013-01-01

    Full Text Available In this study, cesium was added intentionally during paper manufacture for protecting the papers against forgery and counterfeiting by sorbing cesium ions (Cs+ on kaolin, used as special filler in papermaking. The sorption of cesium from aqueous solution by kaolin was studied as a function of pH, shaking time, cesium initial concentration, and mass of kaolin using batch technique. The results showed that a solution containing 10 mg/L Cs+ and 250 mg of kaolin at pH 6 can be used to modify the kaolin. Paper handsheets were prepared containing various percentages of the modified kaolin. The mechanical and optical properties of paper handsheets were studied. The prepared paper handsheets were irradiated by gamma irradiation using different doses. Fourier transform infrared (FTIR spectroscopy was used to study the effect of kaolin modification by cesium and gamma irradiation on paper handsheets properties. The results indicated that modified kaolin enhanced the mechanical and optical properties of paper handsheets. Electron spin resonance (ESR spectroscopy and laser-induced breakdown spectroscopy (LIBS were also used. They provided rapid, sensitive and nondestructive techniques in differentiating between different questioned documents. This study presents a new concept in manufacturing security papers and anticounterfeiting applications.

  13. Cesium-137 in soil texture fractions and its impact on Cesium-137 soil-to-plant transfer

    International Nuclear Information System (INIS)

    Field studies at two sites contaminated by the Chernobyl fallout showed 137Cesium (Cs) soil-to-plant transfer factors in wheat, rye and potato. Transfer values ranged from 0.0017 (potato tuber) to 0.07 (wheat straw). Generally transfer coefficients in cereal grains and potato tubers were significantly below the values of the shoots. A comparison of the two sites led to the conclusion that for all plants investigated 137Cs transfer factors were higher in Lower Austria (Calcic Chernozem) than in Upper Austria (Eutric Cambisol). The specific activities of the texture fractions of the two soil types increased from sand to silt and clay. In the Calcic Chernozem the ratio of the 137Cs activity in the silt fraction to the total activity in the soil was considerably higher than in the Eutric Cambisol. At the same time extractability of 137Cs from the silt fraction of the latter soil was clearly lower. Both results mainly were attributed to the differences between the soils according to the organic matter content of the silt fractions, the Calcic Chernozem being seven times higher. Therefore, the differences in the 137Cs-soil-to-plant transfer can be attributed partly to these soil characteristics. (authors)

  14. Reflections on the juridical implications of the medical use of radiations and radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Campos, Ana Celia P.P. [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Faculdade de Direito]. E-mails: anaceu2000@yahoo.com.br; Cuperschmid, Ethel Mizrahy [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Centro de Memoria da Medicina - CEMMOR]. E-mail: ethel.mizrahy@yahoo.com; Campos, Tarcisio P. Ribeiro de [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Programa de Pos-graduacao em Ciencias e Tecnicas Nucleares]. E-mail: campos@nuclear.ufmg.br

    2007-07-01

    The pacific use of radiation and radioisotopes for the society presents radiological risks, due its capacity to produce damage to environmental and human being, contrasting with its high economic and social benefits. In the face of the risk, juridical system leans over to reach the required regulations that implies in the balance between human and environmental security and the expected improvements of the medical nuclear techniques. The Brazilian Constitution of 1988 tries to provide the normalization for the application of the nuclear energy and its radioisotopes. However, target as a strategically technology and due to its expansion, its regulations still deserves analyses and reflections. The present paper starts from the Constitution presenting the references about the theme and analyzing it. It is addressed the principle of the objective civil responsibility making analyses on the use of radiations and radioisotope on the medicine. It addresses the role of federal autonomy related to the 'MCT - Ministerio de Ciencia e Tecnologia' with its accumulative functions in society, such as scientific and technologic development, education, and its own focalization. The recent opening of the monopoly for the production of radioisotopes for very short half-lives is also discussed. It makes a comparison between juridical aspects of Brazil with international system. The present article contributes to open same topics of discussions on the Brazilian juridical aspects involving radiations and radioisotopes application on medicine. (author)

  15. Planning For Multiple NASA Missions With Use Of Enabling Radioisotope Power

    Energy Technology Data Exchange (ETDEWEB)

