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Sample records for cesium radioisotopes

  1. Fast concentration of dissolved forms of cesium radioisotopes from large seawater samples

    International Nuclear Information System (INIS)

    The method developed for cesium concentration from large freshwater samples was tested and adapted for analysis of cesium radionuclides in seawater. Concentration of dissolved forms of cesium in large seawater samples (about 100 L) was performed using composite absorbers AMP-PAN and KNiFC-PAN with ammonium molybdophosphate and potassium–nickel hexacyanoferrate(II) as active components, respectively, and polyacrylonitrile as a binding polymer. A specially designed chromatography column with bed volume (BV) 25 mL allowed fast flow rates of seawater (up to 1,200 BV h-1). The recovery yields were determined by ICP-MS analysis of stable cesium added to seawater sample. Both absorbers proved usability for cesium concentration from large seawater samples. KNiFC-PAN material was slightly more effective in cesium concentration from acidified seawater (recovery yield around 93 % for 700 BV h-1). This material showed similar efficiency in cesium concentration also from natural seawater. The activity concentrations of 137Cs determined in seawater from the central Pacific Ocean were 1.5 ± 0.1 and 1.4 ± 0.1 Bq m-3 for an offshore (January 2012) and a coastal (February 2012) locality, respectively, 134Cs activities were below detection limit (-3). (author)

  2. Cesium-137 radioisotope, a fallout component in the study of soil erosion and sedimentation

    International Nuclear Information System (INIS)

    A preliminary study on the possibility of using Cesium-137, a component of the fallout, to estimate soil erosion and sedimentation was carried out in a small watershed in Piracicaba, Sao Paulo. High resolution gamma-ray spectrometry (Germanium detector coupled to a multichannel analyzer) was used to detect Cs-137. The fallout standards of the profiles fallout and results of soil losses and gains for the transects are discussed based on these measurements. (author)

  3. 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.

  4. 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)

  5. 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)

  6. 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

  7. Application of Cesium isotopes in daily life

    International Nuclear Information System (INIS)

    In the world of science, the desire of the scientific community to discover new chemical elements is crucial for the development of new technologies in various fields of knowledge. And the main chemical element addressed by this article is Cesium, but specifically 133Cesium isotope and radioisotope 137Cesium, exemplifying their physical and chemical characteristics, and their applications. This article will also show how these isotopes have provided researchers a breakthrough in the field of radiological medicine and in time and frequency metrology. (author)

  8. 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)

  9. Radioisotope generator

    International Nuclear Information System (INIS)

    A radioisotope generator is described in which it is possible to interupt the elution process at any desired time, i.e. before the electron flacon is full. The interuption is performed in such a way that sterile air is simultaneously admitted into the generator, into both the column and the elution flacon. (Th.P.)

  10. Spatial variability and Cesium-137 inventories in native forest

    International Nuclear Information System (INIS)

    With the nuclear fission discovery and development of nuclear weapons in 1940s, artificial radioisotopes were introduced in the environment. This contamination is due to worldwide fallout by superficial nuclear tests realized from early 1950s to late 1970s by USA, former URSS, UK, France and China. One of theses radioisotopes that have been very studied is cesium-137. Cesium-137 has a half-life of 30.2 years and its biological behavior is similar to the potassium. The behavior in soil matrix, depth distribution, spatial variability and inventories values of cesium-137 has been determinate for several regions of the world. In Brazil, some research groups have worked on this subject, but there are few works published about theses properties of cesium-137. The aim of this paper was study the depth distribution, spatial variability, and inventory of cesium-137 in native forest. Two native forests (Mata 1 and Mata UEL) were sampling in region of Londrina, PR. The results shows that there is a spatial variability of 40% for Mata 1 and 42% for Mata UEL. The depth distribution of cesium-137 for two forests presented a exponential form, characteristic to undisturbed soil. Cesium-137 inventory determinate for Mata 1 was 358 Bq m-2 and for Mata UEL was 320 Bq m-2. (author)

  11. 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

  12. 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...

  13. 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.

  14. 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.

  15. 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...

  16. Transport of radioisotopes

    International Nuclear Information System (INIS)

    Presently the amount of radioisotopes increased very much and the application spread to wide fields in Japan. Since facilities using radioisotopes are distributed to every place in the country, every transport means such as airplanes, automobiles, railways, ships and mail are employed. The problems in the transport of radioisotopes include too much difference in the recognition of criticality among the persons concerning the transportation and treatment, knowledges of shielding and energy difference in the types of radiation and handling of sealed and unsealed sources and the casks for transport. IAEA established the latest regulation on the package of radioisotopes in 1973, and in Japan, the related regulations will be revised according to the IAEA's regulation in near future. The present status in the inspection at the time of shipment, supervision, and the measures to the accidents are described for the transport means of airplanes, ships and automobiles. Finally, concerning the insurance for cargo, the objects of the insurance for radioisotopes include either the radioisotopes contained in casks for transportation or radioisotopes only. Generally, radioisotopes are accepted in all-risk condition including casks and limited to the useful radioisotopes for peaceful use. (Wakatsuki, Y

  17. Application of Cesium isotopes in daily life; Aplicacoes dos isotopos do Cesio no cotidiano

    Energy Technology Data Exchange (ETDEWEB)

    Jordao, B.O.; Quaresma, D.S.; Carvalho, R.J., E-mail: bjordan@on.br, E-mail: dansq@on.br, E-mail: carvalho@on.br [Observatorio Nacional (ON/LPTF), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Tempo e Frequencia; Peixoto, J.G.P., E-mail: guilherm@ird.gov.br [Instituto de Radioprotecao e Dosimetria, (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. de Metrologia das Radiacoes Ionizantes

    2014-07-01

    In the world of science, the desire of the scientific community to discover new chemical elements is crucial for the development of new technologies in various fields of knowledge. And the main chemical element addressed by this article is Cesium, but specifically {sup 133}Cesium isotope and radioisotope {sup 137}Cesium, exemplifying their physical and chemical characteristics, and their applications. This article will also show how these isotopes have provided researchers a breakthrough in the field of radiological medicine and in time and frequency metrology. (author)

  18. Cesium chemistry in irradiated fuel; cesium uranates

    International Nuclear Information System (INIS)

    The physico-chemical behaviour of fission products in nuclear fuel during and after irradiation has been studied extensively during the past decades. In spite of the large amount of chemical, crystallographic and thermodynamic data available, the knowledge on the very complicated UO2-fission product system is still far from complete. The paper discusses the multi variant character of uranium in cesium uranates, which has been assessed by a systematic X-ray Photoelectron Spectroscopy (XPS) study of a series of cesium uranates

  19. Radioisotope applications in industry

    International Nuclear Information System (INIS)

    After a short mention of the economic importance of the industrial application of radioisotopes the most necessary fundamental principles of nuclear physics are given. The nature and the laws of the radioactive decay are illustrated, the interaction of radiation with matter and the absorption laws are described and the production of radioisotopes are mentioned. Subsequent the various detectors for measuring radioactivity are described with a short reference to the problems of the electronic measuring devices. At the end the various measuring techniques and the methods of application for radioisotopes in industry are illustrated. (author)

  20. 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)

  1. 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

  2. A Radioisotope Inventory Program

    International Nuclear Information System (INIS)

    The Radioisotope Inventory Program maintains an accurate and up-to-date inventory of all radioisotopes used on campus. An instruction manual provides easy to use directions for using the program. The program is implemented on a Hewlett-Packard HP-85 microcomputer and can be used on other systems. The commands allow updating and changing licensee information easily and quickly. Data Security is maintained by placing the data on a removable tape cartridge and locking the cartridge

  3. Modular Stirling Radioisotope Generator

    Science.gov (United States)

    Schmitz, Paul C.; Mason, Lee S.; Schifer, Nicholas A.

    2016-01-01

    High-efficiency radioisotope power generators will play an important role in future NASA space exploration missions. Stirling Radioisotope Generators (SRGs) have been identified as a candidate generator technology capable of providing mission designers with an efficient, high-specific-power electrical generator. SRGs high conversion efficiency has the potential to extend the limited Pu-238 supply when compared with current Radioisotope Thermoelectric Generators (RTGs). Due to budgetary constraints, the Advanced Stirling Radioisotope Generator (ASRG) was canceled in the fall of 2013. Over the past year a joint study by NASA and the Department of Energy (DOE) called the Nuclear Power Assessment Study (NPAS) recommended that Stirling technologies continue to be explored. During the mission studies of the NPAS, spare SRGs were sometimes required to meet mission power system reliability requirements. This led to an additional mass penalty and increased isotope consumption levied on certain SRG-based missions. In an attempt to remove the spare power system, a new generator architecture is considered, which could increase the reliability of a Stirling generator and provide a more fault-tolerant power system. This new generator called the Modular Stirling Radioisotope Generator (MSRG) employs multiple parallel Stirling convertor/controller strings, all of which share the heat from the General Purpose Heat Source (GPHS) modules. For this design, generators utilizing one to eight GPHS modules were analyzed, which provided about 50 to 450 W of direct current (DC) to the spacecraft, respectively. Four Stirling convertors are arranged around each GPHS module resulting in from 4 to 32 Stirling/controller strings. The convertors are balanced either individually or in pairs, and are radiatively coupled to the GPHS modules. Heat is rejected through the housing/radiator, which is similar in construction to the ASRG. Mass and power analysis for these systems indicate that specific

  4. Industry benefits from radioisotopes

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency since its inception has always sought to promote the industrial use of radioisotopes. Among other ways, it has arranged scientific conferences on various aspects of the question, and has selected and published general information. Industry's attitude to any innovation, however, is the same the world over - viz. does it pay? The Agency, therefore, decided to collect information on the economic benefits derived from the use of radioisotopes in industry, described in terms of 'savings', It arranged for an international survey of these benefits, and at the same time for the collection of information on how radioisotopes are being utilized today. In April 1962 the Agency invited selected Member States to participate in the survey, and in response national governments collected detailed information from industrial organizations in their countries in the fields of prospecting, mining and manufacturing. The radioisotope techniques were grouped under the heads of radioisotope gauging, industrial radiography, ionization applications, tracing, massive irradiation and miscellaneous applications. The national reports from the participating countries recently reached the Agency, which is preparing a comprehensive report on radioisotope use and economics. In order to assess the contents of the various reports and to establish the best means of interpreting and presenting the material, the Agency convened a Study Group in Vienna from 16 to 20 March 1964. About 60 participants from Member States and international organizations discussed the reports, the latest developments in isotope utilization, and how the use of isotopes in industry could be further encouraged. The survey was prepared with care, as there have been few precedents to guide such an investigation on such a scale. Although its main purpose is to make an economic assessment, it has necessarily had to start with the consideration of techniques, and information was collected both

  5. 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

  6. Which way radioisotopes?

    Energy Technology Data Exchange (ETDEWEB)

    Sion, N.

    2011-03-15

    The cancellation of the MAPLES program and the impending retirement of the NRU reactor in 2016 (all utilizing Highly Enriched Uranium HEU for their targets) plus the rigours of non proliferation treaties, has created an increasingly short supply of radioisotopes. Alternate pathways must be found, even created, to maintain the supply of radioisotopes i.e. Mo-99 (decaying into Tc-99m) as well as to provide the several other types of isotopes used in nuclear medicine in order to maintain Canada's leadership in science, innovation and public health. Medical isotopes help locate cancers with precision, therapeutically treat cancers, and provide physicians the diagnostic tools to save lives. (author)

  7. Analysis of radioactive cesium

    International Nuclear Information System (INIS)

    The procedure of analysis of cesium-137 in environmental samples is described. The standard measurement of cesium-137 is made by using a standard solution and a low background G-M counter system. Precipitation and dust are collected on a stainless steel pan. The collected samples are treated by evaporation and extraction or ion exchange and adsorption method. The sample is then quantitatively analyzed. The measurement of cesium-137 is made according to the standard of measurement. Samples collected from inland water and sea water are also treated by evaporation or ion exchange method. The measurements of cesium-137 are also made. This manual describes how to collect soil samples. The collected soil is dried and treated to make samples for activity measurement. Activity measurement is made according to the standard of measurement, then the data are analyzed. Samples are also collected from sediment of sea bottom or river bottom, agricultural products, milk, marine organisms, and daily foods. This manual describes on the methods to collect samples and the treatment to make samples for measurement. (Kato, T.)

  8. Radioisotopes in education

    International Nuclear Information System (INIS)

    The use of radioisotopes and nuclear techniques can in many cases greatly contribute to the value of teaching. With these techniques it is often possible to introduce demonstrations or experiments which explain phenomena otherwise difficult to understand. The choice of the program must be adapted to the teaching level. This requires previous training of the teachers and the provision of basic equipment. (author)

  9. 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.

  10. 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

  11. Vitrification of spent organic ion exchange resins- 137Cesium volatility during oxidation

    International Nuclear Information System (INIS)

    Organic ion exchange (IX) resins are used to purify coolant water in nuclear power plants. The spent IX resins contain 137Cesium as major long-lived radioisotope. Their vitrification requires complete combustion of organic matter. 137Cesium volatility during their oxidation is most important factor for selection of oxidation procedure. Based on TGA studies, copper and vanadate catalysts were selected respectively for cationic and anionic IX resins to oxidise them at 500-700 degC. Experiments were conducted with 137Cesium and catalyst loaded cationic and anionic resins. About 56 to 60% 137Cesium was released from cationic resins in 3 hours. 137Cesium release from cationic resins could be brought down to 19 to 22% by addition of glass formers. The 137Cesium releases from anionic resins were nearly same for 2 hours heating. In absence of glass formers, the catalyst on anionic resins formed molten mass, which was difficult to remove. Experiment with one litre of 137Cesiuin loaded mixed cationic and anionic resins released 16.8% 137Cesium to off gases and formed a slag having specific gravity of 1.73 due to difficulty in oxidising last traces of carbon. The volume reduction factor achieved was 18.2 as against 68 expected for complete oxidation of IX resins. The higher volume reduction factor can be achieved by using improved oxidation procedure in scaling up studies. (author)

  12. 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

  13. Application of radioisotopes in entomology

    International Nuclear Information System (INIS)

    Radioisotope techniques are effective in entomology and studies on insects physiology. The study presents the use of radioisotopes in pest control programs: Methods of insects irradiation and the concept of biological half-life of the radioisotopes in comparison with physical half-life are explained. Main radioisotopes used in entomology are:3H, 14Ca, 32P, 35S, 38Cl. Other radioisotopes contributing to studies on insects are: 198Au, 134Cs, 131I, 86Rb, 65Zn, 59Fe, 45Ca, 24Na, 22Na. Radiation doses specific to each radioisotopes are given in tables. As an example of the application of radioisotopes in pest control: the determination of insects population density by means of releasing irradiated male insects than chasing them; studying of reproduction activity of Agrotis ipsilon; studying of egg laying of Heliocoverpa armigera moth. 15 refs. 2 figs. 2 tabs

  14. Radioisotopes and radiopharmaceuticals catalogue

    International Nuclear Information System (INIS)

    The Chilean Nuclear Energy Commission (CCHEN) presents its radioisotopes and radiopharmaceuticals 2002 catalogue. In it we found physical characteristics of 9 different reactor produced radioisotopes ( Tc-99m, I-131, Sm-153, Ir-192, P-32, Na-24, K-42, Cu-64, Rb-86 ), 7 radiopharmaceuticals ( MDP, DTPA, DMSA, Disida, Phitate, S-Coloid, Red Blood Cells In-Vivo, Red Blood Cells In-Vitro) and 4 labelled compounds ( DMSA-Tc99m, DTPA-Tc99m, MIBG-I131, EDTMP-Sm153 ). In the near future the number of items will be increased with new reactor and cyclotron products. Our production system will be certified by ISO 9000 on March 2003. CCHEN is interested in being a national and an international supplier of these products (RS)

  15. Radioisotopes in medicine

    International Nuclear Information System (INIS)

    Radioisotopes are extensively used in nuclear medicine to allow physicians to explore bodily structures. The thyroid, bones, heart, liver and many other organs can be easily imaged and disorder in their functions revealed. Technetium-99, a radioisotope is a decay product of Molybdenum-99, a radionuclide with half life of sixty-six hours is discussed. It is widely used in nuclear medical procedure. In this application, the radio nuclide is chemically attached to a drug chosen for its tendency to collect in specific organ of the body and the so is then injected into the patient's body. After a short time, half life of only six hours, an image is collected with a radio sensitive detector for analysis. Technetium-99 decays by isomeric process which emits gamma rays and low energy beta particles. (author)

  16. 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

  17. Radio-isotope converter

    International Nuclear Information System (INIS)

    Due to the surface power density required for thermoelectric and thermionic converters, available radioactive sources are surveyed and listed. Curves of specific minimum diameter versus thermal flux density are given. 210Po and 242Cm appear to be suitable for direct thermionic when alpha emitters such as 238Pu and 244Cm are still suitable for thermoelectric conversion. This mode will also work with beta emitters 170Tm, 90Sr, 144Ce and 137Cs. Some thermoelectric radioisotope heated converters are suggested. (authors)

  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. Radioisotope programme in Iran

    International Nuclear Information System (INIS)

    The Nuclear Research Centre of the Atomic Energy Organization of Iran has taken up a program for the production of short-lived radioisotopes. The initial purpose of this program was to give service to isotope users, mainly researchers, who were importing radioisotopes. With the commissioning of the reactor and installation of handling facilities at the temporary isotope laboratories at NRC the scope of the production program elaborated. Meanwhile the application of radiopharmaceuticals in medicine was actively encouraged. The production of radioisotopes in medicine is one of the prime objectives. The development of Tc-99m technology in NRC of AEOI will not only meet the demands of existing nuclear medicine centres, but also help the country to develop know-how in this important area. The output of this project will be the production and supply of Tc-99m generator, which is a primary objective with the technical assistance of IAEA. At the present moment the Tc-99m is processing using Mo-99 produced in the NRC reactor by irradiation Mo03. In view of the easier availability of fission product Mo-99 from several suppliers, now the NRC is seriously considering the preparation of Tc-99m generators using imported fission Mo-99. We are also working on the production of high specific activity Cr-51, P-32, S-33 and Au-198 colloid and some other short-lived radioisotopes in milicurie level. Iodine-131 is processed using the wet distillation method with good recovery. The iodine-131 is tested for radiochemical purity tellurium content and radionuclide purity and is found to be satisfactory. With these studies the processing and quality control of I-131 can be considered complete and batches of one curie activity can be planned. Specifications have been standardized for I-131 labelled formulations radiopharmaceuticals. (Author)

  20. 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

  1. 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.

  2. Advances in Radioisotope Handling Facilities and Automation of Radioisotope Production

    International Nuclear Information System (INIS)

    Founded in 1959, the Institute of Isotopes of the Hungarian Academy of Sciences began to produce radioactive isotopes in 1964. Since then, it has become a major Hungarian centre of research, development and production relating to the application of radioisotopes. Since 1993 a part of the former Institute has been operating as the Institute of Isotopes Co., Ltd. The main advances in radioisotope handling facilities and automation of radioisotope production are presented here. (author)

  3. 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

  4. 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

  5. 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)

  6. Radioisotope powered light sources

    Energy Technology Data Exchange (ETDEWEB)

    Case, F. N.; Remini, W. C.

    1980-01-01

    Radioisotopes have been used for a number of years to excite phosphors to produce visible light. The advent of the nuclear age, however, made possible the preparation of radionuclides in larger quantities at relatively low prices, and with radiation properties that greatly expanded the potential applications for such lights. Current energy conservation needs and inflation leading to even higher costs for maintenance and capital equipment has provided the incentive for development of illuminators for air field markers using both byproduct krypton-85 and processed tritium. Background and current status of these developments are discussed.

  7. Radioisotope powered light sources

    International Nuclear Information System (INIS)

    Radioisotopes have been used for a number of years to excite phosphors to produce visible light. The advent of the nuclear age, however, made possible the preparation of radionuclides in larger quantities at relatively low prices, and with radiation properties that greatly expanded the potential applications for such lights. Current energy conservation needs and inflation leading to even higher costs for maintenance and capital equipment has provided the incentive for development of illuminators for air field markers using both byproduct krypton-85 and processed tritium. Background and current status of these developments are discussed

  8. 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

  9. 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

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

    International Nuclear Information System (INIS)

    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)

  11. 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)

  12. Radioisotopes and radiation technology

    International Nuclear Information System (INIS)

    The field of radioisotopes and radiation processing has grown enormously all over the world with India being no exception. The chemistry and radiochemistry related inputs to the overall technology development and achievements have been, and will continue to be, of considerable value and importance in this multi-disciplinary and multi-specialty field. Harnessing further benefits as well as sustaining proven applications should be the goal in planning for the future. An objective analysis of the socio-economic impact and benefits from this field to the society at large will undoubtedly justify assigning continued high priority, and providing adequate resources and support, to relevant new projects and programmes on the anvil in the area of radioisotopes and radiation technology. It is necessary to nurture and strengthen inter-disciplinary and multi-specialty collaborations and cooperation - at both national and international level as a rule (not as exception) - for greater efficiency, cost-effectiveness and success of ongoing endeavors and future developments in this important field

  13. 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.