    S.G. Johnson; K.L. Lively; C.C. Dwight

    2013-02-01

    Since the early 1960’s the Department of Energy (DOE) and its predecessor agencies have provided radioisotope power systems (RPS) to NASA as an enabling technology for deep space and various planetary missions. They provide reliable power in situations where solar and/or battery power sources are either untenable or would place an undue mass burden on the mission. In the modern era of the past twenty years there has been no time that multiple missions have been considered for launching from Kennedy Space Center (KSC) during the same year. The closest proximity of missions that involved radioisotope power systems would be that of Galileo (October 1989) and Ulysses (October 1990). The closest that involved radioisotope heater units would be the small rovers Spirit and Opportunity (May and July 2003) used in the Mars Exploration Rovers (MER) mission. It can be argued that the rovers sent to Mars in 2003 were essentially a special case since they staged in the same facility and used a pair of small launch vehicles (Delta II). This paper examines constraints on the frequency of use of radioisotope power systems with regard to launching them from Kennedy Space Center using currently available launch vehicles. This knowledge may be useful as NASA plans for its future deep space or planetary missions where radioisotope power systems are used as an enabling technology. Previous descriptions have focused on single mission chronologies and not analyzed the timelines with an emphasis on multiple missions.

  16. The production of cyclotron radioisotopes and radiopharmaceuticals at the national accelerator centre in South Africa

    International Nuclear Information System (INIS)

    Accelerator radioisotopes have been manufactured in South Africa since 1965 with the 30 MeV cyclotron at the Council for Scientific and Industrial Research (CSIR) in Pretoria. After its closure in 1988, the radioisotope production programme was continued at the National Accelerator Centre (NAC) with the 200 MeV separated sector cyclotron (SCC) utilizing the 66 MeV proton beam, which is shared with the neutron therapy programme during part of the week. A variety of radiopharmaceuticals, such as 18F-FDG, 67Ga-citrate, a 67Ga-labelled resin. 111In-chloride, 111In-oxine and 111In-labelled resin. 123I-sodium iodide and 123I-labelled compounds, 201Tl-chloride, as well as the 81Rb/81mKr gas generator, are prepared for use in the nuclear medicine departments of 12 State hospitals and about 28 private nuclear medicine clinics in South Africa. A few longer-lived radioisotopes, such as 22Na, 55Fe and 139Ce, are also produced for research or industrial use. A research and development programme is running to develop new production procedures to produce radioisotopes and radiopharmaceuticals, or to improve existing production procedures. As part of a programme to utilize the beam time optimally, the production of some other radioisotopes is investigated. (author)

  17. Development of Kabila rocket: A radioisotope heated thermionic plasma rocket engine

    Directory of Open Access Journals (Sweden)

    Kalomba Mboyi

    2015-04-01

    Full Text Available A new type of plasma rocket engine, the Kabila rocket, using a radioisotope heated thermionic heating chamber instead of a conventional combustion chamber or catalyst bed is introduced and it achieves specific impulses similar to the ones of conventional solid and bipropellant rockets. Curium-244 is chosen as a radioisotope heat source and a thermal reductive layer is also used to obtain precise thermionic emissions. The self-sufficiency principle is applied by simultaneously heating up the emitting material with the radioisotope decay heat and by powering the different valves of the plasma rocket engine with the same radioisotope decay heat using a radioisotope thermoelectric generator. This rocket engine is then benchmarked against a 1 N hydrazine thruster configuration operated on one of the Pleiades-HR-1 constellation spacecraft. A maximal specific impulse and power saving of respectively 529 s and 32% are achieved with helium as propellant. Its advantages are its power saving capability, high specific impulses and simultaneous ease of storage and restart. It can however be extremely voluminous and potentially hazardous. The Kabila rocket is found to bring great benefits to the existing spacecraft and further research should optimize its geometric characteristics and investigate the physical principals of its operation.