  14. Reactor-produced therapeutic radioisotopes

    International Nuclear Information System (INIS)

    The significant worldwide increase in therapeutic radioisotope applications in nuclear medicine, oncology and interventional cardiology requires the dependable production of sufficient levels of radioisotopes for these applications (Reba, 2000; J. Nucl. Med., 1998; Nuclear News, 1999; Adelstein and Manning, 1994). The issues associated with both accelerator- and reactor-production of therapeutic radioisotopes is important. Clinical applications of therapeutic radioisotopes include the use of both sealed sources and unsealed radiopharmaceutical sources. Targeted radiopharmaceutical agents include those for cancer therapy and palliation of bone pain from metastatic disease, ablation of bone marrow prior to stem cell transplantation, treatment modalities for mono and oligo- and polyarthritis, for cancer therapy (including brachytherapy) and for the inhibition of the hyperplastic response following coronary angioplasty and other interventional procedures (For example, see Volkert and Hoffman, 1999). Sealed sources involve the use of radiolabeled devices for cancer therapy (brachytherapy) and also for the inhibition of the hyperplasia which is often encountered after angioplasty, especially with the exponential increase in the use of coronary stents and stents for the peripheral vasculature and other anatomical applications. Since neutron-rich radioisotopes often decay by beta decay or decay to beta-emitting daughter radioisotopes which serve as the basis for radionuclide generator systems, reactors are expected to play an increasingly important role for the production of a large variety of therapeutic radioisotopes required for these and other developing therapeutic applications. Because of the importance of the availability of reactor-produced radioisotopes for these applications, an understanding of the contribution of neutron spectra for radioisotope production and determination of those cross sections which have not yet been established is important. This

  15. 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.

  16. 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)

  17. 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)

  18. 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

  19. Cardiovascular: radioisotopic angiocardiography

    International Nuclear Information System (INIS)

    Radioisotopic angiocardiography, performed after the intravenous injection of 99/sup m/Tc-labeled pertechnetate or albumin, is a simple, rapid, and safe procedure which permits identification and physiologic assessment of a wide variety of congenital and acquired cardiovascular lesions in infants and children. These include atrial and ventricular septal defect, tetralogy of Fallot, pulmonic stenosis, aortopulmonary window, transposition of the great vessels, valvular stenosis and/or insufficiency, myocardial lesions, and lesions of the great vessels. The simplicity of the procedure lends itself to repeated measurements to assess the effects of therapy or to follow the course of the disease. A wide spectrum of congenital and acquired cardiovascular diseases have been studied which have particular application to the pediatric age group. (auth)

  20. The search for new radioisotopes

    International Nuclear Information System (INIS)

    Phosphorus-30 was the first artificial radioisotope, it was produced by F. and I. Joliot-Curie in 1934, since then 2460 new nuclei have been discovered. This document reviews the radioisotopes known and the methods used to separate them. The authors describe the discovery of new radioisotopes such as Nickel-78 produced in the fission of high energy uranium ions impinging on a lead target (IPN-GSI collaboration) and the discovery of Nickel-48 by a team CENBG-Ganil. All this experience is useful for the processing of nuclear wastes by using transmutation. (A.C.)

  1. 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...

  2. Industrial applications of radioisotope tracers

    International Nuclear Information System (INIS)

    Radioisotope tracing techniques are powerful tools for analysing the behaviour of large systems and investigating industrially or economically important processes. The results of radioisotope experiments can yield important information, for example, on parameters such as flow rates, mixing phenomena, flow abnormalities and leaks. Some examples of current AAEC research are described, covering studies on hearth drainage in blast furnaces, flow behaviour in waste-water treatment ponds, and sediment transport in marine environments

  3. 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

  4. 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.

  5. 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

  6. Cesium Concentration in MCU Solvent

    International Nuclear Information System (INIS)

    During Modular Caustic-Side Solvent Extraction (CSSX) Unit (MCU) operations, Cs-137 concentrations in product streams will vary depending on the location in the process and on the recent process conditions. Calculations of cesium concentrations under a variety of operating conditions reveal the following: (1) Under nominal operations with salt solution feed containing 1.1 Ci Cs-137 per gallon, the maximum Cs-137 concentration in the process will occur in the strip effluent (SE) and equal 15-16.5 Ci/gal. (2) Under these conditions, the majority of the solvent will contain 0.005 to 0.01 Ci/gal, with a limited portion of the solvent in the contactor stages containing ∼4 Ci/gal. (3) When operating conditions yield product near 0.1 Ci Cs-137/gal in the decontaminated salt solution (DSS), the SE cesium concentration will be the same or lower than in nominal operations, but majority of the stripped solvent will increase to ∼2-3 Ci/gal. (4) Deviations in strip and waste stream flow rates cause the largest variations in cesium content: (a) If strip flow rates deviate by -30% of nominal, the SE will contain ∼23 Ci/gal, although the cesium content of the solvent will increase to only 0.03 Ci/gal; (b) If strip flow rate deviates by -77% (i.e., 23% of nominal), the SE will contain 54 Ci/gal and solvent will contain 1.65 Ci/gal. At this point, the product DSS will just reach the limit of 0.1 Ci/gal, causing the DSS gamma monitors to alarm; and (c) Moderate (+10 to +30%) deviations in waste flow rate cause approximately proportional increases in the SE and solvent cesium concentrations. Recovery from a process failure due to poor cesium stripping can achieve any low cesium concentration required. Passing the solvent back through the contactors while recycling DSS product will produce a ∼70% reduction during one pass through the contactors (assuming the stripping D value is no worse than 0.36). If the solvent is returned to the solvent hold tank (containing additional

  7. Applications of radioisotopes in industry

    International Nuclear Information System (INIS)

    In recent years, radioisotope techniques have found ever-increasing application to the investigation of industrial process plant. The chemical industry in particular was quick to appreciate this potential and in ICI the substantial scope for radioisotope applications led some 20 years ago to the establishment of a group specializing in this field. This group, Physics and Radioisotope Services has flourished and now carries out work for all parts of ICI as well as for external companies. An important factor in the growth of this organization has been the realization on the part of production management of the enormous savings which can result from the successful applications of radioisotope techniques. Measurements can, in general, be made while the plant is on-line disrupting the operating conditions and thus saving down-time. In addition, the rapidity and convenience with which the measurements can be made (utilizing as they do equipment external to the process) leads to a direct reduction in service costs. In parallel with the growth of radioisotope techniques in plant investigation, there has been a continuous development of instruments which utilize the properties of radioactive materials in process measurement and control. These so-called ''nucleonic'' instruments are now used widely throughout industry. Typically, ICI manufactures and installs over 300 such instruments every year on its own plants along-through the number of gauges installed throughout industry is much greater than this. The range of radioisotope techniques and instruments is extremely wide and this topic has itself been the subject of several symposia (1), (2), (3), (4), (5). For this reason, it is impractical to attempt a full coverage here. We have chosen rather to restrict the paper to those techniques and instruments which have been found to be used most extensively. This selection has been made by analyzing the work spectrum of Physics and Radioisotope Services which carries out in

  8. Comparative study of cesium adsorption on dioctahedral and trioctahedral smectites

    International Nuclear Information System (INIS)

    Bentonites which are characterized by good rheological, mineralogical and chemical stability is considered used as sealing barriers in multibarrier Slovak system of deep geological repository for high-level radioactive waste and spent nuclear fuel. In Slovak Republic there are several significant deposits of bentonite, which are characterized by appropriate adsorption properties and meet the geotechnical requirements for this type of barriers. Study of adsorption properties of bentonites and other smectites is an essential step for developing the migration model long-lived corrosion and activation products, and fission products of uranium. Nuclear wastes contain the most important nuclear fission products, radioisotopes 134Cs and 137Cs. The present paper investigates and compares the cesium adsorption properties of Slovak and North America bentonites composed mainly of dioctahedral smectite montmorillonite (J, L, SAz-1 and STx-1) and trioctahedral smectites saponite (SapCa-2) and hectorite (SHCa-1). (author)

  9. 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

  10. 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

  11. Cesium in the nutrient cycle

    International Nuclear Information System (INIS)

    Most radioactive cesium in forests is deposited in soil, from which it passes into berries and mushrooms, and further to game. The cesium contents of Finnish berries and mushrooms vary depending on the intensity of Chernobyl fallout. Northern Haeme, Pirkanmaa and parts of central Finland received the most fallout. Weather conditions and the environmental factors, and other circumstances during the growth period, also affect the contents. However, consumption of wild berries, mushrooms and game need not be restricted because of radioactivity anywhere in Finland

  12. Cesium contamination of heather honey

    International Nuclear Information System (INIS)

    In heather honey from Lueneburger Heide, FRG, relatively high values of cesium activity were found (up to about 650 Bq/kg). Activity values for heather honey, Calluna vulgaris plants and soil were measured. It is assumed that the origin of this activity is the direct Chernobyl fallout. There may also be a high transfer of cesium from the soil to the Calluna vulgaris plant, but in order to determine the transfer factor, fresh plants are needed, which have grown later than in spring 1986. (author) 21 refs.; 2 figs.; 2 tabs

  13. Radioisotope methods in environmental hydrogeology

    International Nuclear Information System (INIS)

    This book deals with the regularities of distribution of two radioisotopes, tritium and radiocarbon, in the ground water system as well as with the applications of their indicatory feature to solve problems of environmental hydrogeology. The concept and objectives of environmental hydrogeology, methodology of radioisotopic hydrosphere studies and evolution of hydrogeological processes by radioisotopic methods have been discussed. The experience gained from applying the isotope methods for environmental hydrogeology purposes in the Baltic Artesian Basin covering all the three Baltic states - Lithuania, Latvia and Estonia, as well as the Kaliningrad Region of Russia is generalized. This experience could be useful for specialists of other countries as well, especially those studying artesian basins of a platform type in the areas of former continental glaciers. 185 refs., 91 figs., 34 tabs

  14. 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

  15. 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

  16. Cesium in the Savannah River Site environment

    International Nuclear Information System (INIS)

    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 137Cs 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 137Cs 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 137Cs releases have resulted in a negligible risk to the environment and the population it supports

  17. 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.

  18. 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.

  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. Production and Development of Radioisotopes in HANARO

    International Nuclear Information System (INIS)

    The goal of this paper is to review the current activities at HANARO for the radioisotope production and related research activities in Korea, Also, the future directions in radioisotope production and its applications are described. (author)

  1. 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)

  2. Re-suspension of Cesium-134/137 into the Canadian Environment and the Contribution Stemming from the Fukushima-Daiichi Nuclear Incident

    Science.gov (United States)

    Mercier, Jean-Francois; Zhang, Weihua; Loignon-Houle, Francis; Cooke, Michael W.; Ungar, Kurt R.; Pellerin, Eric R.

    2013-04-01

    Cesium-137 (t1/2 = 30 yr) and cesium-134 (t1/2 = 2yr) constitute major fission by-products observed as the result of a nuclear incident. Such radioisotopes become integrated into the soil and biomass, and can therefore undergo re-suspension into the environment via activities such as forest fires. The Canadian Radiological Monitoring Network (CRMN), which consists of 26 environmental monitoring stations spread across the country, commonly observes cesium-137 in air filters due to re-suspension of material originating from long-past weapons testing. Cesium-134 is not observed owing to its relatively short half-life. The Fukushima-Daiichi nuclear power plant incident of March 2011 caused a major release of radioactive materials into the environment. In Canada, small quantities of both cesium-137 and cesium-134 fallout were detected with great frequency in the weeks which followed, falling off rapidly beginning in July 2011. Since September 2011, the CRMN has detected both cesium-137 and cesium-134 from air filters collected at Yellowknife, Resolute, and Quebec City locations. Using the known initial cesium-134/cesium-137 ratio stemming from this incident, along with a statistical assessment of the normality of the data distribution, we herein present evidence that strongly suggests that these activity spikes are due to re-suspended hot particles originating from the Fukushima-Daiichi nuclear power plant incident. Moreover, we have evidence to suggest that this re-suspension is localized in nature. This study provided empirical insight into the transport and uptake of radionuclides over vast distances, and it demonstrates that the CRMN was able to detect evidence of a re-suspension of Fukushima-Daiichi related isotopes.

  3. Immobilization of aqueous radioactive cesium wastes by conversion to aluminosilicate minerals

    International Nuclear Information System (INIS)

    Radioactive cesium (primarily 137Cs) is a major toxic constituent of liquid wastes from nuclear fuel processing plants. Because of the long half-life, highly penetrating radiation, and mobility of 137Cs, it is necessary to convert wastes containing this radioisotope into a solid form which will prevent movement to the biosphere during long-term storage. A method for converting cesium wastes to solid, highly insoluble, thermally stable aluminosilicate minerals is described. Aluminum silicate clays (bentonite, kaolin, or pyrophyllite) or hydrous aluminosilicate gels are reacted with basic waste solutions to form pollucite, cesium zeolite (Cs-D), Cs-F, cancrinite, or nepheline. Cesium is trapped in the aluminosilicate crystal lattice of the mineral and is permanently immobilized. The identity of the mineral product is dependent on the waste composition and the SiO2/Al2O3 ratio of the clay or gel. The stoichiometry and kinetics of mineral formation reactions are described. The products are evaluated with respect to leachability, thermal stability, and crystal morphology. (U.S.)

  4. Radioisotope methodology course radioprotection aspects

    International Nuclear Information System (INIS)

    The advancement knowledge in molecular and cell biology, biochemistry, medicine and pharmacology, which has taken place during the last 50 years, after World War II finalization, is really outstanding. It can be safely said that this fact is principally due to the application of radioisotope techniques. The research on metabolisms, biodistribution of pharmaceuticals, pharmacodynamics, etc., is mostly carried out by means of techniques employing radioactive materials. Radioisotopes and radiation are frequently used in medicine both as diagnostic and therapeutic tools. The radioimmunoanalysis is today a routine method in endocrinology and in general clinical medicine. The receptor determination and characterization is a steadily growing methodology used in clinical biochemistry, pharmacology and medicine. The use of radiopharmaceuticals and radiation of different origins, for therapeutic purposes, should not be overlooked. For these reasons, the importance to teach radioisotope methodology is steadily growing. This is principally the case for specialization at the post-graduate level but at the pre graduate curriculum it is worthwhile to give some elementary theoretical and practical notions on this subject. These observations are justified by a more than 30 years teaching experience at both levels at the School of Pharmacy and Biochemistry of the University of Buenos Aires, Argentina. In 1960 we began to teach Physics III, an obligatory pregraduate course for biochemistry students, in which some elementary notions of radioactivity and measurement techniques were given. Successive modifications of the biochemistry pregraduate curriculum incorporated radiochemistry as an elective subject and since 1978, radioisotope methodology, as obligatory subject for biochemistry students. This subject is given at the radioisotope laboratory during the first semester of each year and its objective is to provide theoretical and practical knowledge to the biochemistry students, even

  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. Cesium isotopes distribution in a soil-ground profile of aeration zone at meliorative systems

    International Nuclear Information System (INIS)

    Cesium isotopes redistribution in soil layer in time (from august 1986) at 7 experimental sections of meliorative systems are studied. Sections are at different outlying from industrial site and in different directions. It is shown, that radioisotopes distribution on surface is non uniform in quantity as well as in composition. Soil surface is contaminated more in several orders than ground layer even at a depth of 5-10 cm. It is ascertained, that flooding causes the radionuclide introduction into the ground waters level in large quantities. 7 refs.; 1 figs.; 2 tabs

  7. 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)

  8. 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

  9. 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.)

  10. Automation Systems for Radioisotope Laboratories

    International Nuclear Information System (INIS)

    For more than 50 years the company Hans Waelischmiller GmbH (HWM) has worked in the field of nuclear technology worldwide and designed and manufactured equipment for nuclear installations as well as complete turnkey projects. This report deals with the activity of HWM in the field of production of radioisotopes and radiopharmaceuticals as well as in the handling of radioactive materials in nuclear medicine departments in hospitals. (author)

  11. 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

  12. Improvement of radioisotope production technology

    International Nuclear Information System (INIS)

    The widespreading and deepgoing applications of radioisotopes results the increasing demands on both quality and quantity. This in turn stimulating the production technology to be improved unceasingly to meet the different requirements on availability, variety, facility, purity, specific activity and specificity. The major approaches of achieving these improvements including: optimizing mode of production; enhancing irradiation conditions; amelioration target arrangement; adapting nuclear process and inventing chemical processing. (author)

  13. Radioisotopes for therapy: an overview

    International Nuclear Information System (INIS)

    Radionuclides made great impact in the history of nuclear sciences both at the end of 19th century with the discoveries of Becquerel and madame Curie and later in 1934, when Frederic Joliet and Irene Curie demonstrated the production of the first artificial radioisotopes, 30P, by bombardment of 27Al by alpha particles. The subsequent invention of cyclotron and setting up of nuclear reactor opened the floodgate for production of artificial radionuclides. Currently, majority of radionuclides are made artificially by transforming a stable nuclide into an unstable state and thus far over 2500 radionuclides have been produced artificially. Use of radionuclides in various fields immediately followed their production and last century has witnessed tremendous growth in the applications of radiation and radioisotopes, in diverse fields such as medicine, industry, agriculture, food preservation, water resource management, environmental studies, etc. While radiation and radioisotopes are used both for diagnosis as well as for therapy in the field of medicine, therapeutic applications are among the earliest, which began as an empirical science in the beginning and developed into a well structured modality with time. (author)

  14. 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)

  15. 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

  16. 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)

  17. Medical radioisotopes for the next century

    International Nuclear Information System (INIS)

    Radioisotopes are widely used in medicine (Nuclear Medicine) for diagnosis, palliation and therapy of heart disease, cancer, muscoskeletal and neurological conditions. The radioisotopes used are both reactor and cyclotron produced. The utilisation is currently growing and is expected to continue to grow over the next 10-20 years. The combination of radioisotope and delivery vehicle can be designed to meet the intended end use. This paper will deal with the main approaches to the use of radioisotopes for Nuclear medicine ad future prospects for the area

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

    International Nuclear Information System (INIS)

    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

  19. 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.

  20. Radio-isotopic myocardial study

    International Nuclear Information System (INIS)

    The non invasive study of the myocardium with radio-isotopes is effected either with radio-elements labeling on recently infarcted myocardium, such as PYP Tc 99m, or after I.V. injection of Tl 201 extracted by normal myocardium or after I.V. injection of radio-element which study the myocardial metabolism. The fixation of PYP Tc 99m, bordering that of calcium, appears 24 hours after the onset of the myocardial infarction; then it reduces and disappears a week later; its persistency gives evidence of an evolution to ventricular anevrism. The relatively low sensitivity and specificity of this test should induce to reserve if for precise cases. 201 Tl realizes a map of the myocardial flow because this radio-isotope reflects with damping the variations of coronary flow. The scintigraphy is made either after stress test or after I.V. injection of dipyridamole, and the sensitivity and specificity of the test is better than electrocardiographic exercise stress test. The predictive value of the test for a patient highly depends of the prevalence of the coronary disease for this patient; however the results of Tl scintigraphy are far from an ideal test; quantitative or semi-quantitative analysis of the image compared to the analogical image seems to improve sensitivity for detection of coronary disease. After myocardial infarction, its best use is to detect a left anterior descending stenosis after posterior or inferior infarction. Among the possible radio-elements of myocardial metabolism, scintigraphy with fatty acids opens interesting prospects for the study of the myocardial clearance of the radio-isotope, that reflects the global or regional myocardial metabolism

  1. PIXE analyses of cesium in rice grains

    Science.gov (United States)

    Sugai, Hiroyuki; Ishii, Keizo; Matsuyama, Shigeo; Terakawa, Atsuki; Kikuchi, Yohei; Takahashi, Hiroaki; Ishizaki, Azusa; Fujishiro, Fumito; Arai, Hirotsugu; Osada, Naoyuki; Karahashi, Masahiro; Nozawa, Yuichiro; Yamauchi, Shosei; Kikuchi, Kosuke; Koshio, Shigeki; Watanabe, Koji

    2014-01-01

    The Fukushima nuclear power plant accident released vast amounts of radioactive material into the environment. For instance, 134Cs and 137Cs have half-lives of about 2 and 30 years, respectively, and emit many harmful gamma rays. In 2012, rice with radioactivity >100 Bq/kg was occasionally reported in Fukushima prefecture. To determine where and how cesium accumulates in rice, we grew rice in soil containing stable cesium and investigated the distribution of cesium in rice using particle-induced X-ray emission (PIXE). This study found that cesium is accumulated in bran and germ at high concentrations, and white rice contains 40% of the cesium found in brown rice.

  2. Applications of radioisotopes in agriculture

    International Nuclear Information System (INIS)

    India has large population which is engaged in agriculture or related activities. With many agro-climatic zones, diversity in crops and traditional largely plant food based diets, there is need to meet these and increase agricultural production in the face of increasing constraints. Radiations and radioisotopes can contribute significantly to these developments. Mutation breeding is very useful technique in Indian context. Basic technique can be applied where a radiation source or irradiation service and facility to grow few thousand plants are available. Radiation processing can save the valuable food which is subject to spoilage by microbes and insects. Value addition by export is possible by meeting the quarantine and hygienisation conditions

  3. A liquid xenon radioisotope camera.

    Science.gov (United States)

    Zaklad, H.; Derenzo, S. E.; Muller, R. A.; Smadja, G.; Smits, R. G.; Alvarez, L. W.

    1972-01-01

    A new type of gamma-ray camera is discussed that makes use of electron avalanches in liquid xenon and is currently under development. It is shown that such a radioisotope camera promises many advantages over any other existing gamma-ray cameras. Spatial resolution better than 1 mm and counting rates higher than one million C/sec are possible. An energy resolution of 11% FWHM has recently been achieved with a collimated Hg-203 source using a parallel-plate ionization chamber containing a Frisch grid.

  4. Survey of industrial radioisotope savings

    International Nuclear Information System (INIS)

    Only three decades after the discovery of artificial radioactivity and two after radioisotopes became available in quantity, methods employing these as sources or tracers have found widespread use, not only in scientific research, but also in industrial process and product control. The sums spent by industry on these new techniques amount to millions of dollars a year. Realizing the overall attitude of industry to scientific progress - to accept only methods that pay relatively quickly - one can assume that the economic benefits must be of a still larger order of magnitude. In order to determine the extent to which radioisotopes are in daily use and to evaluate the economic benefits derived from such use, IAEA decided to make an 'International Survey on the Use of Radioisotopes in Industry'. In 1962, the Agency invited a number of its highly industrialized Member States to participate in this Survey. Similar surveys had been performed in various countries in the 1950's. However, the approaches and also the definition of the economic benefits differed greatly from one survey to another. Hence, the Agency's approach was to try to persuade all countries to conduct surveys at the same time, concerning the same categories of industries and using the same terms of costs, savings, etc. In total, 24 Member States of the Agency agreed to participate in the survey and in due course they submitted contributions. The national reports were discussed at a 'Study Group Meeting on Radioisotope Economics', convened in Vienna in March 1964. Based upon these discussions, the national reports have been edited and summarized. A publication showing the administration of the Survey and providing all details is now published by the Agency. From the publication it is evident that in general the return of technical information was quite high, of the order of 90%, but, unfortunately the economic response was much lower. However, most of the reports had some bearing on the economic aspects

  5. 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)

  6. Development of Radioisotope Tracer Technology

    International Nuclear Information System (INIS)

    The project is aimed to develop the radiotracer technology for process optimization and trouble-shooting to establish the environmental and industrial application of radiation and radioisotopes. The advanced equipment and software such as high speed data acquisition system, RTD model and high pressure injection tool have developed. Based on the various field application to the refinery/petrochemical industries, the developed technology was transfer to NDT company for commercial service. For the environmental application of radiotracer technology, injector, detector sled, core sampler, RI and GPS data logging system are developed and field tests were implemented successfully at Wolsung and Haeundae beach. Additionally tracer technology were also used for the performance test of the clarifier in a wastewater treatment plant and for the leak detection in reservoirs. From the experience of case studies on radiotracer experiment in waste water treatment facilities, 'The New Excellent Technology' is granted from the ministry of environment. For future technology, preliminary research for industrial gamma transmission and emission tomography which are new technology combined with radioisotope and image reconstruction are carried out

  7. Decontamination of radioisotope production facility

    International Nuclear Information System (INIS)

    The strippable coating method use phosphoric glycerol and irradiated latex as supporting agents have been investigated. The investigation used some decontaminating agents: EDTA, citric acid, oxalic acid and potassium permanganate were combined with phosphoric glycerol supporting agent, then EDTA Na2, sodium citric, sodium oxalic and potassium permanganate were combined with irradiated latex supporting agent. The study was needed to obtain the representative operating data, will be implemented to decontamination the Hot Cell for radioisotope production. The experiment used 50x50x1 mm stainless steel samples and contaminated by Cs-137 about 1.1x10-3 μCi/cm2. This samples according to inner cover of Hot Cell material, and Hot Cell activities. The decontamination factor results of the investigation were: phosphoric glycerol as supporting agent, about 20 (EDTA as decontaminating agent) to 47 (oxalic acid as decontaminating agent), and irradiated latex as supporting agent, about 11.5 (without decontamination agent) to 27 (KMnO4 as decontaminating agent). All composition of the investigation have been obtained the good results, and can be implemented for decontamination of Hot Cell for radioisotope production. The irradiated latex could be recommended as supporting agent without decontaminating agent, because it is very easy to operate and very cheap cost. (author)

  8. Cosmogenic radioisotopes on LDEF surfaces

    Science.gov (United States)

    Gregory, J. C.; Albrecht, A.; Herzog, G.; Klein, J.; Middleton, R.

    1992-01-01

    The radioisotope Be-7 was discovered in early 1990 on the front surface, and the front surface only, of the LDEF. A working hypothesis is that the isotope, which is known to be mainly produced in the stratosphere by spallation of nitrogen and oxygen nuclei with cosmic ray protons or secondary neutrons, diffuses upward and is absorbed onto metal surfaces of spacecraft. The upward transport must be rapid, that is, its characteristic time scale is similar to, or shorter than, the 53 day half-life of the isotope. It is probably by analogy with meteoritic metal atmospheric chemistry, that the form of the Be at a few 100 km altitude is as the positive ion Be(+) which is efficiently incorporated into the ionic lattice of oxides, such as Al2O3, Cr2O3, Fe2O3, etc., naturally occurring on surfaces of Al and stainless steel. Other radioisotopes of Be, Cl, and C are also produced in the atmosphere, and a search was begun to discover these. Of interest are Be-10 and C-14 for which the production cross sections are well known. The method of analysis is accelerator mass spectrometry. Samples from LDEF clamp plates are being chemically extracted, purified, and prepared for an accelerator run.

  9. Multiphoton ionization of atomic cesium

    International Nuclear Information System (INIS)

    We describe experimental studies of resonantly enhanced multiphoton ionization (MPI) of cesium atoms in the presence and absence of an external electric field. In the zero-field studies, photoelectron angular distributions for one- and two-photon resonantly enhanced MPI are compared with the theory of Tang and Lambropoulos. Deviations of experiment from theory are attributed to hyperfine coupling effects in the resonant intermediate state. The agreement between theory and experiment is excellent. In the absence of an external electric field, signal due to two-photon resonant three-photon ionization of cesium via np states is undetectable. Application of an electric field mixes nearby nd and ns levels, thereby inducing excitation and subsequent ionization. Signal due to two-photon excitation of ns levels in field-free experiments is weak due to their small photoionization cross section. An electric field mixes nearby np levels which again allows detectable photoionization signal. For both ns and np states the field induced MPI signal increases as the square of the electric field for a given principal quantum number and increases rapidly with n for a given field strength. Finally, we note that the classical two-photon field-ionization threshold is lower for the case in which the laser polarization and the electric field are parallel than it is when they are perpendicular. 22 references, 11 figures

  10. 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.

  11. 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)

  12. Role of radioisotopes in the study of insect pests

    International Nuclear Information System (INIS)

    Although the use of nuclear techniques, particularly radioisotopes, in entomological research is less than a century old, the contribution of radioisotopes to the science of studying insects (Entomology) is indispensable. In fact, radioisotopes provided a very important and sometimes a unique tool for solving many research problems in entomology. This article discusses the most important and widely used applications of radioisotopes in studying insect pests. In particular, it concentrates on the subject of radioisotopes used in entomological research, methods of labeling insect with radioisotopes, half life of radioisotopes, and the role of radioisotopes in physiological, ecological, biological and behavioral studies of insects. (author)

  13. Activity calculation of radioisotopes in HFETR

    International Nuclear Information System (INIS)

    The activity calculating method and formulas of seven kinds of radioisotopes for High Flux Engineering Test REactor (HFETR) are given. The perturbation of targets to neutron fluence rate is considered while targets are put into the neutron fluence rate field of reactor core. All perturbing factors of seven kinds of radioisotopes being used in HFETR are presented. After considering the perturbation, the calculating accuracy of radioisotope activity has been raised 10%. The given method and formulas have ended the history of all activities estimated by experiences, except for that of 60Co, in the radioisotope production of HFETR. The conclusions are also useful and instructive for the production of radioisotopes in HFETR. (8 tabs.)

  14. Neutron-rich radioisotope production in Australia

    International Nuclear Information System (INIS)

    The author discusses Australia's Replacement Research Reactor (RRR) and the applications of the range of radioisotopes it will produce. The ANSTO's RRR will produce radioisotopes that have medical., industrial and environmental applications. Medicinal radioisotopes would provide the nuclear medicine physicians and oncologists with the necessary tool to non-invasively diagnose and cure diseases, ranging from cancer to infections. Industrial radioisotopes provide the industrial community with high technology tools to evaluate and assess the status of high reliability equipment with respect to safety and functionality in a non-destructive modality. The current commercial radioisotope sources include 60Co, 169Yb and 192Ir with source strengths limited by the HlFAR neutron flux and capacity. These sources are primarily used for industrial X ray moisture, level and thickness gauging. The RRR will allow expansion of the commercial source strengths and allow ANSTO to meet the growing commercial Australasian market for radioactive sources

  15. Application of radioisotopes in pharmaceutical research

    International Nuclear Information System (INIS)

    Full text: To use of radioisotopes in the processes of receiving radiopharmaceutical diagnostic means it is widely know [1]. Radioactivity labeled chemical compounds, pharmacological kinetics of which allows one solving a concrete diagnostic problem in an organism are used in radio pharmaceutics. In spite of this choice of the radioisotope, possessing the most favorable nuclei-physical characteristics for it to be detected and minimization of beam loadings, be of great importance. Development of a method of introduction of a radioisotope also has important value, as it is included into chemical structure of a radiopharmaceutical preparation. One more way of use of radioisotopes in pharmaceutics is their use as a radioactive mark at a stage of creation of a new medical product. And in this case, all those moments, which are listed above, take place. Preparations labeling by radioisotopes are used basically for their studying pharmacological kinetics. In Institute of nuclear physics AS RU, in recent years, works are done on studying pharmacological kinetics of some new medical products, which have been synthesized in the Tashkent pharmaceutical institute. These preparations are on the basis of microelements with a complex set of properties possessing expressed biological activity and have great value in pharmaceutical science of Republic of Uzbekistan. Reception of labeled compounds of all preparations was carried out by a method of introduction of a radioisotope at a stage of their synthesis. The work presents the results of researches on synthesis and study of pharmacological kinetics of radioactively labeled preparations - PIRACIN, labeled by radioisotope 69mZn; FERAMED, labeled by radioisotope 59Fe; COBAVIT, labeled by radioisotope 57Co; VUC, labeled by radioisotope57Co

  16. Radioisotopes - byproducts of the uranium cycle with commercial applications

    International Nuclear Information System (INIS)

    Several fission products are used in industry, medicine and research. Cesium 137 and strontium 90 are the most useful long-lived fission products recovered from the processing of spent reactor fuel. The short-lived isotopes molybdenum 99, xenon 133 and iodine 131 are more widely used, particularly in medicine. Technetium 99, daughter of molybdenum 99, is now the most widely used isotope for in-vivo diagnosis. More than 65 percent of all the molybdenum 99 from which this material is derived comes from uranium targets irradiated in reactors at Chalk River Nuclear Laboratories. Transuranic elements produced by successive neutron capture/decay events in a reactor have at least one commercial application: americium 241 is used in domestic and industrial smoke detectors. Plutonium 238 or americium 241 are combined with beryllium as neutron sources for oil well logging or moisture measurement. Many other isotopes are produced by target irradiation in reactors, including cobalt 60, iodine 125, carbon 14 and iridium 192. New uses are being found for the tritium produced in CANDU reactors by neutron capture in heavy water. Many radioisotopes produced as byproducts of the nuclear fuel cycle have become essential to our high standard of living. Canada is not only the world's largest uranium producer but also the major supplier of reactor isotopes

  17. 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

  18. Decontamination of radioactive cesium in soil

    International Nuclear Information System (INIS)

    Agricultural soil containing radioactive cesium was decontaminated using an extraction method involving aqueous potassium solutions. Results demonstrated that the potassium solution could extract radioactive cesium from soil artificially contaminated with 137Cs, although extraction rate decreased as time after contamination increased. However, visual examination of radioactivity distribution in soil samples significantly contaminated by the accident at the Fukushima Daiichi nuclear power plant showed that radioactive cesium also existed as insoluble particles. Therefore, reducing the volume of radioactive wastes generated from soil decontamination requires a physical decontamination method combined with chemical treatment. (author)

  19. Studies on cesium uptake by phenolic resins

    International Nuclear Information System (INIS)

    The selective removal of cesium by phenolic ion-exchange resins from highly salted alkaline radioactive solutions was studied. The resins were synthesized by alkaline polycondensation of phenol, resorcinol, catechol, and resorcinol-catechol mixture with formaldehyde and characterized for their moisture regain, ion-exchange (H+ → Na+) capacity, and distribution coefficient (KD) for cesium. The effects of open and sealed curing of the polymers on their properties were studied. The effect of Na+, NaOH, and Cs+ concentration on the uptake of cesium by resorcinol-formaldehyde resin was investigated, in particular. The chemical, thermal, and radiation stabilities of the polymers were also studied

  20. 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)

  1. Linear accelerator for radioisotope production

    International Nuclear Information System (INIS)

    A 200- to 500-μA 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-μA 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-μA beam, and the cost per beam watt on the target is less than half that of comparable cyclotrons

  2. Radioisotope studies under pathologic conditions

    International Nuclear Information System (INIS)

    This article presents a general discussion on salivary pathology, before dealing with the various salivary gland diseases which can draw real advantage from radioisotope studies. Clinical problems related to the salivary glands first concern diffuse or focal glandular swelling. Focal swelling includes inflammatory or metastatic deposits in preauricular or submandibular lymph nodes, cysts, abscesses, foci of inflammation, benign and malignant neoplasms of the salivary glands themselves or of surrounding blood or lymph vessels, nerves, connective tissue, and oral mucosa. Primary tumors of the salivary glands are rare and usually benign. The combination of a systemic disease with dry mouth and dry eyes due to inflamed conjunctiva and cornea because of decreased fluid production, forms Sjogren syndrome. It may also cause diffuse glandular swelling. Chronic alcoholism, cirrhosis, diabetes mellitus, hyperlipoproteinemia, and malnutrition are other pathologic conditions sometimes associated with diffuse salivary gland swelling

  3. Method for monitoring radioactive cesium concentration in water using cesium adsorption disk and GM survey meter

    International Nuclear Information System (INIS)

    A method for monitoring radioactive cesium concentration in water using a cesium adsorption disk and a GM survey meter has been developed to ascertain whether the water quality meets standards on radiological contaminants in water. In this method, both dissolved and suspended forms of radioactive cesium are collected on the cesium adsorption disk by means of filtration of a water sample. Beta count rate of the disk is converted into radioactivity using a conservative calibration factor obtained here. The present method was applied to monitoring of decontaminated water of an outdoor school swimming pool in Date City after Fukushima Daiichi Nuclear Power Plant accident. (author)

  4. Trapping characteristics for gaseous cesium generated from different cesium compounds by fly ash filter

    International Nuclear Information System (INIS)

    The purpose of this study is to evaluate the applicability of the fly ash ceramic foam filter to trap gaseous cesium generated during the OREOX and sintering processes of DUPIC green pellets. The trapping experiments of gaseous cesium generated from different cesium compounds using fly ash filters were carried out in a two-zone furnace under air and hydrogen (Ar/4% H2) conditions. XRD and SEM analyses were used to analyze reaction products of different cesium compounds with fly ash filters. To manufacture ceramic foam filters, fly ash with a Si/Al mole ratio of 2.1 and polyvinyl alcohol as binder were used. Reaction products formed by the trapping reaction of different cesium compounds with fly ash filters were investigated. The major reaction products of gaseous cesium generated from cesium silicate and CsI by fly ash filters indicated that pollucite (CsAlSi2O6) phase was formed under air and hydrogen conditions when the carrier gas velocity was 2 cm/sec. The minimum reaction temperature of fly ash filter with gaseous cesium was determined as about 600 deg. C. Finally, off-gas treatment system of sintering process in a hot cell of lMEF was explained as an application example of fly ash filter for trapping gaseous cesium. (author)

  5. 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.

  6. 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

  7. Sintered wire cesium dispenser photocathode

    Energy Technology Data Exchange (ETDEWEB)

    Montgomery, Eric J; Ives, R. Lawrence; Falce, Louis R

    2014-03-04

    A photoelectric cathode has a work function lowering material such as cesium placed into an enclosure which couples a thermal energy from a heater to the work function lowering material. The enclosure directs the work function lowering material in vapor form through a low diffusion layer, through a free space layer, and through a uniform porosity layer, one side of which also forms a photoelectric cathode surface. The low diffusion layer may be formed from sintered powdered metal, such as tungsten, and the uniform porosity layer may be formed from wires which are sintered together to form pores between the wires which are continuous from the a back surface to a front surface which is also the photoelectric surface.

  8. 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.``

  9. 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.''

  10. 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

  11. 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.

  12. 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

  13. 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

  14. 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.)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  17. 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.

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

    International Nuclear Information System (INIS)

    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

  19. 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.

  20. 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.

  1. 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...

  2. 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

  3. Radioisotope production at PUSPATI - five year programme

    International Nuclear Information System (INIS)

    Most of the basic laboratory facilities for radioisotopes production at PUSPATI will be commissioned by September 1983. Work on setting up of production and dispensing facilities is in progress as the nuclides being worked on are those that are commonly used in medical applications, such as Tc-99m, I-131, P-32 and other nuclides such as Na-24 and K-42. Kits for compounds labelled with Tc-99m such as Stannous Pyrophosphate, Sulfur Colloid and Stannous Glucoheptonate are being prepared. The irradiation facilities available now for radioisotope production at the PUSPATI TRIGA Reactor include a central thimble (flux density 1 x 10 13 n.cm-2S-1) and a rotary specimen rack (flux density 0.2 x 1013 n.cm-1S-1). Irradiation schedules and target handling techniqes are discussed. Plans for radioisotope production at PUSPATI over the period of 1983-1987, based on present demand for radioisotope, are also explained. (author)

  4. 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

  5. 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)

  6. 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...

  7. 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).

  8. 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?.

  9. Thirty years history of Japan Radioisotope Association

    International Nuclear Information System (INIS)

    The import of radioisotopes into Japan under occupation was permitted and their utilization was reopened in 1950. The Japan Radioisotope Association was established in May, 1951. At that time, the radioisotope committee in the science and technology administration council handled the import, the spread of utilization and the safety of radioisotopes as the administration authority. In the management of the Association, most attention has been paid to secure the autonomy. The Association is responsible to develop correctly the utilization of radioisotopes, and the autonomy of the Association is indispensable to accomplish it. The first import of isotopes was nine nuclides amounting to $3905, which were used in 25 organizations. In 1980, the Association handled the isotopes totaling 28 billion yen, and about 4500 business establishments used isotopes as of March, 1981. The development of the utilization of radioisotopes during 30 years has been really conspicuous. However, one of the important problems is the treatment of wastes. In order to solve this problem, the understanding of people is a key point. The knowledge of whole nation on atomic energy must be increased. (Kako, I.)

  10. 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)

  11. 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)

  12. Early radioisotope uses in Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Segovia, N.; Tejera, A.; Bulbulian, S.; Palma, F

    1991-10-15

    Mexico is traditionally a mining country and the first information about the presence of uranium is related to mine exploitation. Around 1945 when uranium became economically important, a rumor had spread that large amounts of black ceramics from Oaxaca were being purchased and sent abroad because of its assumed high uranium content. It was only in 1949 when minerals containing thorium and uranium were declared by law as 'National Reserves'. In those years a radium emanation plant was installed at the 'Hospital General' in Mexico City with the main purpose of carrying out radon seed implantation in tumors. In the fifties a radium dial painting facility was operating in the city of Toluca some 70 km from Mexico City. In 1955, when the National Commission of Nuclear Energy (CNEN) was founded by a government decree, two main activities were in sight: a training program on 'Radioisotope Techniques and Nuclear Instrumentation' and the creation of specialized laboratories. In this paper a general description of these events and undertakings spanning the decades 1940 to 1970 is given. (Author)

  13. Radioisotopes In Animal Production Research

    International Nuclear Information System (INIS)

    Animal productivity may be measured among others, in terms of two important physiological processes of reproduction and growth each of which involves a number of integrated disciplines. Both physiological processes are controlled by interactions of genotype and environment. Reproduction essentially involves complex physiological processes controlled by secretions of endocrine glands known as hormones. On the other hand growth is determined largely by availabilty of essential nutrients. In order to achieve good reproductive and growth rates adequate and constant nutrition for livestock include pasture, cereals, tubers and their by-products as well as industrial by-products. While reproduction is essential to provide the required number and replacement of livestock, growth guarantees availability of meat. Another aspect of livestock production is disease control. An animal needs a good health to adequately express its genetic make up and utilize available nutrition. Research in animal production is aimed at improving all aspects of productivity of livestock which include reproduction, growth, milk production, egg production, good semen etc. of livestock. In order to achieve this an understanding of the biochemical and physiological processes occurring in the animal itself, and in the feedstuff fed to the animal as well as the aetiology and control of diseases affecting the animal among other factors, is desirable. A number of methods of investigation have evolved with time. These include colorimetry, spectrophotometry, chromatography, microscopy and raidoisotopic tracer methods. While most of these methods are cumbersome and use equipment with low precision, radioisotopic tracer methods utilize equipment with relatively high precision

  14. Early radioisotope uses in Mexico

    International Nuclear Information System (INIS)

    Mexico is traditionally a mining country and the first information about the presence of uranium is related to mine exploitation. Around 1945 when uranium became economically important, a rumor had spread that large amounts of black ceramics from Oaxaca were being purchased and sent abroad because of its assumed high uranium content. It was only in 1949 when minerals containing thorium and uranium were declared by law as 'National Reserves'. In those years a radium emanation plant was installed at the 'Hospital General' in Mexico City with the main purpose of carrying out radon seed implantation in tumors. In the fifties a radium dial painting facility was operating in the city of Toluca some 70 km from Mexico City. In 1955, when the National Commission of Nuclear Energy (CNEN) was founded by a government decree, two main activities were in sight: a training program on 'Radioisotope Techniques and Nuclear Instrumentation' and the creation of specialized laboratories. In this paper a general description of these events and undertakings spanning the decades 1940 to 1970 is given. (Author)

  15. 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

  16. 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

  17. 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.