  18. Determination of details of regulations concerning transportation of radioisotopes by vehicles

    International Nuclear Information System (INIS)

    The determination is defined under the regulation concerning transportation of radioactive materials by vehicles. Permissible surface density shall be 1/100,000 micro-curie per centi-meter2 for radioisotopes emitting alpha rays and 1/10,000 micro-curie per centi-meter2 for radioisotopes not emitting alpha rays. Radioisotope loads are classified to types of L, A, BM and BU. Quantity of radioactivity or radioisotope is stipulated for each type of loads respectively with tables attached. Radioactivity quantity of solid L load is 1/1,000 of Al value in the appendix table. For tritium water of fluid L load radioactivity quantity is 1,000 curie, 100 curie and 1 curie respectively according to the water radioactivity per litre of less than 0.1 curie, less than 1 curie and more than 0.1 curie, and more than 1 curie. Conditions concerning A, BM and BU loads are provided for in detail in the bylaw annexed. Quantity of leaking specified for BM load is 1/1,000,000 of A2 value and in other particular cases A2 value, etc. Leaking quantity for BU load is 1/1,000 of A2 value. Radioactive concentration of radioisotopes to be transferred not as radioactive goods is 1/10,000 of A2 value per gram. (Okada, K.)

  19. Problems, experience in designing and application of radioisotope devices in mining and metallurgical sector

    International Nuclear Information System (INIS)

    This report presents basic outcomes of development of methods and means of materials composition monitoring, using radioactive isotopes.Informative and measuring systems to analyze moisture of loose materials in technological circulation, using neutron sources, were considered. Method of moisture content measuring of loose materials with variable density, based on individual registration of thermal and above-thermal neutrons decelerated in a substance, was validated. Radioisotope method of solid fuel ash content determination in the conveyor belt, based on application of radioisotope Am-241 source, was considered.Basic errors of radioisotope methods of moisture and ash content measuring of heterogeneous substances with variable density and without sampling from technological circulation and preparation for the measuring, were studied and demonstrated.Examples of methodical, algorithmic, technical and constructive provision of radioisotope devices introduction, fabrication and designing were given.Technical and economical outcomes of large-scale industrial application of the developed devices and systems are presented. The issues to increase efficiency of activity on radioisotope apparatus designing were discussed

  20. Sympathetic cooling in a rubidium cesium mixture: Production of ultracold cesium atoms; Sympathetisches Kuehlen in einer Rubidium-Caesium-Mischung: Erzeugung ultrakalter Caesiumatome

    Energy Technology Data Exchange (ETDEWEB)

    Haas, M.

    2007-07-01

    This thesis presents experiments for the production of ultracold rubidium cesium mixture in a magnetic trap. The long-termed aim of the experiment is the study of the interaction of few cesium atoms with a Bose-Einstein condensate of rubidium atoms. Especially by controlled variation of the cesium atom number the transition in the description of the interaction by concepts of the one-particle physics to the description by concepts of the many-particle physics shall be studied. The rubidium atoms are trapped in a magneto-optical trap (MOT) and from there reloaded into a magnetic trap. In this the rubidium atoms are stored in the state vertical stroke f=2,m{sub f}=2 right angle of the electronic ground state and evaporatively cooled by means of microwave-induced transitions into the state vertical stroke f=1,m{sub f}=1] (microwave cooling). The cesium atoms are also trppaed in a MOT and into the same magnetic trap reloaded, in which they are stored in the state vertical stroke f=4,m{sub f}=4 right angle of the electronic ground state together with rubidium. Because of the different hyperfine splitting only rubidium is evaporatively cooled, while cesium is cooled jointly sympathetically - i.e. by theramal contact via elastic collisions with rubidium atoms. The first two chapters contain a description of interatomic interactions in ultracold gases as well as a short summary of theoretical concepts in the description of Bose-Einstein condensates. The chapters 3 and 4 contain a short presentation of the methods applied in the experiment for the production of ultracold gases as well as the experimental arrangement; especially in the framework of this thesis a new coil system has been designed, which offers in view of future experiments additionally optical access for an optical trap. Additionally the fourth chapter contains an extensive description of the experimental cycle, which is applied in order to store rubidium and cesium atoms together into the magnetic trap. The

  1. Charged particle cross-section database for medical radioisotope production: diagnostic radioisotopes and monitor reactions. Final report of a co-ordinated research project

    International Nuclear Information System (INIS)