  18. 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

  19. 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

  20. Research on decontamination of cesium contaminated soil by electrokinetic process

    International Nuclear Information System (INIS)

    In this research, electrokinetic process was applied for the decontamination of cesium contaminated soil. As a result, about 4.0 times cesium removal was achieved by applying a DC electric field of 80 V/m to comparing zero electric field in treatment for 30 days. Therefore, the electrokinetic process has a possibility to decontamination of cesium contaminated soil. (author)

  1. Cesium ion uptake by moss (Hypnum cupressiforme)

    International Nuclear Information System (INIS)

    Lower land mosses uptake water and minerals from the atmosphere. They can collect metals polluting the air and radioactive fallout elements so they can be suitable for monitoring of these substances. Cesium ion uptake by Hypnum cupressiforme is studied by a radioactive tracer, 134Cs. The quantity of cesium ion in different celluar locations and the capacity of ion uptake is determined. The total capacity is found to be several times 10-3 mol g-1 and is therefore of the same order of magnitude as the cation exchange capacity of ion exchangers. The kinetics and reversibility of the process is studied as well. (orig.)

  2. 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

  3. Environmental transfer of radio-cesium

    International Nuclear Information System (INIS)

    A large amount of Cs 134 and 137 were emitted from the destroyed reactors of Fukushima Daiichi Nuclear Power Station and deposited on the soil surface of vast area including forests, fields, and residential areas. The present report explains mainly land transfer behaviors of cesium which deposited on the surface soils, absorbed into soil particles as time passed on and finally became difficult to move from the particles (aging effect). Depth-distribution of radio-cesium in rice paddy and grassland as well as the change over years is presented. Changes with the passage of time of Cs 137 concentrations in leaves of spinach, wormwood, and persimmon are also provided. (S. Ohno)

  4. 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.

  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. RADIOISOTOPE INVENTORY FOR TSPA-SR

    Energy Technology Data Exchange (ETDEWEB)

    C. Leigh; R. Rechard

    2001-01-30

    The total system performance assessment for site recommendation (TSPA-SR), on Yucca Mountain, as a site (if suitable) for disposal of radioactive waste, consists of several models. The Waste Form Degradation Model (i.e, source term) of the TSPA-SR, in turn, consists of several components. The Inventory Component, discussed here, defines the inventory of 26 radioisotopes for three representative waste categories: (1) commercial spent nuclear fuel (CSNF), (2) US Department of Energy (DOE) spent nuclear fuel (DSNF), and (3) high-level waste (HLW). These three categories are contained and disposed of in two types of waste packages (WPs)--CSNF WPs and co-disposal WPs, with the latter containing both DSNF and HLW. Three topics are summarized in this paper: first, the transport of radioisotopes evaluated in the past; second, the development of the inventory for the two WP types; and third, the selection of the most important radioisotopes to track in TSPA-SR.

  7. RADIOISOTOPE INVENTORY FOR TSPA-SR

    International Nuclear Information System (INIS)

    The total system performance assessment for site recommendation (TSPA-SR), on Yucca Mountain, as a site (if suitable) for disposal of radioactive waste, consists of several models. The Waste Form Degradation Model (i.e, source term) of the TSPA-SR, in turn, consists of several components. The Inventory Component, discussed here, defines the inventory of 26 radioisotopes for three representative waste categories: (1) commercial spent nuclear fuel (CSNF), (2) US Department of Energy (DOE) spent nuclear fuel (DSNF), and (3) high-level waste (HLW). These three categories are contained and disposed of in two types of waste packages (WPs)--CSNF WPs and co-disposal WPs, with the latter containing both DSNF and HLW. Three topics are summarized in this paper: first, the transport of radioisotopes evaluated in the past; second, the development of the inventory for the two WP types; and third, the selection of the most important radioisotopes to track in TSPA-SR

  8. 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.)

  9. 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

  10. Development of an adsorbent for both cesium and strontium

    International Nuclear Information System (INIS)

    Described is the development of the adsorbent in the title at the process of developing the agent to adsorb each element. For cooling the reactors injured by the Fukushima Nuclear Power Plant Accident by the earthquake and tsunami on the day before (Mar. 11, 2011), fresh/ sea water is supplied in the reactor and flows out contaminated with radioactive elements in the turbine building and then in the treatment plant to remove oil and cesium for re-circulation to the reactor. Water from the plant still contains radioisotopes derived from fission, like 90Sr/90Y at 1.2 x 108 Bq/L and 137Cs/137mBa at 6.1 x 103 Bq/L, and from activation of reactor materials. Before the plant, the water contains 137Cs at the level as high as 4.1 x 107 Bq/L. Authors have examined various agents to adsorb 90Sr and 137Cs with a measure of partition coefficient Kd (L of the artificial sea water/kg) and have come to find out the adsorbent in the title: it is derived from the Cs-adsorbing crystalized silico-titanate (CST). The adsorbent is obtainable by surface treatment of CST with NaOH and has high Kds of >1 x 103 and >1 x 104 L/kg for Sr and Cs, respectively, while other ordinary adsorbents' Kds are: artificial zeolite 1-10 x 102/1-10 x 101 for Sr/Cs, respectively; natural one 0.1-10 x 101/1-10 x 102; ferrocyanide 0.1-10 x 101/1-10 x 104, and CST 1 x 101/>1 x 104. When 1 m3 of the present adsorbent is used, >99% of Cs and Sr can be removable in >3,000 m3 of contaminated water, suggesting its usefulness for dealing with water after the Accident. (T.T.)

  11. Production of radioisotopes using a cyclotron

    International Nuclear Information System (INIS)

    Cyclotron produced radioisotopes are generally neutron deficient and decay by EC or β+ emission. They find major applications in diagnostic nuclear medicine. The production processes involve rather sophisticated technology and the areas needing research and development work include nuclear data, targetry, chemical processing, remote control, automation and quality control. A comparison of the various parameters relevant to the production of radioisotopes using a nuclear reactor and a cyclotron is given. The cyclotron products are more expensive than the reactor products; they are, however, far superior to the latter as far as in-vivo functional studies are concerned. (author)

  12. Industrial applications of radioisotope techniques in Poland

    International Nuclear Information System (INIS)

    A general review of applications of radioisotope techniques in the Polish industry for about 25 years is given. The radiotracer methods used in metallurgy, hydrometallurgy, glass industry, oil and petroleum industries, in material testing and in other industries are described. Neutron activation analysis methods as well as nuclear gauges for industry (thickness meters, density meters, conveyer belt weigher, acid concentration meters and others) are also presented. The economic advantages of industrial applications of radioisotope techniques are described too. 42 refs., 43 figs., 11 tabs. (author)

  13. Radioisotope producer reactor: technical report 1991

    International Nuclear Information System (INIS)

    This report describes activities in the year of 1991 related the Project of a New Conception for the Radioisotope Producer reactor (RPR). Results as well as proposals for future studies are presented. Chapter 1 describes investigations performed for the conception of the reactor core. Chapters 2 and 3 contain preliminary results of thermal-hydraulic calculations and accident analysis respectively. Chapter 4 describes the aspects of production of 99 Mo in the RPR, concluding the body of the paper. This initial effort will continue with the Radioisotope Producer Reactor Conceptual Project, to be carried out during the year of 92. (author)

  14. Radioisotopes in non-destructive testing

    International Nuclear Information System (INIS)

    After defining nondestructive testing (NDT) and comparing this concept with destructive testing, a short description is given of NDT methods other than radiologic. The basic concepts of radiologic methods are discussed and the principles of radiography are explained. Radiation sources and gamma radiography machines are next reviewed and radiographic inspection of weldings and castings is described. A brief description is given of the radiographic darkroom and accessories. Other radioisotope methods, such as neutron radiography, are shortly reviewed. Cost estimations for radioisotopic equipment conclude the report. (author)

  15. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1982

    International Nuclear Information System (INIS)

    The radioisotope production and distribution activities by facilities at Argonne National Laboratory, Pacific Northwest Laboratory, Brookhaven National Laboratory, Hanford Engineering Development Laboratory, Idaho Operations Office, Los Alamos Scientific Laboratory, Oak Ridge National Laboratory, Savannah River Laboratory, and UNC Nuclear Industries, Inc. are listed. The information is divided into five sections: isotope suppliers, facility, contacts, and isotopes or services supplied; alphabetical list of customers, and isotopes purchased; alphabetical list of isotopes cross-referenced to customs numbers; geographical location of radioisotope customers; and radioisotope sales and transfers-FY 1982

  16. 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.

  17. 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.

  18. 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.

  19. Scintillator handbook with emphasis on cesium iodide

    Science.gov (United States)

    Tidd, J. L.; Dabbs, J. R.; Levine, N.

    1973-01-01

    This report provides a background of reasonable depth and reference material on scintillators in general. Particular attention is paid to the cesium iodide scintillators as used in the High Energy Astronomy Observatory (HEAO) experiments. It is intended especially for use by persons such as laboratory test personnel who need to obtain a working knowledge of these materials and their characteristics in a short time.

  20. 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

  1. Structure and manual of radioisotope-production data base, ISOP

    International Nuclear Information System (INIS)

    We planned on collecting the information of radioisotope production which was obtained from research works and tasks at the Department of Radioisotopes in JAERI, and constructed a proto-type data base ISOP after discussion of the kinds and properties of the information available for radioisotope production. In this report the structure and the manual of ISOP are described. (author)

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. List of DOE radioisotope customers with summary of radioisotope shipments, FY 1981

    International Nuclear Information System (INIS)

    The seventeenth 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 Laboratory; 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

  7. How to find out in radioisotope methodology

    International Nuclear Information System (INIS)

    The subject is dealt with in sections entitled: tracing books by topic; radioisotope methodology cross reference structure; finding a review; journals and how to trace journal articles; abstract; theses and dissertations; research and development reports; critical reviews and information summaries; data books; dictionaries and encyclopedias; guides to the literature; whom to contact; expert advice, research in progress, institutions. (U.K.)

  8. Fuel selection for radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    The availability of Radioisotope Thermoeletric Generator fuels is evaluated based on the amount of fuel discharged from selected power reactors. In general, the best alternatives are either to use Plutonium-238 produced by irradiation of Neptunium-237 generated in typical thermal reactors or to use Curium-244 directly separated from the discharged fuels of fast or thermal reactors. (author)

  9. Radioisotope methods for cardio-rehabilitation diagnostics

    International Nuclear Information System (INIS)

    Radio-cardiography, radio-cyclography, and radioisotopic examinations of the pulmonary and coronary circulation are reviewed, including the instruments and labelled compounds applied to the measurements. The indications, the normal values and the information provided by the different methods are reported with special emphasis on ischaemic diseases, myocardial infarction and valve disorders. (L.E.)

  10. Application of artificial radioisotopes in hydrological studies

    International Nuclear Information System (INIS)

    In this article, various applications of the artificial radioisotopes in surface water and groundwater investigations are briefly reviewed with a few recent case studies. They are found to be extremely useful in understanding the hydrological processes and obtaining pertinent parameters such as dilution factors, dispersion coefficients, rate of sediment transport in surface waters and recharge rate, velocity and flow direction in groundwater systems. (author)

  11. 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

  12. The industrial application of radioisotopes in Australia

    International Nuclear Information System (INIS)

    Over the past 10 years, the Australian Atomic Energy Commission has conducted a wide-ranging program of radioisotope applications to solve industrial problems of local, regional or national importance. Most of the investigations have been concerned with the behaviour of large complex systems. Broadly, the work covers such economically important fields as flow studies, environmental studies and coastal engineering studies. (author)

  13. 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)

  14. Development of radioisotope production in the Philippines

    International Nuclear Information System (INIS)

    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 131I. In the Philippines, radioisotopes are widely used in nuclear medicine, with 131I and 99mTc 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 131I 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 99Mo-99mTc generators, based on low specific activity reactor-produced 99Mo, research and development work on the preparation of 99mTc gel generators is ongoing. (author)

  15. Radioisotopes and ionizing radiations in biological research

    International Nuclear Information System (INIS)

    This book deals with the use of radioisotopes and ionizing radiations in the various aspects of biological research. The following topics were presented: labelled compounds; conformation-function relationships of hormonal polypeptides and their spectroscopic study; neutron scattering and neutron diffraction for biological studies; high resolution autoradiography; radioimmunoassay; nuclear medicine; transfer of excitation energy in photosynthesis; radioagronomy; radiation preservation of food

  16. Radioisotope licence application: Fixed nuclear gauges

    International Nuclear Information System (INIS)

    This guide will assist you in completing and filing an application for a new licence or licence renewal for fixed nuclear gauges in accordance with the Atomic Energy Control Regulations and radioisotope licensing policies. It also provides some of the background information that you will require in order to safely use radioactive materials

  17. Production of Radioisotopes and Radiopharmaceuticals. Pt. G

    International Nuclear Information System (INIS)

    The radioisotope products such as P-32, I-131, Tc-99m, Cr-51 and others are being in the Nuclear Research Institute (Dalat) for medical uses. Additionally, the development of the chromatographic gel-type Tc-99m generator, new method for I-131 production, inorganic ion exchanger is introduced. (N.H.A). 3 refs, 5 figs, 1 tab

  18. The control of radioisotopes in Canada

    International Nuclear Information System (INIS)

    The Regulations applicable to the control of radioisotopes in Canada are reviewed. The administrative procedures are described, the definition of atomic radiation workers clarified and the means for inspections and compliance indicated. An outline is provided of the main revisions currently under consideration. (author)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  1. 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.

  2. 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)

  3. Composition and process for separating cesium ions from an acidic aqueous solution also containing other ions

    Science.gov (United States)

    Dietz, M.L.; Horwitz, E.P.; Bartsch, R.A.; Barrans, R.E. Jr.; Rausch, D.

    1999-03-30

    A crown ether cesium ion extractant is disclosed as is its synthesis. The crown ether cesium ion extractant is useful for the selective purification of cesium ions from aqueous acidic media, and more particularly useful for the isolation of radioactive cesium-137 from nuclear waste streams. Processes for isolating cesium ions from aqueous acidic media using the crown ether cesium extractant are disclosed as are processes for recycling the crown ether cesium extractant and processes for recovering cesium from a crown ether cesium extractant solution. 4 figs.

  4. Novel radioisotope applications in industry promoted by the IAEA

    International Nuclear Information System (INIS)

    Presently, there is a lively activity in further development and use of radioisotope technology. Novel radioisotope applications in industry are promoted by the IAEA. Radioisotope technology is contributing significantly to improving and optimising process performance bringing an annual economic benefit to industry of several billion US$. Probably, an average benefit to cost ratio of 40: 1 is reasonably representative of radioisotope applications in industry. There are few short-term investments, which will give a return of this magnitude. The cost effectiveness of radioisotope applications should be widely promulgated to encourage industrialists to take full advantage of the technology. (author)

  5. 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

  6. Strontium-90 and cesium-137 in milk

    International Nuclear Information System (INIS)

    The milk samples have been collected from 30 prefectures by prefectural public health laboratories and institutes (raw milk: 4 times per year for the report to WHO, and raw and city milk: 2 times per year), and analysed for strontium-90 and cesium-137 content at Japan Chemical Analysis Center. Collected samples were the raw milk and the city ones for the producing districts and the consuming ones, respectively. Three liters of fresh milk were carbonized in each prefectural public health laboratories and institutes, and then it was asked at Japan Chemical Analysis Center. The ask to which both some carriers and hydrochloric acid were added, was destroyed under heating. The nuclides was dissolved into hydrochloric acid and filtrated, after it was added with nitric acid and heated to dryness. The filtrate was radiochemically analysed for strontium-90 and cesium-137 using the method recommended by Science and Technology Agency. (author)

  7. Cesium stress and adaptation in pseudomonas fluorescens

    International Nuclear Information System (INIS)

    Industrialization and acid rain have led to a marked increment on the bioavailability of numerous metals. These metallic pollutants pose a serious threat to the ecosystem due to their ability to interact negatively with living organisms. Thus, considerable effort has been directed towards the development of environmentally-friendly technologies tailored to the management of metal wastes. As microbes are known to adapt to most environmental stresses, they constitute organisms of choice in the study of molecular adaptation processes. The adaptive features may be subsequently engineered for biotechnological applications. Cesium, a monovalent metal with chemical similarities to potassium but no know essential biological function has become a cause of environmental concern owing to its accidental release from the Chernobyl nuclear accident. This study examines the impact of cesium on the soil microbe Pseudomonas fluorescensts, and discusses the possibilities of its use in management of this nuclear waste. 15 refs., 3 figs

  8. Thermochemical evaluation and preparation of cesium uranates

    International Nuclear Information System (INIS)

    Two kinds of cesium uranates, Cs2UO4 and Cs2U2O7, which are predicted by thermochemical estimation to be formed in irradiated oxide fuels, were prepared from U3O8 and Cs2CO3 for measurements of the thermal expansions and thermal conductivities. In advance of the preparation, thermochemical calculations for the formation and decomposition of these cesium uranates were performed by Gibbs free energy minimizer. The preparation temperatures for Cs2UO4 and Cs2U2O7 were determined from the results of the thermochemical calculations. The prepared samples were analyzed by X-ray diffraction, which showed that the single phases of Cs2UO4 and Cs2U2O7 were formed. Thermogravimetry and differential thermal analysis were also performed on these samples, and the decomposition temperatures were evaluated. The experimental results were in good agreement with those of the thermochemical calculations. (author)

  9. Cesium legacy safety project management work plan

    International Nuclear Information System (INIS)

    This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)

  10. Murine immunization by cesium-137 irradiation attenuated Schistosoma mansoni cercariae

    International Nuclear Information System (INIS)

    Cesium-137, becoming a more readily available ionizing gamma radiation source for laboratory use, was shown to effectively attenuate Schistosoma mansoni cercariae for vaccine production. In parallel comparison studies with the murine model, cesium-137 attenuated cercariae consistently afforded better protection than did the cobalt-60 prepared vaccine. Dose-response data indicated that the optimal total irradiation with cesium-137 was between 45 and 50 Krad

  11. Murine immunization by cesium-137 irradiation attenuated Schistosoma mansoni cercariae

    Energy Technology Data Exchange (ETDEWEB)

    Stek, M. Jr.; Minard, P.; Cruess, D.F.

    1984-06-01

    Cesium-137, becoming a more readily available ionizing gamma radiation source for laboratory use, was shown to effectively attenuate Schistosoma mansoni cercariae for vaccine production. In parallel comparison studies with the murine model, cesium-137 attenuated cercariae consistently afforded better protection than did the cobalt-60 prepared vaccine. Dose-response data indicated that the optimal total irradiation with cesium-137 was between 45 and 50 Krad.

  12. Sorption of cesium 137 by steel from sodium melt

    International Nuclear Information System (INIS)

    Sorption of cesium-137 radionuclide by Kh18N10T steel from sodium melt at different temperatures (150-450 deg C) has been studied. Equilibrium coefficients of cesium distribution between sodium and steel are determined, which depend on the conditions of sorption realization, such as cesium concentration in sodium melt, the content of oxygen admixture in sodium and the state of sorbing surface

  13. Cesium-137 as a radiation source

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) Byproducts Utilization Program (BUP) seeks to develop and encourage widespread commercial use of defense byproducts that are produced by DOE. Cesium-l37 is one such byproduct that is radioactive and decays with emission of gamma rays. The beneficial use of this radiation to disinfect sewage sludge or disinfest food commodities is actively being pursued by the program. The radiation produced by cesium-l37(Cs-l37) is identical in form to that produced by cobalt-60(Co-60), an isotope that is widely used in commercial applications such as medical product sterilization. The choice of isotope to use depends on several factors ranging from inherent properties of the isotopes to availability and cost. The BUP, although centrally concerned with the beneficial use of Cs-l37, by investigating and assessing the feasibility of various uses hopes to define appropriate circumstances where cesium or cobalt might best be used to accomplish specific objectives. This paper discusses some of the factors that should be considered when evaluating potential uses for isotopic sources

  14. Removal of cesium from red deer meat

    International Nuclear Information System (INIS)

    The effect was studied of marinading on the reduction of cesium radionuclide activity in red deer meat contaminated by ingestion of feed containing 134Cs+137Cs from radioactive fallout following the Chernobyl accident. Two types of marinade were studied, viz., a vinegar infusion and a vinegar infusion with an addition of vegetables and spices. The meat was chopped to cubes of about 1.5 cm in size and the marinading process took place at temperatures of 5 and 11 degC. The drop of cesium content in the meat was determined by gamma spectrometry at given time intervals. The replacement of the marinade and the duration of the process were found to maximally affect efficiency. If the solution was not replaced, about 80% of cesium radionuclides were removed after seven hours of marinading. With one replacement of the infusion the drop in 134Cs+137Cs radioactivity amounted to up to 90% after seven hours of marinading. No effects were shown of vegetable additions to the vinegar infusion and of the change in temperature from 5 to 11 degC on the efficiency of the process. (author). 3 tabs., 6 refs

  15. Radioisotope scanning for the spinal cord tumor

    International Nuclear Information System (INIS)

    Radioisotope scanning with sup(99m)Tc-pertechnetate or 67Ga-citrate for the spinal cord tumors are reported. Six patients with spinal cord tumors including 2 ependymomas, 1 neurinoma, 1 metastatic medulloblastoma, 1 metastatic astrocytoma, and 1 metastatic pinealoma as well as 6 patients with non-neoplastic lesions were examined by this method. Two out of 6 cases with tumors showed positive scans, and two showed equivocal scans. This new method is different from myeloscintigraphy or radioisotope angiography as already reported. It directly demonstrates the tumor itself like brain scanning does and is very useful as a nontraumatic method for screening spinal cord lesions, especially in poor risk patients. Both the usefulness and the limitations of this method are discussed. (auth.)

  16. Radioisotope method for demonstration of gastroesophageal reflux

    International Nuclear Information System (INIS)

    Gastroesophageal scintigraphy with 99mTc pertechnetate was performed in 17 patients for diagnosing gastroesophageal reflux. Two of these patients had sclerodermia, 2 had undergone gastric resection for gastroduodenal ulcer, 3 had chronic gastroduodenitis, 5 - duodenal ulcer, 1 - gastric ulcer, 1 - gastric ulcer+hiatus hernia, 1 six-year-old child -duodenal ulcer and 2 infants - gastritis. 99mTv-sulphocolloid was orally introduced in dose 7,40 mBq for adults, 4,44 mBq for infants, 5,18 mBq for children younger than 14 years and 5,92 mBq for patients having undergone gastric resection. Gastroesophageal reflux was demonstrated in 4 patients, the data of the radioisotopic examination being verified by fibrogastroscopy. The radioisotopic method for demonstration of gastroesophageal reflux is an original, physiological and noninvasive method of low radiation load for demonstration of gastroesophageal reflux, requiring no intubation

  17. 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)

  18. Radioisotopes development and production in Malaysia

    International Nuclear Information System (INIS)

    Development of radioisotopes for use in medical, industrial and agriculture sector was began in 1982 after the commissioning the 1MW TRIGA MARK II research reactor. Production of Tc-99m using Methyl Ethyl Ketone (MEK) extraction began in 1985 with the capacity about 1.2 Ci of Mo-99. By 1994, we produced Tc-99m generator using fission Molybdenum imported from Indonesia. Early 1990's, we assemble I-131 plant from Hungary for production of I-131 using TeO2 irradiated inour reactor but the yield are low. We have imported I-131 to meet the demand about 10 Ci/month. Development of Sm-153 EDTMP was began in 1994 and the trial production began in 1998. We also established the procedure for production of industrial and agriculture radioisotopes such as P-32, Na-24 and Au-198. (author)

  19. 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

  20. Micro-battery Development using beta radioisotope

    International Nuclear Information System (INIS)

    Nuclear battery which use the beta radiation sources emitting the low penetration radiation energy from radioisotope can be applied as the long term (more than 10 years) micro power source in MEMS and nano components. This report describes the basic concept and principles of nuclear micro-battery and its fabrication in space and military field. In particular direct conversion method is described by investigating the electron-hole generation and recombination in p-n junction of silicon betavoltaics with beta radiation

  1. Radiation protection at radioisotope processing facilities

    International Nuclear Information System (INIS)

    MDS Inc. is Canada's largest diversified health and life sciences company and provides health care services and products to prevent, diagnose and treat disease. MDS Nordion Inc. is a subsidiary of MDS Inc. and is located in Ottawa, Ontario. It provides much of the world's supply of radioisotopes used in nuclear medicine primarily to diagnose, but also to treat disease. MDS Nordion is composed of three major production divisions at its Ottawa location and serves customers in three major markets. These are primarily: radioisotopes used in nuclear medicine (Nuclear Medicine Division), radiation processing for sterilization of medical equipment and supplies, and food (Ion Technologies Division), and teletherapy equipment used in cancer treatment (Therapy Systems Division). MDS Nordion supplies customers in over 100 countries, exporting more than 95 percent of its product processed in Canada. Every year, 15 to 20 million diagnostic imaging tests are carried out in hospitals around the world, using radioisotopes supplied by MDS Nordion. In addition, 150 to 200 million cubic feet (that's enough to cover an entire CFL field - including the end zones - stacked over half a kilometer high) of single use medical products are sterilized using MDS Nordion supplied equipment. MDS Nordion receives medical isotopes from AECL, Chalk River Laboratories and processes the material to purify and quantify the radioisotope product. Sealed sources, comprised of cobalt 60, are supplied from CANDU reactors. Production processes include ventilated shielded cells with remote manipulators, gloveboxes and fumehoods, to effectively control the safety of the workplace and the environment, and to prevent contamination of the products. The facilities are highly regulated by the Canadian Nuclear Safety Commission (CNSC) for safety and environmental protection. Products are also regulated by Health Canada and the US-Food and Drug Administration (FDA). (author)

  2. Beneficial uses of radioisotopic waste program

    International Nuclear Information System (INIS)

    Activities include efforts to: (1) develop a cost-effective radioisotope separation technology based on column separation techniques associated with the Sandia Solidification Process and (2) develop a broader technology for beneficial applications of the separated isotopes, including engineered radioactive sources and applications facilities and/or devices, and studies related to cost-effectiveness, safety, and security of these sources, facilities, and devices. (LK)

  3. Alternate methods for the production of radioisotopes

    International Nuclear Information System (INIS)

    The use of radioisotopes for diagnostic and therapeutic clinical applications has increased in the past decade. The growth has been in two areas: the use of 99mTc for gamma-ray imaging and the use of 18F in positron emission tomography (PET). The 99mTc (6.01 h) is a daughter of the longer-lived precursor 99Mo (65.9 h), which is produced in nuclear reactors. Conversely, the isotopes for PET have been produced using cyclotrons at centralized hospital complexes. The economic potential of the radioisotope market has been demonstrated by the major producers of 99Mo this past year when they announced their plans to purchase two MAPLE reactors for the dedicated production of 99Mo. This market potential, coupled with the efforts by the U.S. Department of Energy to encourage the private, commercial production of radioisotopes that the government currently supplies, has provided motivation to investigate innovative technologies to produce both 99Mo and PET isotopes. Incentives for looking at alternate production methods include life-cycle cost and source portability for short-lived radioisotopes. This paper presents alternative production methods that could provide unique advantages for the production of 99Mo and tremendously higher availability of PET isotopes. We have examined the use of an existing high-current, linear accelerator for the production of 99Mo from the fission of depleted uranium and the production of short-lived isotopes used in PET using a portable source of low-energy antiprotons

  4. 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.)

  5. 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

  6. 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)

  7. Lanthanide doped strontium-barium cesium halide scintillators

    Science.gov (United States)

    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.

  8. 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

  9. 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.)

  10. 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

  11. Radioisotope applications on fluidized catalytic cracking units

    International Nuclear Information System (INIS)

    Radioisotopes are used to trace the flow of all the phases of Fluidized Catalytic Cracking process in oil refineries. The gaseous phases, steam, hydrocarbon vapour and air, are generally traced using a noble-gas isotope, 41Ar, 79Kr or 85Kr. An appropriate tracer for the catalyst is produced by irradiating a catalyst sample in a nuclear reactor. The activation products,140La and 24Na provide appropriate radioactive 'labels' for the catalyst, which is reinjected into the FCC. An advantage of this approach is that it facilitates the study of the behaviour of different particle size fractions. Radioisotopes as sealed sources of gamma radiation are used to measure catalyst density variations and density distributions in critical parts of the unit. An important trend in radioisotope applications is the increasing use of the information they produce as inputs to or as validation of, mathematical process models. In line with the increasing sophistication of the models, the technology is undergoing continuous refinement. Developments include the investigation of more efficient, more convenient tracers, the introduction of systems to facilitate more rapid and comprehensive data acquisition and software refinements for enhanced data analysis

  12. Analysis of mathematical models of radioisotope gauges

    International Nuclear Information System (INIS)

    Radioisotope gauges as industrial sensors were briefly reviewed. Regression models of instruments based on various principles developed in Institute of Nuclear Research and Institute of Nuclear Chemistry and Technology were analysed and their mathematical models assessed. It was found that for one - dimensional models the lowest value of standard error of estimate was achieved when calibration procedure was modelled by logarithmic function. Mathematical expressions for variance and mean value of intrinsic error for linear and non - linear one - as well as for multi - dimensional models of radioisotope gauges were derived. A conclusion was drawn that optimal model of calibration procedure determined by regression analysis method not always corresponds to the minimum value of the intrinsic error variance. Influence of cutting off of probability distribution function of measured quantity and its error at the lower upper limit of measurement range on variance and mean value of intrinsic error was evaluated. Feasibility study for application of some aspects of Shannon's information theory for evaluation of mathematical models of radioisotope gauges was accomplished. Its usefulness for complex evaluation of multidimensional models was confirmed. 105 refs. (author)

  13. 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.

  14. 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.

  15. 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.)

  16. 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.)

  17. Selective Removal Of Strontium And Cesium From Simulated Waste Solution With Titanate Ion-Exchangers In A Filter Cartridge Configurations-12092

    International Nuclear Information System (INIS)

    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.

  18. 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.

  19. 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)

  20. 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

  1. 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...

  2. 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.)

  3. 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

  4. 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.

  5. The law concerning prevention from radiation hazards due to radioisotopes

    International Nuclear Information System (INIS)

    The law regulates uses, sales and disposal of radioisotopes, uses of radiation generating apparatuses, disposal of materials contaminated with radioisotopes, and so on, in accordance with the Atomic Energy Fundamental Act, for public safety. Covered are the following: permission for and notification of the uses and permission for businesses selling and disposing of radioisotopes, and approval of designs concerning radiation hazard prevention mechanisms, obligations of the users and business enterprises selling and disposing of radioisotopes, the licensed engineers of radiation, organs, etc. for confirmation of the mechanisms, punitive provisions, and so on. (Mori, K.)

  6. Production and application of radioisotopes in Asian Countries

    International Nuclear Information System (INIS)

    Production and application of radioisotopes in some Asian countries including Bangladesh, India, Indonesia, Iran, Japan, Republic of Korea, Malaysia, Pakistan, Philippines, Thailand, Uzbekistan, and Viet Nam are introduced

  7. 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...

  8. 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.

  9. Ion and electron thermoemission of cesium alumosilicates

    International Nuclear Information System (INIS)

    Relationships between and electron thermoemission of cesium aluminosilicate were studied. Measurements were made at 5.10-8-5.10-9 Tor and temperatures up to 1400 deg C. The effect of additions refractory metals Ti, Mo, Cu and Ir was studied. Ion thermoemission in the pulse regime was also studied. Conclusions are drawn that capacity depends upon additions. The temperature dependence of thermoionic emission current has two maxima and is characterized by instability in time. A conclusion is drawn that aluminosilicate thermionic cathodes can be reckoned as cathodes of a film type

  10. Cesium-137 in grass from Chernobyl fallout

    International Nuclear Information System (INIS)

    Grass ecosystem was monitored for 137Cs, a relatively long-lived radionuclide, for about 16 years since the Chernobyl reactor accident occurred on April 26, 1986. Cesium-137 in grass gramineae or poaceae the species, ranged from 122.9 Bq kg-1 (September 4, 1986) to 5.8 mBq kg-1 (October 16, 2001) that is a range of five orders of magnitude. It was observed that there was a trend of decreasing 137Cs with time reflecting a removal half-time of 40 months (3 1/3 years), which is the ecological half-life, T ec of 137Cs in grassland

  11. 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

  12. 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.)

  13. Evaluation of electrochemical ion exchange for cesium elution

    International Nuclear Information System (INIS)

    Electrochemical elution was investigated as an alternative method to acid elution for the desorption of cesium from loaded ion exchange resins. The approach was found to have several potential advantages over existing technologies, in particular, electrochemical elution eliminates the need for addition of chemicals to elute cesium from the ion exchange resin. Also, since, in the electrochemical elution process the eluting solution is not in direct contact with the ion exchange material, very small volumes of the eluting solution can be used in a complete recycle mode in order to minimize the total volume of the cesium elute. In addition, the cesium is eluted as an alkaline solution that does not require neutralization with caustic to meet the tank farm specifications. Other advantages include easy incorporation of the electrochemical elution process into the present cesium recovery schemes

  14. 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

  15. 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

  16. 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.

  17. 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)

  18. The uses of radioisotope gauges in industry

    International Nuclear Information System (INIS)

    A radioisotope gauge consists basically of a sealed radioisotope source of radiation, a detector, and an electronic indicating unit for visually displaying the detector output. The degree of absorption or scattering of the radiation by a material, as measured with the detector, is used to measure properties such as thickness, density, composition and level; the different instruments being named after the property being determined, e.g. thickness gauge or level gauge. Depending on whether the source and detector are on the same or opposite sides of the material, the instruments are known as backscatter or transmission instruments respectively. They are further classified according to the type of radiation used, e. g. beta transmission thickness gauge or gamma backscattering density gauge. The physical properties which can be determined are: (a) Thickness, or mass per unit area, of homogeneous sheet materials such as aluminium or steel or of heterogeneous materials of constant composition such as paper or plastic; (b) Coating thickness, such as paper or textiles coated with rubber, plastic or abrasives; (c) Plating thickness, such as tin on steel; (d) Density of materials of constant thickness, such as liquids or slurries in a pipe, or of tobacco, in cigarettes; (e) Levels of solids or fluids in containers; (f) Elemental composition of certain materials; (g) Density of materials in large bulk, such as concrete, soil or rock strata. In addition to the above, the instruments are also used for such varied purposes as pressure gauges, flowmeters, torquemeters and as position indicators. Radioisotopes became available in quantity around 1947 from nuclear reactors and the first beta transmission thickness gauges were installed on paper mills about 1949

  19. Recent progress in radioisotope production in Vietnam

    International Nuclear Information System (INIS)

    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 131I, 99Mo-99mTc, 32P, 51Cr, 153Sm, 46Sc, 192Ir was produced annually. Radiopharmaceuticals such as 131I-Hippuran and in-vivo Kits for 99mTc 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 131I 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 99mTc generators using low power research reactors. Gel technology using Zr- and Ti- molybdate gel columns for 99mTc generator production was developed and improved continually. Portable 99mTc generator using Zr-(99Mo) molybdate gel column and ZISORB adsorbent column for 99mTc concentration were developed. The ZISORB adsorbent of high adsorption capacity for 99Mo and other parent radionuclides was also studied for the development purpose of alternative technology of 99mTc and other different radionuclide generator systems. The studies on the preparation of therapeutic radiopharmaceuticals labelling with 153Sm and 131I such as 153Sm-EDTMP, 131I-MIBG were carried out. (author)

  20. A new radioisotope facility for Thailand

    International Nuclear Information System (INIS)

    The Thai Office of Atomic Energy for Peace (OAEP) is planning a new Nuclear Research Centre which will be located at Ongkharak, a greenfield site some 100 km North of Bangkok. General Atomics (GA) has submitted a bid for a turnkey contract for the core facilities comprising a Reactor to be supplied by GA, an Isotope Production Facility supplied by ANSTO and a Waste Processing and Storage Facility to be supplied by Hitachi through Marubeni. The buildings for these facilities will be provided by Raytheon, the largest constructor of nuclear facilities in the USA. The proposed Isotope Facility will consist of a 3000 m2 building adjacent to the reactor with a pneumatic radioisotope transfer system. Hot cells, process equipment and clean rooms will be provided, as well as the usual maintenance and support services required for processing radiopharmaceutical and industrial products. To ensure the highest standards of product purity the processing areas will be supplied with clean air and operated at slightly positive pressure. The radioisotopes to be manufactured include Phosphorus 32 (S-32 [n,p]P-32), I-131(Te-130 [n,g]Te-131[p]I-131) for bulk, diagnostic capsules and therapeutic capsules, Iridium 192 (Ir-191[n,g]Ir-192) wire for radiotherapy and discs for industrial radiography sources and bulk Iodine 125 (Xe-124[n,g]Xe-125[β]I-125 for radioimmunoassay. The bid includes proposals for training OAEP staff during design and development at ANSTO's radioisotope facilities, and during construction and commissioning in Thailand. The entire project is planned to take four years with commencement anticipated in early 1997. The paper will describe the development of the design of the hot-cells, process equipment, building layout and ventilation and other services

  1. 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)

  2. 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)

  3. List of DOE radioisotope customers with summary of radioisotope shipments FY 1978

    International Nuclear Information System (INIS)

    The purpose of the document is to list DOE's radioisotopes 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; Savannah River Laboratory; and UNC Nuclear Industries, Inc

  4. Experience on radioisotope waste management in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; Ju, Jun Sik; Kim, Chong Hyun; Lee, Byung Jik; Park, Hun Hwee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    1991-07-01

    The number of institutions using radioisotopes (RI) is almost 800 in total and among them RI waste is generated from 496 institutions, mainly hospitals. The amount of waste to be collected is estimated to be about 800 drums per year. Waste storage and treatment facility are scheduled to be constructed within 1991 through the licensing procedure. Treatment equipment for compaction and solidification are designed and manufactured by the domestic technology. Other related equipment such as drums for collection and transportation vehicle are prepared. RI wastes from hospitals and research institutions have been collected on a trial basis since Aug. 28, 1990.

  5. 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)

  6. Radioisotope Thermoelectric Generator Transport Trailer System

    International Nuclear Information System (INIS)

    The Radioisotope Thermoelectric Generator (RTG) Transportation System, designated as System 100, comprises four major systems. The four major systems are designated as the Packaging System (System 120), Trailer System (System 140), Operations and Ancillary Equipment System system 160), and Shipping and Receiving Facility Transport System (System 180). Packaging System (System 120), including the RTG packaging is licensed (regulatory) hardware; it is certified by the US Department of Energy to be in accordance with Title 10, Code of federal Regulations, Part 71 (10 CFR 71). System 140, System 160, and System 180 are nonlicensed (nonregulatory) hardware

  7. Experience on radioisotope waste management in Korea

    International Nuclear Information System (INIS)

    The number of institutions using radioisotopes (RI) is almost 800 in total and among them RI waste is generated from 496 institutions, mainly hospitals. The amount of waste to be collected is estimated to be about 800 drums per year. Waste storage and treatment facility are scheduled to be constructed within 1991 through the licensing procedure. Treatment equipment for compaction and solidification are designed and manufactured by the domestic technology. Other related equipment such as drums for collection and transportation vehicle are prepared. RI wastes from hospitals and research institutions have been collected on a trial basis since Aug. 28, 1990

  8. Radioisotope hepatography in patients with chronic bronchitis

    International Nuclear Information System (INIS)

    Examination carried out by means of radioisotope hepatography with bengal-rose-iodine 131 in 69 patients with chronic obstructive bronchitis associated with respiratory insufficiency of grades 1, 2, 3 at the phase of remission revealed disturbances of the absorptive-excretory function of the liver. A direct dependence was found between the intensity of disorder of the functionsl state of parenchymatous cells and degree of resperatory insufficiency in this category of patients. The disorders of the absorptive-excretory function of the liver were most pronounced in respiratory insufficiency of grade 3

  9. 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.

  10. 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

  11. Studies on release and deposition behaviour of cesium from contaminated sodium pools and cesium trap development for FBTR

    International Nuclear Information System (INIS)

    Investigations were carried out on the release and deposition behaviour of cesium from sodium pools in air-filled chamber in the temperature range of 673 to 873 K, using Cs-134 to simulate Cs-137. About 0.12 kg of sodium was loaded in a burn-pot together with 92.5 kBq of cesium. Experiments were carried out with 21% oxygen. Natural burning period of sodium and specific activity ratio between cesium and sodium showed a tendency to decrease and release fractions of both the species tended to increase with temperature. From the surface deposited aerosols it was observed that cesium has propensity to settle down closer to the point of release. A cesium trap has been developed for FBTR with RVC as getter material. Absorption kinetics and particle release behaviour studies pointed to its intended satisfactory performance in the plant. (author)

  12. 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

  13. 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

  14. 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

  15. Cesium separation Using Electrically Switched Ion Exchange

    International Nuclear Information System (INIS)

    Electrically Switched Ion Exchange (ESIX) is a separation technology being developed at Pacific Northwest National Laboratory as an alternative to conventional ion exchange for removing metal ions from wastewater. In ESIX, which combines ion exchange and electro-chemistry, ion uptake and elution can be controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto an electrode. This paper presents the results of experiments on high surface area electrodes and the development of a flow system for cesium ion separation. Bench-scale flow system studies showed no change in capacity or performance of the ESIX films at a flow rate up to 113 BV/h, the maxi-mum flow rate tested, and breakthrough curves supported once-through waste processing. A comparison of results for a stacked 5-electrode cell versus a single-electrode cell showed enhanced breakthrough performance. In the stacked configuration, break-through began at about 120 BV for a feed containing 0.2 ppm cesium at a flow rate of 13 BV/h. A case study for the KE Basin (a spent nuclear fuel storage basin) on the Hanford Site demonstrated that KE Basin wastewater could be processed continuously with minimal waste generation, reduced disposal costs, and lower capital expenditures

  16. 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

  17. 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)

  18. 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.

  19. 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.