    Medical applications of nuclear radiation are of considerable interest to the IAEA. Cyclotrons and accelerators, available in recent years in an increasing number of countries, are being used for the production of radioisotopes for both diagnostic and therapeutic purposes. The physical basis of this production is described through interaction of charged particles, such as protons, deuterons and alphas, with matter. These processes have to be well understood in order to produce radioisotopes in an efficient and clean manner. In addition to medical radioisotope production, reactions with low energy charged particles are of primary importance for two major applications. Techniques of ion beam analysis use many specific reactions to identify material properties, and in nuclear astrophysics there is interest in numerous reaction rates to understand nucleosynthesis in the Universe. A large number of medically oriented cyclotrons have been running in North America, western Europe and Japan for more than two decades. In recent years, 30-40 MeV cyclotrons and smaller cyclotrons (Ep < 20 MeV) have been installed in several countries. Although the production methods are well established, there are no evaluated and recommended nuclear data sets available. The need for standardization was thus imminent. This was pointed out at three IAEA meetings. Based on the recommendations made at these meetings, the IAEA decided to undertake and organize the Co-ordinated Research Project (CRP) on Development of Reference Charged Particle Cross-Section Database for Medical Radioisotope Production. The project was initiated in 1995. It focused on radioisotopes for diagnostic purposes and on the related beam monitor reactions in order to meet current needs. It constituted the first major international effort dedicated to standardization of nuclear data for radioisotope production. It covered the following areas: Compilation of data on the most important reactions for monitoring light ion

  2. Applicability of sodium alginate in decorporation therapy of strontium radioisotopes in human being; Aplicabilidade do alginato de sodio na terapia de decorporacao de radioisotopos de estroncio em seres humanos

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Aloisio Cordilha

    1999-10-01

    The increasing release of fission products from nuclear weapon tests in the environment has been rising the levels of radioactive contamination of food chains caused by the fall-out of these elements. In cases of accidental exposure, human subjects could be submitted to an internal contamination, which is likely to include several radionuclides. Special concern must be given, however, to the radioactive isotopes of strontium, cesium and iodine, along with the highly radio toxic transuranium elements like cerium. It was found that sodium alginate, a polyelectrolyte commonly used in food industry and obtained from brown algae (Phaeophyceae), provides the selective suppression of absorption of radioactive strontium presented in the ingested food material with no disturbance of the electrolyte balance nor undesirable side effects, even for a long term treatment. Moreover, these patterns were maintained when alginate was associated to other decontamination additives, specially those related to the other radioisotopes mentioned above, as, in this case, losses in the effectiveness, mutual interference or adverse health effects were not detected. These conclusions ground the discussion about the present trend in the usual choice of EDTA/DTPA complex therapy rather than of alginate therapy for medical assistance of radiocontaminated patients, although they corroborate the efficiency and usefulness of alginate salts in situations related to extensive intakes of strontium radioisotopes alone or associated to other fission products. The purpose of the present work is to make a general review of the alginate therapy as well as to discuss its present and future therapeutic importance from the scientific and institutional points of view. (author)

  3. Comparison of organic and inorganic ion exchange materials for removal of cesium and strontium from tank waste

    Energy Technology Data Exchange (ETDEWEB)

    Brown, G. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-10-01

    This work is part of an ESP task to develop high-capacity, selective, solid extractants for cesium, strontium, and technetium from nuclear wastes. Pacific Northwest National Laboratory (PNNL) staff are investigating novel ion exchangers for use in nuclear waste remediation (groundwater, high-level waste (HLW), and low-level waste (LLW)). Waste components targeted for remediation include cesium, strontium, and technetium.

  4. Behavior of ruthenium, cesium and antimony during simulated HLLW vitrification

    International Nuclear Information System (INIS)