  20. Renal function studies with radioisotopes: an appraisal

    International Nuclear Information System (INIS)

    The use of radioisotopes in renal disorders has grown out of the development of scintillation detectors and gamma cameras and the availability of appropriate radioactive pharmaceuticals. It is now time to approach these studies from a different point of view. What further information would the practising nephrologist or urologist, physician or surgeon like to know about patients' kidney function that is not easily obtainable by non-radioactive methods. He would like a simple and reliable measurement of individual renal function; a test to demonstrate the presence or absence of obstruction in a patient with oliguria or uraemia; some help as to whether nephrectomy or a more difficult restorative operation is better for the patient with hydronephrosis, calculus or renal artery stenosis; a measure of the degree to which an obstructive uropathy is causing an obstructive nephropathy; clarification of which kidney to operate upon first when bilateral obstructive nephropathy presents with uraemia; a quantitative index of the progress following an operation to relieve an outflow system disorder; a screening procedure for renal disorders in the hypertensive and other populations; a prognostic guide to the likely evolution of glomerulonephritis and pyelonephritis, a prediction of the onset of rejection in the renal transplant, particularly in the presence of acute tubular necrosis. This review attempts to define the extent to which renal function studies with radioisotopes meet or fail to meet these needs and to indicate areas for potential development. (author)

  1. Medical research with radioisotopes in Greece

    International Nuclear Information System (INIS)

    An important program of research into the nature and causes of congenital haemolytic anaemias, notably the disease known as Mediterranean anaemia or Thalassaemia, which is a serious medical problem in the Mediterranean countries, is at present being carried out in the Department of Clinical Therapeutics of the University of Athens under a research contract awarded by the International Atomic Energy Agency. This program is concerned with diseases in which there is an inherited defect or abnormality in the production of haemoglobin, the iron-containing pigment of the red blood cells which is responsible for the carriage of oxygen in the blood. Two techniques have been widely used in the studies at the University of Athens. In the first of these, a radioisotope of iron, iron-59, is used to follow iron metabolism and haemoglobin production. Iron metabolism in the body is concerned largely with the synthesis and breakdown of haemoglobin, which consists of a protein, globin, linked to an iron containing substance, haeme. The second technique makes use of a radioisotope of chromium, chromium-51, to study the fate of the red cells in the blood. By performing simultaneous studies with iron- 59 and chromium-51, a detailed picture of haemoglobin synthesis and red cell production and destruction can be built up. Such investigations have been invaluable in establishing the characteristic patterns of different congenital haemolytic anaemias

  2. A Hydraulic Transfer System for Producing Radioisotopes

    International Nuclear Information System (INIS)

    Research reactors are constructed mainly for producing radioisotopes, neutron beams and neutron irradiation research and so on. The research reactors generally have two separate area; one is the reactor area and the other is the radioisotopes (RI) production area. After various irradiation objects are irradiated in the reactor located in the reactor area, they are transferred to the RI production building for post-processing. The Hydraulic Transfer System (HTS) is one of RI production and utilization facilities of a research reactor. The HTS is for irradiating targets in the reactor core, and targets are transferred through pipes by hydraulic force. A similar system can be seen in other research reactor such as FRM II, JMTR, HFIR, etc. There are two parallel open-loops used to irradiate targets, and the HTS will circulate pool water to load/unload targets into/from the irradiation tubes and cool targets during irradiation. This paper contains the introduction and operation of the HTS. The HTS permits instantaneous irradiation activity during the reactor operation. It contributes to the RI production and utilization for public welfare, industrial applications and research areas

  3. 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

  4. 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.

  5. A Hydraulic Transfer System for Producing Radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Joonho; Lee, Sangjin; Lee, Chungyoung; Lee, Jongmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Research reactors are constructed mainly for producing radioisotopes, neutron beams and neutron irradiation research and so on. The research reactors generally have two separate area; one is the reactor area and the other is the radioisotopes (RI) production area. After various irradiation objects are irradiated in the reactor located in the reactor area, they are transferred to the RI production building for post-processing. The Hydraulic Transfer System (HTS) is one of RI production and utilization facilities of a research reactor. The HTS is for irradiating targets in the reactor core, and targets are transferred through pipes by hydraulic force. A similar system can be seen in other research reactor such as FRM II, JMTR, HFIR, etc. There are two parallel open-loops used to irradiate targets, and the HTS will circulate pool water to load/unload targets into/from the irradiation tubes and cool targets during irradiation. This paper contains the introduction and operation of the HTS. The HTS permits instantaneous irradiation activity during the reactor operation. It contributes to the RI production and utilization for public welfare, industrial applications and research areas.

  6. Safe Handling of Radioisotopes. Health Physics 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 technical information necessary for the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the technical 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.

  7. Rhenium radioisotopes for therapeutic radiopharmaceutical development

    International Nuclear Information System (INIS)

    Rhenium-186 and rhenium-188 represent two important radioisotopes which are of interest for a variety of therapeutic applications in oncology, nuclear medicine and interventional cardiology. Rhenium-186 is directly produced in a nuclear reactor and the 90 hour half-life allows distribution to distant sites. The relatively low specific activity of rhenium-186 produced in most reactors, however, permits use of phosphonates, but limits use for labelled peptides and antibodies. Rhenium-188 has a much shorter 16.9 hour half-life which makes distribution from direct reactor production difficult. However, rhenium-188 can be obtained carrier-free from a tungsten-188/rhenium-188 generator, which has a long useful shelf-life of several months which is cost-effective, especially for developing regions. In this paper we discuss the issues associated with the production of rhenium-186- and rhenium-188 and the development and use of various radiopharmaceuticals and devices labelled with these radioisotopes for bone pain palliation, endoradiotherapy of tumours by selective catheterization and tumour therapy using radiolabelled peptides and antibodies, radionuclide synovectomy and the new field of vascular radiation therapy. (author)

  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. Production of Short-Lived Radioisotopes

    International Nuclear Information System (INIS)

    A review is made of the current literature and a bibliography given. Selected references are cited and comment made on the general techniques currently employed by short-lived radioisotope producers. A distinction is drawn between the large centrally-local high flux reactors and local reactors for producing short-lived radioisotopes; the complementary role of the two is pointed out as, for example, the need for obtaining very high specific activities in special off-site reactors or the need for high-speed transfers and fast processing in local reactors. The equipment and procedures used for irradiating target materials to produce short-lived radioisotopes in the three routinely-operated ORNL reactors are described, as well as those for the High Flux Isotope Reactor (HFIR) now under construction at ORNL, which will have a maximum flux of 5 x 1015 n/cm2s. The use of the HFIR will permit production of certain short-lived radioisotopes of unprecedented specific activity. Techniques that have been developed for irradiating samples in various kinds of reactors ranging from the 1012n/cm2 s air-cooled, graphite reactor to the high flux (1014 - 1016) water-cooled, enriched uranium reactors are described. The requirements for sample irradiations in the various kinds of reactors, such as material, method of sealing, handling, method of heat removal, and kinds of sample materials, are discussed. Pneumatic transfer tubes are used for irradiations where cooling requirements are not great and fast transfer is desired. Hydraulic tubes are used for irradiation of samples with greater heat generation, although the speed of transfer is not as great as with the pneumatic tubes. The advantages in using enriched target materials in certain cases are pointed out and several illustrations are given. In some cases, where die target nuclide occurs in low abundance, such as Ca46 in calcium (0.003%), great advantage can be obtained by using enriched target materials. This may be of importance

  10. 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)

  11. The use of radioisotope tracers in the metallurgical industries

    International Nuclear Information System (INIS)

    Radioisotope techniques have been widely used in the metallurgical industries for many years. They have been shown to be very suitable for studying large scale plant and, in many cases, they are the most suitable techniques for such investigations. Applications of radioisotope tracers to some specific metallurgical problems are discussed. (author)

  12. Radioisotope-thermographic studies in patients with breast tumors

    International Nuclear Information System (INIS)

    The paper provides an analysis of the results of concomitant radioisotope-thermographic studies of 152 patients with malignant and benign breast tumors. The efficacy of concomitant radioisotope- thermographic studies in breast tumor diagnosis was evaluated. The efficacy of chemo- and radiotherapy was also evaluated

  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. Production and application of radioisotopes and radiopharmaceuticals - status and prospects

    International Nuclear Information System (INIS)

    Given are the main data on the use of radioisotopes and radiopharmaceuticals for nuclear medical applications. Shown are the methods for their routine production including the results obtained in the Laboratory for Radioisotopes (Vinca Institute of Nuclear Sciences). Particular emphasis is devoted to the trends in the development of the agents suitable for specific diagnostic or therapeutic applications. (author)

  16. Assessment of radioisotope heaters for remote terrestrial applications

    International Nuclear Information System (INIS)

    This paper examines the feasibility of using radioisotope byproducts for special heating applications at remote sites in Alaska and other cold regions. The investigation included assessment of candidate radioisotope materials for heater applications, identification of the most promising cold region applications, evaluation of key technical issues and implementation constraints, and development of conceptual heater designs for candidate applications. Strontium-90 (Sr-90) was selected as the most viable fuel for radioisotopic heaters used in terrestrial applications. Opportunities for the application of radioisotopic heaters were determined through site visits to representative Alaska installations. Candidate heater applications included water storage tanks, sludge digesters, sewage lagoons, water piping systems, well-head pumping stations, emergency shelters, and fuel storage tank deicers. Radioisotopic heaters for water storage tank freeze-up protection and for enhancement of biological waste treatment processes at remote sites were selected as the most promising applications

  17. 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

  18. 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

  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. 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)

  2. 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

  3. Development of radioisotopes and radiation sources

    International Nuclear Information System (INIS)

    The purpose of this project is to develop RI production technology utilizing HANARO and to construct a sound infra-structure for mass production and supply to domestic users. The Ir-192 NDT sources of more than 50 Ci, equivalent in activity, are now available in KAERI and covers more than 90 % of the nationwide demand. For the commercial supply of Ir-192 industrial source, we developed irradiation target for mass-production and automatic fabrication system. The developed IR-Rigs have been used in production of various radioisotope and radiation sources in IR 1, 2 and CT irradiation holes. A Loop-Batch system for the mass-production of I-125 has been developed and tested its reliability and safety.The separation of I-125 formed from irradiated xenon gas was performed by column chromatographic technique using platinum coated on copper(PCC) granules as an adsorbent. For the preparation of I-125 seed, the retention of iodine on a ceramic rod coated with silver nitrate as an iodine absorbent was studied. The production possibility of Sr-89 using 89Y(n,p) and 88Sr(n,γ) in HANARO has been estimated. A new distillation process for P-33 production has been developed and applied for production of P-32. The current status of W-188/Re-188 generator production technology were reviewed. Main interests were given to the aspects of W-188 reactor production, irradiated targets reprocessing and generator loading technologies, such as alumina type and gel type generators. To develop the Yb-169 radiographic sources for industrial NDT application, molding machine which can apply fabrications of small pellets with various size and shapes was designed and manufactured. Automatic welding system and assembly technologies for Co-60 source fabrication were developed. The developed HDR Ir-192 source was tested for application in Microselectron [32P] γ - ATP has been developed using [32P] phosphoric acid produced by KAERI. Calibration sources for correcting of energy and detection efficiency

  4. 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)

  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. 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

  7. Double manganese(III) cesium triphosphate

    International Nuclear Information System (INIS)

    Double triphosphates have been identified in research on interactions in the P2O5-M2O3-Cs2O-H2O system, where M(III) = Al, Ga, Cr, Fe, at 570-770K, which have the M(III)Cs2 - P3O10 composition; here we report the identification of a new phase made under analogous conditions in a system containing Mn(III) together with some of its physicochemical properties. The product was analyzed for phosphorus by a colorimetric method, for manganese by titration with EDTA, and for cesium by atomic absorption. The x-ray phase analysis was performed with a DRON-3.0 diffractometer. The IR spectra were recorded. Thermogravimetry indicates that the product is MnCs2P3O10·H2O

  8. Radioisotopes and radiopharmaceuticals in nuclear cardiology

    International Nuclear Information System (INIS)

    Nuclear medicine studies of the heart represent one of the fastest growing areas of research and clinical interest. Some years ago, nuclear medicine cardiac studies were limited to the evaluations of myocardial infraction. Developments in radiopharmaceuticals chemistry and instrumentation have made possible advances in cardiovascular nuclear medicine. Techniques and Radiopharmaceuticals no exist for the imaging of viable myocardium and the determination of myocardial tissue metabolism, as well as radionuclide angiography to obtain quantitative information of cardiac output, mean transit times, cardiac volumes, and ejection fractions. This paper will firstly describe that anatomy and physiology of the heart as to relate to the radiopharmaceuticals which will be discussed, and will secondly explore various radiopharmaceuticals which have been used for various purposes in cardiac imaging, than will explore radioisotopes which have been proposed for myocardial treatment

  9. Radioisotope heaters for spacecraft life support systems

    International Nuclear Information System (INIS)

    Future manned space flight requires the sanitary collection and disposal of biological wastes to minimize microbial contamination hazard. The recovery and reuse of water from such wastes are also necessary to reduce the weight of vehicles at launching and resupply logistics. The development and test of an engineering model, i.e. the completely integrated waste management-water system using radioisotopes for thermal energy, are described. This is capable of collecting and processing the wastes from four men during 180-day simulated space mission. The sub-systems include collection of feces, trash and urine, water reclamation, the storage, heating and dispensing of the water, and the disposal of feces, urine residue and other non-metallic waste material by incineration. (Mori, K.)

  10. 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)

  11. 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.

  12. Current status of radio-isotopes utilization

    International Nuclear Information System (INIS)

    Utilization of radioisotopes were reviewed briefly in a categorized manner. In plant biochemistry, long lived radioactive carbon ,14C, was applied to clarify such metabolic processes as photosynthesis, respiration and protein synthesis, etc., while radioactive oxygen ,18O, was used to study the O2 generation mechanism. Radioactive phosphorus ,32P, was used to detect the amount, grain size of phosphatic fertilizer as well as the time and depth for better utilization. Radioactive sulphur ,35S, and nitrogen ,15N, could be of use in studies of protein metabolism in plants. Radioactive tracers of other minerals such as N, P, K, Ca, Mg, Zn, Mo, B, and Co were also used to detect their specific role in plants. Use of radioactive isotopes in protein synthesis and transfer of genetic information was described. Radioactive iodine ,131I, binding capacity of milk proteins, and radio trace studies in the iodine turn over in the use of radioactive iodine were summarized. (Mukohata, S.)

  13. 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

  14. Microbiological quality control practices at Australian Radioisotopes

    International Nuclear Information System (INIS)

    As a domestic manufacturer of therapeutic substances, Australian Radioisotopes (ARI) must adhere to guidelines set out by the Commonwealth Department of Health in the Code of Good Manufacturing Practices for Therapeutic Goods 1983 (GMP). The GMP gives guidelines for staff training, building requirements, sanitation, documentation and quality control practices. These guidelines form the basis for regular audits performed by officers of the National Biological Standards Laboratories. At Lucas Heights, ARI has combined the principles of the GMP with the overriding precautions introduced for environmental and staff safety and protection. Its policy is to maintain a high level of quality assurance for product identity, purity and sterility and apyrogenicity during all stages of product manufacture

  15. 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.

  16. 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

  17. Performance tuned radioisotope thermophotovoltaic space power system

    International Nuclear Information System (INIS)

    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 ampersand 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

  18. List of ERDA radioisotope customers with summary of radioisotope shipments FY 1977 (plus the transition quarter)

    International Nuclear Information System (INIS)

    The thirteenth edition of the radioisotope customer list gives ERDA's (now DOE) FY-1977 and transition quarter 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 Laboratory; Oak Ridge National Laboratory; Savannah River Laboratory; and United Nuclear Industries, Inc. The information is divided into four sections. Sect. I is an alphabetical list of domestic and foreign customers and their addresses. Sect. II is an alphabetical list of isotopes that are cross-referenced to customer numbers and divided into the domestic and foreign categories. Sect. III is an alphabetical list of states and countries, and is also cross-referenced to customer numbers, indicating geographical concentrations of isotope users. Sect. IV summarizes the FY-1977 radioisotope shipment activities of laboratories in a comprehensive table providing an alphabetical listing of the isotopes and their suppliers. The shipments, quantities, and dollars are broken down for each isotope under the domestic, foreign, and project (ERDA facilities) categories, and the total figures for each isotope are also provided

  19. 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)

  20. 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.

  1. 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)

  2. 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

  3. 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.

  4. 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)

  5. 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.)

  6. Future radioisotope power needs for missions to the solar system

    International Nuclear Information System (INIS)

    NASA and DOE plan a cooperative team effort with industry, government laboratories and universities to develop a near term, low cost, low power (100 watt electric class), low mass (<10 kg), advanced radioisotope space power source (ARPS) and in the process reduce the plutonium-related costs as well. The near term is focused on developing an advanced energy converter to use with the General Purpose Heat Source (GPHS). The GPHS was developed and used for the current radioisotope thermoelectric generators (RTGs). Advanced energy converter technologies are needed as a more efficient replacement for the existing thermoelectric converters so that the space radioisotope power source mass and cost can be reduced. a more advanced technology space radioisotope power system program is also planned that addresses a longer-term need. Twenty first century robotic scientific information missions to the outer planets and beyond are planned to be accomplished with microspacecraft which may demand safe, even more compact, lower-power, lower-mass radioisotope power sources than those which can be achieved as a result of the near term efforts. The longer-term program focuses not only on converter technology but also on lower power, more compact radioisotope heat source technology and smaller, lower mass radioisotope heater units for second generation microspacecraft. This more ambitious, longer time-horizon focus necessarily occurs at this time on the technology R and D level rather than at the system technology level

  7. Low-work-function surfaces produced by cesium carbonate decomposition

    Science.gov (United States)

    Briere, T. R.; Sommer, A. H.

    1977-01-01

    Cesium carbonate (Cs2CO3) was heated to the decomposition temperature of approximately 600 C. The nonvolatile decomposition products were condensed on a nickel substrate while the carbon dioxide was removed by pumping. The deposited material is characterized by an effective work function of between 1.05 and 1.15 eV at 450 K and by photoemission in the visible and near-infrared region of the spectrum. It is suggested that the deposited material consists of Cs2O, possibly Cs2O2, and adsorbed cesium. Silver, evaporated from a heated silver bead, produced the typical photoemissive and thermionic properties of a silver-oxygen-cesium (S-1) photocathode. The material may be of interest for thermionic energy converters and for the formation of silver-oxygen-cesium photocathodes.

  8. 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

  9. Cesium iodide crystals fused to vacuum tube faceplates

    Science.gov (United States)

    Fleck, H. G.

    1964-01-01

    A cesium iodide crystal is fused to the lithium fluoride faceplate of a photon scintillator image tube. The conventional silver chloride solder is then used to attach the faceplate to the metal support.

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

    International Nuclear Information System (INIS)

    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 10-8 and 10-3 mol/l. The distribution coefficients of the sorption, Rd and Ra 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.)

  11. 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.

  12. Cesium pre-implantation of embedded biological sections

    International Nuclear Information System (INIS)

    An ion implantation system which allows the implantation of a large surface of a specimen has been used to obtain an homogeneous enrichment with cesium of embedded biological tissues sections. In such a specimen, containing already oxygen at a high concentration, the addition of cesium allows both positive and negative secondary ions to be studied with the highest sensitivity, using the same primary ion source.

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

    OpenAIRE

    Wisniewski, Eric; Velazquez, Daniel; 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 incl...

  14. 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 ...

  15. 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)

  16. Trends in indigenous radioisotope and radiopharmaceutical production in Bangladesh

    International Nuclear Information System (INIS)

    The Radioisotope Production Division (RIPD) of the Institute of Nuclear Science and Technology started producing radioisotopes for medical use in 1987, as soon as the 3 MW TRIGA Mark-II research reactor started operation. There are 17 nuclear medicine centres in Bangladesh and the RIPD partially meets domestic demand for medical radioisotopes, the balance being imported. The RIPD routinely produces 131I solution and 99mTc generator and from October 2005 it was scheduled to substitute the import of these items by indigenous production. The RIPD is planning to establish a 99mTc cold kit manufacturing facility by 2007-2008. (author)

  17. Radioisotope Reduction Using Solar Power for Outer Planetary Missions

    Science.gov (United States)

    Fincannon, James

    2008-01-01

    Radioisotope power systems have historically been (and still are) the power system of choice from a mass and size perspective for outer planetary missions. High demand for and limited availability of radioisotope fuel has made it necessary to investigate alternatives to this option. Low mass, high efficiency solar power systems have the potential for use at low outer planetary temperatures and illumination levels. This paper documents the impacts of using solar power systems instead of radioisotope power for all or part of the power needs of outer planetary spacecraft and illustrates the potential fuel savings of such an approach.

  18. 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

  19. Study of strontium and cesium migration in fractured crystalline rock

    International Nuclear Information System (INIS)

    The purpose of this investigation has been to study the retardation and dilution of non-active strontium and cesium relative to a non-absorbing substance (iodide) in a well-defined fracture zone in the Finnsjoen field research area. The investigation was carried out in a previously tracer-tested fracture zone. The study has encompassed two separate test runs with prolonged injection of strontium and iodide and of cesium and iodide. The test have shown that: - Strontium is not retarded, but rather absorbed to about 40% at equilibrium. - At injection stop, 36.3% of the injected mass of strontium has been absorbed and there is no deabsorption. -Cesium is retarded a factor of 2-3 and absorbed to about 30% at equilibrium. - At injection stop, 39.4% of the injected mass of cesium has been absorbed. Cesium is deabsorbed after injection stop (400h) and after 1300 hours, only 22% of the injected mass of cesium is absorbed. (author)

  20. 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.

  1. A power conditioning system for radioisotope thermoelectric generator energy sources

    Science.gov (United States)

    Gillis, J. A., Jr.

    1974-01-01

    The use of radioisotope thermoelectric generators (RTG) as the primary source of energy in unmanned spacecraft is discussed. RTG output control, power conditioning system requirements, the electrical design, and circuit performance are also discussed.

  2. 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...

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

    International Nuclear Information System (INIS)

    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, γ-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, 90Y, 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)

  4. Investigation of natural radioisotope activities in forest soil horizons

    International Nuclear Information System (INIS)

    Activities of radioisotopes were measured in samples of forest soil. The samples were collected in forests situated along the roads from Zloty Stok (Poland) to Hradec Kralove (Czech Republic). Each soil profile was separated into individual horizons and subhorizons. Activities of radioisotopes were measured in the sample of each soil horizon. Activities of the following radioisotopes were determined by gamma-ray spectrometry: 214Pb, 214Bi, 231Th, 235U, 212Pb, 212Bi and 228Ac. Distributions of the data concerning radioactivities were positively skewed. The lowest activity was found for 235U (median value was 2.25 Bq/kg) and the highest one for 228Ac (16.26 Bq/kg in median). In organic horizons activities of radionuclides were lower than in organic ones. Interrelation between activities was examined using ordinary and robust regression methods. It was found that activities of the radioisotopes were well correlated. (authors)

  5. 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

  6. Synthesis and characterization of coordination polymer nanoparticles as radioisotope tracers

    International Nuclear Information System (INIS)

    Coordination polymer nanoparticles (NPs) with gamma-emitting nuclide (Au-198), 411 keV, 675 keV, 822 keV and 1087 keV were prepared by coordination polymerization of the radioisotope Au3+ ions and 1,4-bis(imidazole-1-ylmethyl)benzene in an aqueous solution at room temperature for 3 h. Here, the radioisotope Au3+ ions were prepared by dissolution of Au-198 foil, which was prepared by neutron irradiation from the HANARO reactor, in KCN aqueous solution. The successful synthesis of the radioisotope coordination polymer NPs with 5±0.5 nm was confirmed via UV–vis spectroscopy, Transmission Electron Microscopy (TEM), Energy Dispersive X-ray Spectrometry (EDXS), Thermogravimetric analysis (TGA), and Gamma spectroscopy analysis. The synthesized radioisotope coordination polymer NPs can be used as radiotracers in science, engineering, and industrial fields

  7. Determining Molar Combining Ratios Using Radioisotopes--A Student Experiment

    Science.gov (United States)

    Sears, Jerry A.

    1976-01-01

    Outlines an experimental procedure in which an iodine radioisotope is used to determine molar combining ratios of lead and silver with the iodine. Tables and graphs show the definitive results that should be attainable. (CP)

  8. 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

  9. Dose mapping experiments of refurbished cesium irradiator

    International Nuclear Information System (INIS)

    Full text: Cesium irradiator is a technology demonstration facility for irradiation of food commodities to achieve various purposes like control of sprouting in onion and potato, insect disinfestations of cereals and pulses, quarantine treatment of fresh fruits and vegetables and shelf life extension of perishable foods. The facility was installed in 1968 and recently refurbished with the new control console. The current source strength (137Cs) of the irradiator is 44.3 kCi. The real success of irradiation of food commodities lies in the adequate delivery of radiation dose to achieve the particular purpose of irradiation. Therefore, evaluation of dose distribution pattern in the product trays of the irradiation facility is of paramount importance. Two sets of dose mapping experiments of the product trays of the facility were carried out to find out the dose distribution profile and dose uniformity ratio. Reference standard dosimeter Fricke was used for the experiment. The standardized ionic concentrations of Fricke dosimeter are Ferrous Ammonium Sulphate (FeSO4(NH4)2SO4 6H2O ) - 1 mM, Sodium Chloride (NaCl) - 1 mM, Sulphuric acid (H2SO4) - 400 mM. The Optical Density (O.D) evaluation was carried out using Spectrophotometry with wave length of 304 nm. The dosimetry tray was partitioned into two planes namely bottom plane and top plane using card-board sheets. Polypropylene vials containing Fricke solution were prepared and fixed on the planes. Each plane was containing nine numbers of dosimeters. The product thickness was around 9 cm. The temperatures of irradiation and measurements were 30 deg C and 28 deg C respectively. The first set of experiment was intended to find out the dose distribution profile throughout the irradiation chamber. The dose rate at Dmin position was observed as 3.69 Gy/min with a poor Dose Uniformity Ratio (DUR) of 6.5. In order to improve the dose rate and DUR the second set of the experiment was carried out with modified product geometry

  10. Cores of production : reactors and radioisotopes in France

    OpenAIRE

    Adamson, Matthew

    2009-01-01

    This paper concerns the technologies used in radioisotope production in the French Atomic Energy Commission (the Commissariat à l’Energie Atomique) between 1946 and 1958. Particular attention is given to the various instruments used for the bombardment of isotopes, including accelerators and reactors, and their relationship with the CEA’s radioisotope preparation laboratories. Ultimately, the vast majority of bombardments took place in research reactors. These versatile machines, and the isot...

  11. Legal regulations governing workplace monitoring in radioisotope laboratories

    International Nuclear Information System (INIS)

    Legal regulations governing workplace monitoring in radioisotope laboratories are presented and compared on the basis of the West German and Swiss Radiation Protection Ordinances and the pertinent EC standards. The following subjects are covered: Application of the fundamentals of radiation protection; requirements to be met for licenses to handle radioisotopes; classification of monitored areas; requirements on radiation monitoring. The possible consequences of the new ICRP recommendations are discussed. (orig.)

  12. Development of a auto-loading system for radioisotope liquor

    International Nuclear Information System (INIS)

    A loading system with computer distant control for radioisotope liquor is developed. It's arm to avoid close operating to the radioactive in the radioisotope liquor. Microcontroller is used as control center, step motor and peristaltic pump as manipulator in this system. The product process is performed with real-time measurement and control. The system has many function including data storage, data query, printing, operator information management, et al. (authors)

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

    OpenAIRE

    Neilly, Brian; Allen, Sarah; 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 representative...

  14. The safe use of radioisotopes in South Africa

    International Nuclear Information System (INIS)

    This article is given a general look on the safe use of radioisotopes in South Africa. This include general information on the history and applications of radioisotopes. The main development of industrial nuclear techniques has been in the use of radioactive tracers for process dynamics studies. Nuclear techniques for elemental analysis have also been used successfully in the monitoring of those mining and industrial processes where concentration of specific elements are needed as control parameters

  15. KAERI's challenge to steady production of radioisotopes and radiopharmaceuticals

    International Nuclear Information System (INIS)

    The Korea Atomic Energy Research Institute (KAERI) is a national organization in Korea, and has been doing many research and development works in radioisotope production and applications for more than 30 years. Now KAERI regularly produces radioisotopes (I-131, Tc-99m, Ho-166) for medical use and Ir-192 for industrial use. Various I-131 labeled compounds and more than 10 kinds of Tc-99m cold kits are also produced. Our multi-purpose reactor, named HANARO, has been operative since April of 1995. HANAKO is an open tank type reactor with 30 MW thermal capacity. This reactor was designed not only for research on neutron utilization but for production of radioisotopes. KAERI intended to maximize the radioisotope production capability. For this purpose, radioisotope production facilities (RIPF) have been constructed adjacent to the HANARO reactor building. There are four banks of hot cells equipped with manipulators and some of the hot cells were installed according to the KGMP standards and with clean rooms. In reviewing our RI production plan intensively, emphasis was placed on the development of new radiopharmaceuticals, development of new radiation sources for industrial and therapeutic use, and steady production of selected radioisotopes and radiopharmaceuticals. The selected items are Ho-166 based pharmaceuticals, fission Mo-99/Tc-99m generators. solution and capsules of I-131, and Ir-192 and Co-60 for industrial use. The status and future plan of KAERI's research and development program will be introduced, and will highlight programs for steady production. (author)

  16. Radioisotopes - where have we got to, where are we going ?

    International Nuclear Information System (INIS)

    Rapid growth has been achieved and there are remarkable possibilities in various fields of radioisotopes and radiation. New applications in molecular biology, in nuclear medicine, and in biotechnology are opening further opportunities for the use of radioisotopes. In the industrial field too there is growth, as microprocessor techniques extend the usefulness of radioisotope methods. And radiation engineering is a success story of its own, as ever-increasing use is made of radiation processing and sterilization, and new horizons open for food irradiation. This paper begins by recalling how isotope technology developed from the research laboratory to become the industry-scale activity it is today. A section is devoted to describing the development of a new radioisotope industry during the period from the 1930s through 1960s, focusing on the growth in the areas of nuclear medicine, radiotherapy, isotope gauging and tracing, production control, industrial processing, and production of radioisotopes. After a brief review of the present it looks into the future to suggest the directions in which new developments may lie. In particular, remarkable growth is expected in such areas as molecular biology, biotechnology, radiography, gauging, process control, radiation processing, and radiation sterilization. A review is also made of the transport and disposal of radioisotopes. (Nogami, K.)

  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. 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)

  20. Radioisotopic heater units warm an interplanetary spacecraft

    International Nuclear Information System (INIS)

    The Cassini orbiter and Huygens probe, which were successfully launched on October 15, 1997, constitute NASA's last grand-scale interplanetary mission of this century. The mission, which consists of a four-year, close-up study of Saturn and its moons, begins in July 2004 with Cassini's 60 orbits of Saturn and about 33 fly-bys of the large moon Titan. The Huygens probe will descend and land on Titan. Investigations will include Saturn's atmosphere, its rings and its magnetosphere. The atmosphere and surface of Titan and other icy moons also will be characterized. Because of the great distance of Saturn from the sun, some of the instruments and equipment on both the orbiter and the probe require external heaters to maintain their temperature within normal operating ranges. These requirements are met by Light Weight Radioisotope Heater Units (LWRHUs) designed, fabricated and safety tested at Los Alamos National Laboratory, New Mexico. An improved gas tungsten arc welding procedure lowered costs and decreased processing time for heat units for the Cassini spacecraft

  1. 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.)

  2. 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.

  3. Accidental radioisotope burns - Management of late sequelae

    Directory of Open Access Journals (Sweden)

    Varghese Bipin

    2010-10-01

    Full Text Available Accidental radioisotope burns are rare. The major components of radiation injury are burns, interstitial pneumonitis, acute bone marrow suppression, acute renal failure and adult respiratory distress syndrome. Radiation burns, though localized in distribution, have systemic effects, and can be extremely difficult to heal, even after multiple surgeries. In a 25 year old male who sustained such trauma by accidental industrial exposure to Iridium192 the early presentation involved recurrent haematemesis, pancytopenia and bone marrow suppression. After three weeks he developed burns in contact areas in the left hand, left side of the chest, abdomen and right inguinal region. All except the inguinal wound healed spontaneously but the former became a non-healing ulcer. Pancytopenia and bone marrow depression followed. He was treated with morphine and NSAIDs, epidural buprinorphine and bupivicaine for pain relief, steroids, antibiotics followed by wound excision and reconstruction with tensor fascia lata(TFL flap. Patient had breakdown of abdominal scar later and it was excised with 0.5 cm margins up to the underlying muscle and the wound was covered by a latissimis dorsi flap. Further scar break down and recurrent ulcers occurred at different sites including left wrist, left thumb and right heel in the next two years which needed multiple surgical interventions.

  4. Radioisotopes Identification Algorithm Based on Generic Database

    International Nuclear Information System (INIS)

    The homeland security market is seeking for advanced radiation detectors with improved isotope identification capability. This need is increasing due to the operational difficulties derived by the high probability of innocent alarm shielding and masking scenarios. The identification algorithm should focus on discrimination between Naturally Occurring radioactive Material (NORM) and medical isotopes from industrial sources or Special Nuclear Materials (SNM) following the standards for HLS. The SpecIdentifier software application developed to provide spectrum analysis and identification solutions for various types of detectors. The key requirement is identification of radio-isotopes included in standards for spectroscopic radiation detectors (SPRD).The process of isotope identification is based on spectrum analysis leaning on multi-parametric tests. The parameters include Peak-to-Compton ratio, FWHM (resolution), gain and other values. However, many obstacles are in the way to the proper determination of each parameter: Peak-to-Compton ratio varies with scintillator’s geometry; spectrum shape and resolution vary with scintillator’s physical properties; temperature dependency of scintillation light yield result in gain instability; non-proportionality in light yield as function of incident gamma energy; high count rates results in shift the calibration relation (gain)(4,5). These and other obstacles are considered by the proposed approach to the spectrum analysis and are implemented in the SpecIdentifier software

  5. Improvement of cesium retention in uranium dioxide by additional phases

    International Nuclear Information System (INIS)

    The objective of this study is to improve the cesium retention in nuclear fuel. A bibliographic survey indicates that cesium is rapidly released from uranium dioxide in an accident condition. At temperatures higher than 1500 deg C or in oxidising conditions, our experiments show the difficulty of maintaining cesium inside simulated fuel. Two ternary systems are potentially interesting for the retention of cesium and to reduce the kinetics of release from the fuel: Cs2O-Al2O3-SiO2 et Cs2O-ZrO2-SO2. The compounds CsAISi2O6 and Cs2ZrSi6O15 were studied from 1200 deg C to 2000 deg C by thermogravimetric analysis. The volumetric diffusion coefficients of cesium in these structures, in solid state as well as in liquid one, were measured. A fuel was sintered with (Al2O3 + SiO2) or (ZrO2 + SiO2) and the intergranular phase was characterized. In the presence of (Al2O3 + SiO2), the sintering is realized at 1610 deg C in H2. It is a liquid phase sintering. On the other end, with (ZrO2 + SiO2), the sintering is a low temperature one in oxidising atmosphere. Finally, cesium containing simulated fuels were produced with these additives. According to the effective diffusion coefficients that were measured, the additives improved the retention of cesium. We have predicted the improvement that could be hoped for in a nuclear reactor, depending on the dispersion of the intergranular additives, the temperature and the degree of oxidation of the UO2+x. We wait for a factor of 2 for x=0 and more than 8 for x=0.05, up to 2000 deg C. (author). 148 refs., 122 figs., 34 tabs

  6. 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

  7. Cesium-137 levels detected in Georgia otters

    International Nuclear Information System (INIS)

    Beginning in the 1940's and continuing through the 50's and early 60's, nuclear devices were tested by aerial detonation in the United States and other countries around the world. Cesium-137 (137Cs) is one of the most important radionuclide by-products due to its abundance and slow decay (30-year half-life). The uptake of 137Cs in animal tissue is the result of its similarity to potassium. The somatic and genetic effects of 137Cs, along with its effect on reproductive cells, can pose great hazards to wildlife species. A reported buildup of 137Cs in white-tailed deer in the lower coastal plain of Georgia during the 1960's was followed by a gradual decline during the 1970's. Although numerous studies have involved terrestrial mammals of Georgia, few have involved aquatic mammals such as the river otter. With continued atmospheric testing by some foreign countries and the increased use of nuclear power as an energy source, there is a need for continued monitoring of radionuclides in wildlife to ascertain the quality of the environment. This study was initiated as part of an overall study of environmental pollutants in the river otter of Georgia and deals with analysis of the 137Cs accumulations in this species

  8. Uptake of cesium ions by human erythrocytes and perfused rat heart: a cesium-133 NMR study

    Energy Technology Data Exchange (ETDEWEB)

    Davis, D.G.; Murphy, E.; London, R.E.

    1988-05-17

    Cesium-133 NMR studies have been carried out on suspended human erythrocytes and on perfused rat hearts in media containing CsCl. The resulting spectra exhibit two sharp resonances, arising from intra-and extracellular Cs/sup +/, separated in chemical shift by 1.0-1.4 ppm. Thus, intra- and extracellular resonances are easily resolved without the addition of paramagnetic shift reagents required to resolve resonance of the other alkali metal ions. Spin-lattice relaxation times in all cases are monoexponential and significantly shorter (3-4 times) for the intracellular component. When corrections are made for the pulse repetition rate, the total intensity of the intracellular and extracellular Cs/sup +/ resonances in erythrocytes is conserve, implying total observability of the intracellular pool. The uptake of Cs/sup +/ by erythrocytes occurs at approximately one-third the reported rate for K/sup +/ and was reduced by a factor of 2 upon addition of ouabain to the sample. These results indicate that /sup 133/Cs NMR is a promising tool for studying the distribution and transport of cesium ions in biological systems and, in some cases such as uptake by cellular Na,K-ATPase, for analysis of K/sup +/ ion metabolism.

  9. 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.

  10. 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.)

  11. Micro-PIXE evaluation of radioactive cesium transfer in contaminated soil samples

    International Nuclear Information System (INIS)

    Highlights: • There are radioactively contaminated soils having a radioactive cesium transfer of 0.01. • Micro-PIXE analysis has revealed an existence of phosphorus in a contaminated soil. • Radioactive cesium captured by phosphorus compound would be due to radioactive transfer. -- Abstract: Micro-PIXE analysis has been performed on two soil samples with high cesium activity concentrations. These soil samples were contaminated by fallout from the accident at Fukushima Daiichi Nuclear Power Plant. One exhibits a radioactive cesium transfer of ∼0.01, and the other shows a radioactive cesium transfer of less than 0.001, even though both samples have high cesium activity concentrations exceeding 10,000 Bq/kg. X-ray spectra and elemental images of the soil samples revealed the presence of chlorine, which can react with cesium to produce an inorganic soluble compound, and phosphorus-containing cesium-capturable organic compounds

  12. A fundamental study on cesium migration to sodium at low temperature

    International Nuclear Information System (INIS)

    Our experiment study aims to understand the behavior of cesium in severe accident of sodium cooled fast breeder reactor, especially cesium migration rate to sodium. In past study, exact migration rate of cesium to sodium has not been reported because of difficulty of the cesium-sodium interfacial area evaluations of gas bubble. In this study, we developed a pool-type experimental apparatus which can simplify the shape of interfacial area, and measured cesium migration rate in a low temperature range of 200degC to 300degC. The cesium migration rates obtained under the condition that the cesium mixed argon gas flow is the same temperature with sodium vary in the range of 10-3 - 10-1 mol/m2min and increase with increasing the system temperature. The difference of cesium migration rates between non-oxidized sodium surface and oxidized sodium surface is also clearly observed. (author)

  13. 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.

  14. 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

  15. 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

  16. 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.

  17. Accumulation of cesium-137 by useful mollusca

    International Nuclear Information System (INIS)

    There are few data available on the radioactive contamination of marine mollusca, especially cephalopoda. Therefore, in this paper, data obtained on the radioactive contamination of cephalopoda were compared with those on pelecypoda and gastropoda. The uptake and elimination experiments were carried out by means of radioisotope tracer methods, and the concentration factors of 137Cs due to radioactive fallout were estimated. The contamination of cephalopoda was also compared with those of other marine organisms in terms of concentration factor. The activity ratios in the organs or tissues of octopus were in the range of 3.5 and 12.8 on the 14th day after the beginning of exposure and those of squid were in the range of 8.8 and 10.9 on the 6th day after the commencement of the experiment. The biological half time was 90 days for octopus from the observation over 75 days, while it was 31 days for clam from the results of 75 days' experiment. The concentration factors of 137Cs due to radioactive fallout were in the range of 3 and 23 for cephalopoda, 7 and 28 for pelecypoda and 24 and 30 for gastropoda, respectively. It was concluded that no difference in the concentration factors was clearly observable among the classes of mollusca, but the values were substantially similar to those of crustaceans and slightly lower than those of marine fish. (auth.)

  18. 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

  19. Alternative method for 64Cu radioisotope production

    International Nuclear Information System (INIS)

    The method for 64Cu production based on a 64Ni target using an 18 MeV proton energy beam was developed. The studies on the optimisation of targetry for the 18 MeV proton bombardments were performed in terms of the cost-effective target utilisation and purity of the 64Cu product. The thickness-specific 64Cu yield (μCi/(μAxμm)) was introduced into the optimisation calculation with respect to cost-effective target utilisation. A maximum target utilisation efficacy factor (TUE) was found for the proton energy range of 2.5-13 MeV with corresponding target thickness of 36.2 μm. With the optimised target thickness and proton energy range, the 64Ni target thickness saving of 45.6% was achieved, while the overall 64Cu yield loss is only 23.9%, compared to the use of the whole effective proton energy range of 0-18 MeV with target thickness of 66.6 μm. This optimisation has the advantage of reducing the target amount to a reasonable level, and therefore the cost of the expensive 64Ni target material. The 64Ni target electroplated on the Au-Tl multi layer coated Cu-substrate was a new and competent design for an economic production of high quality 64Cu radioisotope using an 18 MeV proton energy cyclotron or a 30 MeV cyclotron with proton beam adjustable to 18 MeV. In this design, the Au coating layer plays a role of protection of 'cold' Cu leakage from the Cu substrate and Tl serves to depress the proton beam energy (from 18 MeV to the energy optimised value 13 MeV). The ion exchange chromatographic technique with a gradient elution was applied to improve the 64Cu separation with respect to reducing the processing time and control of 64Cu product quality.

  20. Measurement cross sections for radioisotopes production

    International Nuclear Information System (INIS)

    New radioactive isotopes for nuclear medicine can be produced using particle accelerators. This is one goal of Arronax, a high energy - 70 MeV - high intensity - 2*350 μA - cyclotron set up in Nantes. A priority list was established containing β- - 47Sc, 67Cu - β+ - 44Sc, 64Cu, 82Sr/82Rb, 68Ge/68Ga - and α emitters - 211At. Among these radioisotopes, the Scandium 47 and the Copper 67 have a strong interest in targeted therapy. The optimization of their productions required a good knowledge of their cross-sections but also of all the contaminants created during irradiation. We launched on Arronax a program to measure these production cross-sections using the Stacked-Foils' technique. It consists in irradiating several groups of foils - target, monitor and degrader foils - and in measuring the produced isotopes by γ-spectrometry. The monitor - natCu or natNi - is used to correct beam loss whereas degrader foils are used to lower beam energy. We chose to study the natTi(p,X)47Sc and 68Zn(p,2p)67Cu reactions. Targets are respectively natural Titanium foil - bought from Goodfellow - and enriched Zinc 68 deposited on Silver. In the latter case, Zn targets were prepared in-house - electroplating of 68Zn - and a chemical separation between Copper and Gallium isotopes has to be made before γ counting. Cross-section values for more than 40 different reactions cross-sections have been obtained from 18 MeV to 68 MeV. A comparison with the Talys code is systematically done. Several parameters of theoretical models have been studied and we found that is not possible to reproduce faithfully all the cross-sections with a given set of parameters. (author)

  1. 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).