    The behavior of ruthenium, cesium, and antimony during the vitrification of simulated high-level radioactive liquid wastes (HLLW) in a liquid fed melter was studied on a laboratory scale and on a semi-pilot scale. In the laboratory melter of a 2.5 kg capacity, a series of tests with the simulate traced with 103Ru, 134Cs and 124Sb, has shown that the Ru and Cs losses to the melter effluent are generally higher than 10% whereas the antimony losses remain lower than 0.4%. A wet purification system comprising in series, a dust scrubber, a condenser, an ejector venturi and an NOx washing column retains most of the activity present in the off-gas so that the release fractions for Ru at the absolute filter inlet ranges between 5.10-3 to 5.10-5% of the Ru fed, for Cs the corresponding release fraction ranges between 3.10-3 to 10-4% and for Sb the release fraction ranges between 1.7 10-4 to 1.7 10-5%. The same experiments were performed at a throughput of 1 to 2 1 h-1 of simulated solution in the semi-pilot scale unit RUFUS. The RUFUS unit comprises a glass melter with a 50 kg molten glass capacity and the wet purification train comprises in series a dust scrubber, a condenser, an ejector venturi and an NOx washing column. The tracer tests were restricted to 103Ru and 134Cs since the laboratory tests had shown that the antimony losses were very low. The results of the tests are presented

  5. Cesium and Strontium Specific Exchangers for Nuclear Waste Effluent Remediation

    International Nuclear Information System (INIS)

    During the past 50 years, nuclear defense activities have produced large quantities of nuclear waste that now require safe and permanent disposal. The general procedure to be implemented involves the removal of cesium and strontium from the waste solutions for disposal in permanently vitrified media. This requires highly selective sorbents or ion exchangers. Further, at the high radiation doses present in the solution, organic exchangers or sequestrants are likely to decompose over time. Inorganic ion exchangers are resistant to radiation damage and can exhibit remarkably high selectivities. We have synthesized three families of tunnel-type ion exchangers. The crystal structures of these compounds as well as their protonated phases, coupled with ion exchange titrations, were determined and this information was used to develop an understanding of their ion exchange behavior. The ion exchange selectivities of these phases could be regulated by isomorphous replacement of the framework metals by larger or smaller radius metals. In the realm of layered compounds, we prepared alumina, silica, and zirconia pillared clays and sodium micas. The pillared clays yielded very high Kd values for Cs+ and were very effective in removing Cs+ from groundwaters. The sodium micas also had a high affinity for Cs+ but an even greater attraction for S42+. They also possess the property of trapping these ions permanently as the layers slowly decrease their interlayer distance as loading occurs. Sodium nonatitanate exhibited extremely high Kd values for Sr2+ in alkaline tank wastes and should be considered for removal of Sr2+ in such cases. For tank wastes containing complexing agents, we have found that adding Ca2+ to the solution releases the complexed Sr2+ which may then be removed with the CST exchanger

  6. Immobilisation and solidification of cesium on 11 A calcium silicate hydroxy hydrate column

    International Nuclear Information System (INIS)

    Calcium silicate hydrate closely resembling silicate mineral 11 A tobermorite has been synthesised by hydrothermal treatment of lime and silica at 175 degC. The synthetic mineral exhibits selectivity for Cs+ in the presence of strong solutions of alkali and alkaline earth cations, viz, Na+, K+, Mg2+, Ca2+, Sr2+, etc. The Al-substituted form of this mineral effectively separates cesium ion when used as an exchanger in column of size 35x5 mm (hxr). It is possible to remove 98.65±0.5%Cs+ from a mixed solution of cesium and sodium (0.0001N Cs+ + 0.5N Na+). Column separation of cesium from simulated intermediate level waste solution shows that from the first run ∼ 76% Cs+ can be immobilised on a small column, 18x10mm (hxr), having 2.0 g of exchanger. (author)

  7. Studies of cesium and strontium migration in unconsolidated Canadian geological materials

    International Nuclear Information System (INIS)

    Distribution coefficients (Ksub(d)) were measured for cesium and strontium in 16 samples of Canadian unconsolidated geological materials. The samples were collected to cover a wide range of grain size, clay-mineral composition, cation exchange capacity and carbonate mineral content. Distribution coefficients ranged between 102 and 2.0 x 104 ml/g for cesium and between 2.5 and 102 ml/g for strontium, indicating that most unconsolidated geological materials have a substantial ability to retard the migration of cesium, while strontium could generally be expected to be somewhat more mobile. The measured K values were not significantly correlated with the measured soil properties, but appeared to be significantly affected by the background concentration of stable isotopes of the respective radionuclides

  8. The effects of using Cesium-137 teletherapy sources as a radiological weapon (dirty bomb)

    CERN Document Server

    Liolios, Theodore

    2009-01-01

    While radioactive sources used in medical diagnosis do not pose a great security risk due to their low level of radioactivity, therapeutic sources are extremely radioactive and can presumably be used as a radiological weapon. Cobalt-60 and Cesium-137 sources are the most common ones used in radiotherapy with over 10,000 of such sources currently in use worldwide, especially in the developing world, which cannot afford modern accelerators. The present study uses computer simulations to investigate the effects of using Cesium-137 sources from teletherapy devices as a radiological weapon. Assuming a worst-case terrorist attack scenario, we estimate the ensuing cancer mortality, land contamination, evacuation area, as well as the relevant evacuation, decontamination, and health costs in the framework of the linear risk model. The results indicate that an attack with a Cesium-137 dirty bomb in a large metropolitan city (especially one that would involve several teletherapy sources) although would not cause any sta...

  9. Phosphate ceramic solidification and stabilization of cesium-containing crystalline silicotitanate resins.

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C. A.

    1999-05-11

    This paper reports on the fabrication and testing of magnesium potassium phosphate (MKP)-bonded cesium-loaded crystalline silicotitanate (CST) resins. Typical waste loading of CST resins in the final waste forms was 50 wt.%. Physical and chemical characterization of the MKP materials has shown them to be physically, chemically, and mineralogically stable. Long-term durability studies (using the AN 16.1 standard test) showed a leachability index of {approx}18 for cesium in the phosphate matrix when exposed to deionized water under ambient and elevated temperatures. Leaching of cesium was somewhat higher than in glass waste forms as per PCT and MCC-1 tests. MKP-based final waste forms showed no significant weight changes after exposure to aqueous media for {approx}90 days, indicating the highly insoluble nature of the phosphate matrix. In addition, durability of the CST-MKP waste forms was further established by freeze-thaw cycling tests.

  10. Determining Reactor Flux from Xenon-136 and Cesium-135 in Spent Fuel

    CERN Document Server

    Hayes, A C

    2012-01-01

    The ability to infer the reactor flux from spent fuel or seized fissile material would enhance the tools of nuclear forensics and nuclear nonproliferation significantly. We show that reactor flux can be inferred from the ratios of xenon-136 to xenon-134 and cesium-135 to cesium-137. If the average flux of a reactor is known, the flux inferred from measurements of spent fuel could help determine whether that spent fuel was loaded as a blanket or close to the mid-plane of the reactor. The cesium ratio also provides information on reactor shutdowns during the irradiation of fuel, which could prove valuable for identifying the reactor in question through comparisons with satellite reactor heat monitoring data. We derive analytic expressions for these correlations and compare them to experimental data and to detailed reactor burn simulations. The enrichment of the original uranium fuel affects the correlations by up to 3 percent, but only at high flux.

  11. Reduction of cesium levels in the diet through management of food

    International Nuclear Information System (INIS)

    Several processes influence the radionuclide concentration of food products during processing: dilution, losses, concentration. Boiling of leaf vegetables yields a decontamination effect of up to 80% in the case of radioiodine. Peeling of potato tubers results in a reduction of the cesium concentration of 30%. The cesium and strontium concentration of flour is a factor of two lower as compared to the corresponding cereal grain due to the milling process. Significant discrimination occurs during the milk processing. The skimmed milk is significantly richer in cesium, iodine and especially in strontium than the cream. It follows that butter is depleted in its radionuclide contents as compared to other milk produce. Strontium is concentrated in the casein. Pressurized cooking in combination with salting or a treatment with acetic acid results in an Cs-activity loss of beef, veal and lamb meat of 50 to 90%. (Author) 3 figs., 7 tabs., 13 refs

  12. Continuous Separation of Cesium Based on NiHCF/PTCF Electrode by Electrochemically Switched Ion Exchange

    Institute of Scientific and Technical Information of China (English)

    孙斌; 郝晓刚; 王忠德; 张忠林; 刘世斌; 官国清

    2012-01-01

    Nickel hexacyanoferrate (NiHCF) film was synthesized on porous three-dimensional carbon felt (PTCF) substrate by repetitious batch chemical depositions, and the NiHCF/PTCF electrode was used as electrochemically switched ion exchange (ESIX) electrode in a packed bed for continuous separation for cesium ions. The morphologies of the prepared electrodes were characterized by scanning electron microscopy and the effects of solution concentration on the ion-exchange capacity of the electrodes were investigated by cyclic voltammetry technique. Cycling stability and long-term storage stability of NiHCF/PTCF electrodes were also studied. The NiHCF/PTCF electrodes with excellent ion-exchange ability were used to assemble a diaphragm-isolated ESIX reactor for cesium separation. Continuous separation of cesium and regeneration of NiHCF/PTCF electrode based on the diaphragm-isolated reactor were performed in a laboratory-scale two-electrode system.

  13. Small-Column Cesium Ion Exchange Elution Testing of Spherical Resorcinol-Formaldehyde

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Garrett N.; Russell, Renee L.; Peterson, Reid A.

    2011-10-21

    This report summarizes the work performed to evaluate multiple, cesium loading, and elution cycles for small columns containing SRF resin using a simple, high-level waste (HLW) simulant. Cesium ion exchange loading and elution curves were generated for a nominal 5 M Na, 2.4E-05 M Cs, 0.115 M Al loading solution traced with 134Cs followed by elution with variable HNO3 (0.02, 0.07, 0.15, 0.23, and 0.28 M) containing variable CsNO3 (5.0E-09, 5.0E-08, and 5.0E-07 M) and traced with 137Cs. The ion exchange system consisted of a pump, tubing, process solutions, and a single, small ({approx}15.7 mL) bed of SRF resin with a water-jacketed column for temperature-control. The columns were loaded with approximately 250 bed volumes (BVs) of feed solution at 45 C and at 1.5 to 12 BV per hour (0.15 to 1.2 cm/min). The columns were then eluted with 29+ BVs of HNO3 processed at 25 C and at 1.4 BV/h. The two independent tracers allowed analysis of the on-column cesium interaction between the loading and elution solutions. The objective of these tests was to improve the correlation between the spent resin cesium content and cesium leached out of the resin in subsequent loading cycles (cesium leakage) to help establish acid strength and purity requirements.

  14. Cesium removal from high-pH, high-salt wastwater using crystalline silicotitanate sorbent

    Energy Technology Data Exchange (ETDEWEB)

    Walker, J.F. Jr.; Taylor, P.A.; Lee, D.D.

    1997-11-01

    Treatment and disposal options for Department of Energy (DOE) underground storage tank waste at Hanford, Savannah River, and Oak Ridge National Laboratory (ORNL) are limited by high gamma radiation fields that are produced by high concentrations of cesium in the waste. Treatment methods are needed to remove the cesium from the liquid waste and thus concentrate the cesium into high-activity, remote-handled waste forms. The treated liquids could then be processed and disposed of by more cost-effective means with less radiation exposure to workers. A full-scale demonstration of one cesium removal technology is currently being conducted at ORNL. This demonstration utilizes a modular, mobile ion-exchange system and existing facilities for the off-gas system, secondary containment, and utilities. The ion-exchange material, crystalline silicotitanate (CST), was chosen on the basis of its effectiveness in laboratory tests. The CST, which was developed through a Cooperative Research and Development Agreement between DOE and private industry, has several advantages over current organic ion-exchange technologies. These advantages include (1) the ability to remove cesium in the presence of high concentrations of potassium, (2) a high affinity for cesium in both alkaline and acidic conditions, (3) physical stability over wide alkaline and acidic ranges, and (4) the elimination of large volumes of secondary waste required for regeneration of organic ion exchangers. Approximately 100,000 L of wastewater will be processed during the demonstration. The wastewater being processed has a high salt content, about 4 M NaNO{sub 3}, and a pH of 12 to 13. This paper discusses the results of the full-scale demonstration and compares these results with data from the laboratory tests.

  15. Separation of cesium from simulated active waste using zinc hexacyanoferrate supported composite

    International Nuclear Information System (INIS)

    Potassium zinc hexacyanoferrate (KZnHCF) was prepared and supported on polyacrylonitrile (PAN) binding polymer. This composite was characterized and used to study the elimination of cesium from acidic radioactive waste containing Sr(II), Eu(II), Am(II), Zr(IV), Hf(IV) and Nb(V) using batch and column techniques. The sorption capacity of this composite for cesium was found to be 1.14 meq/g for column technique. The effect of presence of NH4SCN, NaNo3 and other complexing agents in the aqueous solutions was studied

  16. A preliminary deposit model for lithium-cesium-tantalum (LCT) pegmatites

    Science.gov (United States)

    Bradley, Dwight; McCauley, Andrew

    2013-01-01

    This report is part of an effort by the U.S. Geological Survey to update existing mineral deposit models and to develop new ones. We emphasize practical aspects of pegmatite geology that might directly or indirectly help in exploration for lithium-cesium-tantalum (LCT) pegmatites, or for assessing regions for pegmatite-related mineral resource potential. These deposits are an important link in the world’s supply chain of rare and strategic elements, accounting for about one-third of world lithium production, most of the tantalum, and all of the cesium.

  17. Heat Transfer During Evaporation of Cesium From Graphite Surface in an Argon Environment

    Directory of Open Access Journals (Sweden)

    Bespala Evgeny

    2016-01-01

    Full Text Available The article focuses on discussion of problem of graphite radioactive waste formation and accumulation. It is shown that irradiated nuclear graphite being inalienable part of uranium-graphite reactor may contain fission and activation products. Much attention is given to the process of formation of radioactive cesium on the graphite element surface. It is described a process of plasma decontamination of irradiated graphite in inert argon atmosphere. Quasi-one mathematical model is offered, it describes heat transfer process in graphite-cesium-argon system. Article shows results of calculation of temperature field inside the unit cell. Authors determined the factors which influence on temperature change.

  18. Synthesis of novel calixcrown derivatives with selective complexation towards cesium ions

    Institute of Scientific and Technical Information of China (English)

    Lu Zhang; Juan Du; Li Hua Yuan; Dong Zhang; Gui Ping Dan; Yuan You Yang; Wen Feng

    2011-01-01

    A series of novel calix [4]arenecrown-6 derivatives with an alkenyl loop of various sizes 5-8 were synthesized via intramolecular ring closing olefin metathesis and characterized by 1H NMR, 13C NMR and ESI-HRMS. Their complexation property towards cesium ion was studied by 'H NMR technique. Two-phase extraction of alkali metal ions using UV-vis spectroscopy revealed remarkably different extractabilities. These results indicate that the complexation capacities towards cesium ions can be tuned and controlled through cooperative regulation of the strain of the loop and conformational change of calixcrown skelton.

  19. Measurement of Ionization Threshold of Ultracold Cesium Rydberg Atoms in Static Electric Field

    Institute of Scientific and Technical Information of China (English)

    FENG Zhi-Gang; ZHANG Lin-Jie; ZHAO Jian-Ming; LI Chang-Yong; LI An-Ling; JIA Suo-Tang

    2008-01-01

    We investigate the field ionization spectra of ultracold cesium Rydberg atoms in dc electric field. The ionization thresholds of different electric fields are measured and shift of the ionization threshold relative to field-free ionization threshold is accurately described by (6.06±0.14) F1/2, which is in good agreement with the classical saddle-point model for field ionization. We obtain the field-free ionization threshold of cesium (6P,3/2) as 19674.89士2.99cm-1 by fitting experimental data.

  20. A direct frequency comb for two-photon transition spectroscopy in a cesium vapor

    Institute of Scientific and Technical Information of China (English)

    Zhang Yi-Chi; Wu Ji-Zhou; Li Yu-Qing; Jin Li; Ma Jie; Wang Li-Rong; Zhao Yan-Ting; Xiao Lian-Tuan; Jia Suo-Tang

    2012-01-01

    A phase-stabilized femtosecond frequency comb is used to measure high-resolution spectra of two-photon transition 62S1/2-62P1/2,3/2-82S1/2 in a cesium vapor.The broadband laser output from a femtosecond frequency comb is split into counter-propagating parts,shaped in an original way,and focused into a room-temperature cesium vapor.We obtain high-resolution two-photon spectroscopy by scanning the repetition rate of femtosecond frequency comb,and through absolute frequency measurements.