  2. 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

  3. 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)

  4. Sorption of cesium and uranium to Feldspar

    International Nuclear Information System (INIS)

    Within safety assessment studies, for nuclear waste disposal in deep geologic formations, calculation for the migration of radionuclides through the geosphere are often carried out with models taking sorption into account. In the past 8 years the insight grew that other physico-chemical processes, besides sorption, could affect migration behaviour. While the currently used transport models were being improved taking either linear or non-linear sorption into account, the coupling of geochemical and transport models came into scope. In spite of these developments models which are still based on the sorption theory are frequently applied in studying migration behaviour of radionuclides. This is caused by the necessity of making preliminary pronouncements, while coupled models are still in stage of development and thermodynamic data are very limited available. Therefore one has to obtain insight in the reliability of the models based on the sorption theory. within the sorption database there is a lack of knowledge about mineralogy, composition of the fluid and the experimental conditions underlying the data. Therefore the Expert Group on geochemical Modelling supported by the Finnish proposal in order to obtain insight in the possible deviation of the sorption coefficients that can be estimated from experiments performed with standard samples, fluid composition and experimental conditions. Nine laboratories from OECD membership countries took part in this intercalibration study. In the framework of the Dutch safety assessment studies the Dutch National Institute of Public health and Environmental protection (RIVM) has decided to participate in this exercise. In this report the results are presented of sorption experiments for cesium and natural Uranium to Feldspar. (H.W.). 4 refs.; 1 fig.; 7 tabs

  5. Spins and magnetic moments of rubidium and cesium nuclides far from stability

    International Nuclear Information System (INIS)

    Previous studies at ISOLDE have concerned spins and magnetic moments of neutron-deficient rubidium and cesium isotopes. Here, the main results obtained, and, in the case of cesium, new moment measurements are briefly discussed also the results from measurements on neutron-rich nuclides of rubidium and cesium. (orig./AH)

  6. Environmental application of cesium-137 irradiation technology: Sludges and foods

    Science.gov (United States)

    Sivinski, Jacek S.

    Several activities have been undertaken to investigate and implement the use of the military byproduct cesium-137 in ways which benefit mankind. Gamma radiation from cesium-137 has been shown to be effective in reducing pathogens in sewage sludge to levels where reuse of the material in public areas meets current regulatory criteria for protection of public health. Food irradiation at doses of 10 kGy or less have been found by international expert committees to be wholesome and safe for human consumption. Cesium-137 can be used as a means of enhancing particular properties of various food commodities by means of sterilization, insect disinfestation, delayed senescence and ripening, and sprout inhibition. This paper discusses the U.S. Department of Energy Beneficial Uses Program research and engineering history, as well as current activities and future plans, relating to both sewage sludge and food irradiation.

  7. Environmental application of cesium-137 irradiation technology: sludges and foods

    International Nuclear Information System (INIS)

    Several activities have been undertaken to investigate and implement the use of the military byproduct cesium-137 in ways which benefit mankind. Gamma radiation from cesium-137 has been shown to be effective in reducing pathogens in sewage sludge to levels where reuse of the material in public areas meets current regulatory criteria for protection of public health. Food irradiation at doses of 10 kGy or less have been found by international expert committees to be wholesome and safe for human consumption. Cesium-137 can be used as a means of enhancing particular properties of various food commodities by means of sterilization, insect disinfestation, delayed senescence and ripening, and sprout inhibition. This paper discusses the U.S. Department of Energy Beneficial Uses Program research and engineering history, as well as current activities and future plans, relating to both sewage sludge and food irradiation. (author)

  8. 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.

  9. 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

  10. 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.

  11. On the compartmental modeling of cesium migration in soils

    International Nuclear Information System (INIS)

    The prediction of the migration of radionuclides in soil following deposition after a nuclear accident is important for both external dose and plant uptake prediction. In this paper, the validity conditions of compartment models for cesium migration in soils are investigated. A compartment model is derived from a diffusion-convection model. The model considers free and bound cesium compartments and is applied to measured profiles of 137Cs of undisturbed soil in Northern Greece. It is concluded that the rate of cesium transfer must vary linearly with depth and that from measured equilibrium profiles, the ratios of model parameters can be determined but not the parameters themselves. This model is applied to measured profiles of 137Cs in soil due to wet deposition following the Chernobyl accident

  12. The study on the management of radioisotope wastes

    International Nuclear Information System (INIS)

    The purpose of this study is to aid the polish of radwaste treatment expecting nuclear power plant. The amount of annual radwaste generation from the institutional use of radioisotopes is predicted based on the estimation of radioisotope imports that is made in the present study for 1985-1986 in collaboration with Korea Radioisotope Association Inc. In order to survey and to realize the current status of the radiowaste management, we visited organizations using radioisotopes, i.e. medical institutions, colleges, research institutes and industries. It was revealed as a result that there was no unified treatment process and the radwaste management in those institutions has been rather expedient. The management of radwaste from RI application is controlled by the Atomic Energy Low. However, the procedures of handling and treatment suggested and the technological difficulties make it hard to conform with. Accordingly, a guide for the safe handling and treatment of radwaste(draft) is prepared to enhance the safety during the use of radioisotopes and in the management of waste generated from their application. The radwaste containers for the collation and interim storage and their materials should be specified and standardized according to the type and characteristics of radwaste. In the present study, several specific containers are selected and suggested for use. However, their performance should be tested later on. (Author)

  13. Introduction of KIRAMS activity for radioisotope production and its application

    International Nuclear Information System (INIS)

    Full text: Korea Institute of Radiological and Medical Sciences (KIRAMS) has a great potential for clinical and pre-clinical studies of radioisotopes and radiopharmaceuticals. For radioisotope production, we hold a lot of technologies to prepare the short-lived radioisotopes, such as F-18 and C- 11 for application of PET and the radiometals, such as Tl- 201, Ga-67 and In-111 for SPECT using 30MeV (IBA) and 50MeV (MC50) cyclotrons. Recently, we developed radioiodides like I-123 for SPECT and I-124 for PET to label monoclonal antibodies to target the cell surface markers of specific diseases. In order to improve PET radiotracers for the chelator-systems, we also developed the production techniques of new several radionuclides, such as Cu-64, Tc-94m and so on. Therefore, the radiopharmaceutical studies with various radioisotopes, produced by cyclotron, were used for the purpose of invivo imaging of tumor, brain, and organ functions. In case of clinical and pre-clinical applications, the quality control system of radiopharmaceuticals should have been carried at preparation with safety and stability. This is called QURI (QUality Examination for Radiopharmaceuticals Investigation) project as a Top Brand of KIRAMS, which is important to develop the radioisotope production and its application. The future work at KIRAMS will be focused on developing the molecular targets for the purpose of clinical and preclinical applications in order to overcome intractable diseases. (author)

  14. Optimization of radiation protection in the transportation of radioisotopes

    International Nuclear Information System (INIS)

    The collective effective dose equivalent incurred by the population in Argentina as a result of the distribution of radioisotopes for medical applications is estimated. An analysis is performed on the optimization of radiation protection in the transportation of radioisotopes, following the recommendations of the International Commission on Radiological Protection (ICRP). In Argentina, radiopharmaceutical products are arranged and distributed in type-A packages under the regulations for the safe transport of radioactive materials of the International Atomic Energy Agency (IAEA). Additionally, the national regulatory authority requires the application of the dose limitation system to all practices involving radiation exposure by man. Radioisotopes are transported in special vehicles (60%), in domestic flights (30%) and in buses (10%). The collective effective dose equivalent was estimated by taking into account the different transportation means and the storage time while radioisotopes are in transit. The differential cost-benefit analysis shows that, in order to obtain an optimized level of protection, it would be necessary to reduce the current dose rates during transportation. This is particularly worthwhile when the distribution is made through public transportation, such as commercial planes or buses. It is concluded that, for the application of the dose limitation system to the transport of radioisotopes, it would be necessary to reduce the present IAEA limits of radiation levels at a one-meter distance from the packages in about a factor of ten. 6 references, 3 tables

  15. 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

  16. Thallous and cesium halide materials for use in cryogenic applications

    International Nuclear Information System (INIS)

    Certain thallous and cesium halides, either used alone or in combination with other ceramic materials, are provided in cryogenic applications such as heat exchange material for the regenerator section of a closed-cycle cryogenic refrigeration section, as stabilizing coatings for superconducting wires, and as dielectric insulating materials. The thallous and cesium halides possess unusually large specific heats at low temperatures, have large thermal conductivities, are nonmagnetic, and are nonconductors of electricity. They can be formed into a variety of shapes such as spheres, bars, rods, or the like and can be coated or extruded onto substrates or wires. (author)

  17. Selective chemical binding enhances cesium tolerance in plants through inhibition of cesium uptake

    Science.gov (United States)

    Adams, Eri; Chaban, Vitaly; Khandelia, Himanshu; Shin, Ryoung

    2015-03-01

    High concentrations of cesium (Cs+) inhibit plant growth but the detailed mechanisms of Cs+ uptake, transport and response in plants are not well known. In order to identify small molecules with a capacity to enhance plant tolerance to Cs+, chemical library screening was performed using Arabidopsis. Of 10,000 chemicals tested, five compounds were confirmed as Cs+ tolerance enhancers. Further investigation and quantum mechanical modelling revealed that one of these compounds reduced Cs+ concentrations in plants and that the imidazole moiety of this compound bound specifically to Cs+. Analysis of the analogous compounds indicated that the structure of the identified compound is important for the effect to be conferred. Taken together, Cs+ tolerance enhancer isolated here renders plants tolerant to Cs+ by inhibiting Cs+ entry into roots via specific binding to the ion thus, for instance, providing a basis for phytostabilisation of radiocesium-contaminated farmland.

  18. Selective chemical binding enhances cesium tolerance in plants through inhibition of cesium uptake

    DEFF Research Database (Denmark)

    Adams, Eri; Chaban, Vitaly; Khandelia, Himanshu; Shin, Ryoung

    2015-01-01

    High concentrations of cesium (Cs(+)) inhibit plant growth but the detailed mechanisms of Cs(+) uptake, transport and response in plants are not well known. In order to identify small molecules with a capacity to enhance plant tolerance to Cs(+), chemical library screening was performed using...... Arabidopsis. Of 10,000 chemicals tested, five compounds were confirmed as Cs(+) tolerance enhancers. Further investigation and quantum mechanical modelling revealed that one of these compounds reduced Cs(+) concentrations in plants and that the imidazole moiety of this compound bound specifically to Cs......(+). Analysis of the analogous compounds indicated that the structure of the identified compound is important for the effect to be conferred. Taken together, Cs(+) tolerance enhancer isolated here renders plants tolerant to Cs(+) by inhibiting Cs(+) entry into roots via specific binding to the ion thus, for...

  19. 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.

  20. Alpha spectroscopy for in-situ liquid radioisotope measurements

    International Nuclear Information System (INIS)

    Using calculation and SRIM simulations of alpha particle energy spectroscopy, we show that the initial energies and concentrations of alpha-emitting radioisotopes can be measured in-situ in a liquid environment. We quantify the effect on the alpha spectrum of reducing the thickness of the liquid source in front of the alpha particle detector as well as adding a cover material onto the alpha particle detector surface. In all cases, initial energies and concentrations are recoverable from the alpha particle energy spectra. By reducing the thickness of the liquid source, the contribution to the spectrum for low count rate, low energy radioisotopes can be revealed. However, adding a cover on the detector obscures the contributions of these radioisotopes

  1. Transportation and safety test of type BM packages for radioisotopes

    International Nuclear Information System (INIS)

    In the period of May 1977 to October 1979, the Division of Radioisotope Production, JAERI, made containers for transportation of radioisotopes as type BM package, which satisfied the requirements in the amended regulations for transportation of radioisotopes. Two types of packages were prepared, accomodating a drawer type container (lead shielding 15 cm thick) and a cylinder type container (lead shielding 15 or 8 cm thick) respectively; these are for transportation of 192Ir (6540 Ci) and 32P (188 Ci) as type BM package. The package accomodating a drawer type container weighs about 1800 kg. The package accomodating a cylinder type container of 15 cm and 8 cm thick lead shielding weighs 1500 kg or 840 kg respectively. The packages were subjected to series of safety tests prescribed in the regulations, both theoretically and experimentally. Results of the tests showed constructual soundness and safety of the packages. Safety of the type A package prepared is also described in the appendix. (author)

  2. Radioisotope production at the cyclotron in Rio de Janeiro, Brazil

    International Nuclear Information System (INIS)

    A radioisotope production laboratory has been installed at Instituto de Engenharia Nuclear in Rio de Janeiro. It is intended primarily for processing short-lived radioisotopes produced by a multiparticle, variable energy, isochronous, compact CV-28 Cyclotron and for preparation of radiopharmaceuticals and labelled molecules. Carrier-free iodine-123, indium-111, thalium-201, bromine-77 and gallium-67 with high purity have been produced. An irradiated target transport system has been built. Special targets that can dissipate high surface power densities are being developed. Each radioisotope is processed in a remotely controlled cell equiped with electric and pneumatic systems as well as manipulators ans tongs. Quality control is achieved by atomic absorption spectrophotometry, spot tests, gamma-ray spectroscopy and thin-layer chromatography. Biological tests in mice have confirmed the good quality of the radiopharmaceuticals. (Author)

  3. 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)

  4. Educational Web site. Radioisotopic methods of determining body composition

    International Nuclear Information System (INIS)

    A Web site intended to inform the general public about existing nuclear technologies based on the measurement of radioisotopes in the human body has been designed. The presentation is focused on the concept of radioisotope measurements for determination of body composition (bone, muscle, water, fat), and the risks, benefits, and clinical applications of these techniques. Procedures covered are 40K whole body counting, delayed-gamma neutron activation, prompt-gamma neutron activation, and dual-energy X-ray absorptiometry. The information presented is tailored for the nonscientific public, in order to promote familiarity with and understanding of the basic concepts of radioisotope measurements in the human body. Further development of the site will include greater scientific detail, suitable for student instruction or for continuing education requirements of various certification programs. (author)

  5. Digital Data Processing and Display in Radioisotope Imaging

    International Nuclear Information System (INIS)

    In conventional radioisotope images much information is lost through taking data by analogue instruments and displaying them on analogue devices. By utilizing appropriate digital instruments, data in radioisotope imaging are taken in the form of a numerical array ('digital image') and each number corresponds to the counts in a small area that is called an 'elemental image'. If the area of an 'elemental image' is much smaller than a resolving area of the imaging system, all useful information is contained in the 'digital image'. Since the radioisotope image must be interpreted by the human visual system at present, the resulting 'digital image' should be so processed that human eyes can easily extract the diagnostic information from the image pattern. Three methods of image processing are described: (1) 'smoothing' (2) 'focusing' (restoring) and (3) 'differential imaging'. A preliminary experiment using a thyroid phantom was made and the results showed the effectiveness of the image processing. (author)

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

    Science.gov (United States)

    Choi, Sang H.; Duzik, Adam J.

    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.

  7. Role of mesoscale eddies in transport of Fukushima-derived cesium isotopes in the ocean

    Science.gov (United States)

    Budyansky, M. V.; Goryachev, V. A.; Kaplunenko, D. D.; Lobanov, V. B.; Prants, S. V.; Sergeev, A. F.; Shlyk, N. V.; Uleysky, M. Yu.

    2015-02-01

    We present the results of in situ measurements of 134Cs and 137Cs released from the Fukushima Nuclear Power Plant (FNPP) collected at surface and different depths in the western North Pacific in June and July 2012. It was found that 15 month after the incident concentrations of radiocesium in the Japan and Okhotsk seas were at background or slightly increased level, while they had increased values in the subarctic front area east of Japan. The highest concentrations of 134Cs and 137Cs up to 13.5±0.9 and 22.7±1.5 Bq m-3 have been found to exceed ten times the background levels before the accident. Maximal content of radiocesium was observed within subsurface and intermediate water layers inside the cores of anticyclonic eddies (100-500 m). Even slightly increased content of radiocesium was found at some eddies at depth of 1000 m. It is expected that convergence and subduction of surface water inside eddies are main mechanisms of downward transport of radionuclides. In situ observations are compared with the results of simulated advection of these radioisotopes by the AVISO altimetric velocity field. Different Lagrangian diagnostics are used to reconstruct the history and origin of synthetic tracers imitating measured seawater samples collected in each of those eddies. The results of observations are consistent with the simulated results. It is shown that the tracers, simulating water samples with increased radioactivity to be measured in the cruise, really visited the areas with presumably high level of contamination. Fast water advection between anticyclonic eddies and convergence of surface water inside eddies makes them responsible for spreading, accumulation and downward transport of cesium rich water to the intermediate depth in the frontal zone.

  8. 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.

  9. 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

  10. Radiation surveillance procedure during veterinary application of radioisotope

    International Nuclear Information System (INIS)

    Radioisotopes have found wide applications in the field of biomedical veterinary nuclear medicine and research. Radiation safety issues during internal administration of radioisotopes to laboratory animals, unlike human use, are far more challenging and requires stringent, well planned and an organized system of radiation protection in the animal house facility. In this paper, we discuss our experience during veterinary research experiments involving use, handling and administration of liquid sources of 131I. With extensive radiation protection surveillance and application of practical and essential radiation safety and hygiene practices, the radiation exposure and contamination levels during the veterinary application of isotopes can be kept ALARA

  11. 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)

  12. Regulatory aspects on the utilization of radioisotopes in industry

    International Nuclear Information System (INIS)

    The legal provisions to regulate the use of radioisotopes in industry are based on Sections 3e (i), (ii) and (iii) and 17 of the Atomic Energy Act 1962. The Central Government delegated the authority to enforce the safety-related rules to the Atomic Energy Regulatory Board (AERB). The Board has issued codes and standards and established procedures to carry out its mandate. AERB imposed regulatory restrictions on erring institutions, wherever necessary and evolved policies on the use of equipment containing radioisotopes. (author)

  13. 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)

  14. 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.)

  15. The development of radioisotope applications in South Africa

    International Nuclear Information System (INIS)

    The first era of radioactive isotopes and radiation since the turn of the century was inevitably restricted to x-rays and radium, with the greatest application in medicine for diagnosis and therapy. In South Africa a second era began when the first artificial radioisotope was imported on 27 July 1948, and the medical practitioners, in particular, were ready to use this new modality also as a tracer. This article gives general information on radiation protection, isotope users, therapy and in vivo and in vitro tests with radioisotopes in South Africa

  16. 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

  17. A method for reducing the cesium-137 content in meat

    International Nuclear Information System (INIS)

    Reports a study of a method for reducing the amount of cesium-137 in meat from wild animals. The method is intended for use in the kitchen and is based on a combined leaching and mechanical process. (K.A.E.)

  18. 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.

  19. Fission-product tellurium and cesium telluride chemistry revisited

    International Nuclear Information System (INIS)

    The chemistry of fission-product tellurium is discussed with a focus on conditions in an operating CANDU reactor and in an accident scenario, i.e., a loss of coolant accident (LOCA). Cesium telluride, Cs2Te, is likely to be one of the most abundant tellurium species released to containment. Available thermodynamic data on gas phase Cs2Te is not complete; hence the volatility of cesium telluride was studied by Knudsen-cell mass spectrometry. Cesium telluride was found to vapourize incongruently, becoming more tellurium-rich in the condensed phase as vapourization progressed. Vapour-phase species that were observed were elemental cesium and tellurium, CsTe, Cs2Te, Cs2Te2 and Cs2Te3. Second-law enthalpies and entropies were obtained for many of these species, and a third-law value, ΔH298o, of 186 ± 2 kJ·mol-1 was obtained for Cs2Te. (author)

  20. 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.

  1. 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)

  2. Cesium ion desorption ionization with Fourier transform mass spectrometry

    International Nuclear Information System (INIS)

    Cesium ions (Cs+) are used for the production of the feed ions necessary to obtain Fourier transform mass spectra (FTMS). The molecule chosen for the initial study of this Cs+ desorption ionization (DI-FTMS) was vitamin B-12 because of its nonvolatile, thermally labile character. 21 references

  3. 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.

  4. Hot demonstration of proposed commercial cesium removal technology

    International Nuclear Information System (INIS)

    This report describes the work done in support of the development of technology for the continuous removal and concentration of radioactive cesium in supernatant from Melton Valley Storage Tanks (MVSTs) at the ORNL site. The primary objective was to test candidate absorbers and ion exchangers under continuous-flow conditions using actual supernatant from the MVSTs. An experimental system contained in a hot-cell facility was constructed to test the materials in columns or modules using the same batch of supernatant to allow comparison on an equal basis. Resorcinol/formaldehyde (RF) resin was evaluated at three flow rates with 50% breakthrough ranges of 35 to 50 column volumes (CV) and also through a series of five loading/elution/regeneration cycles. The results reported here include the cesium loading breakthrough curves, elution curves (when applicable), and operational problems and observations for each material. The comparative evaluations should provide critical data for the selection of the sorbent for the ORNL Cesium Removal Demonstration project. These results will be used to help determine the design parameters for demonstration-scale systems. Such parameters include rates of cesium removal, quantity of resin or sorbent to be used, and elution and regeneration requirements, if applicable

  5. Cesium-137 Levels Detected in Otters from Austria

    OpenAIRE

    Gutleb A.C.; Mraz, G.

    1991-01-01

    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.

  6. Selective extraction of cesium: from compound to process

    International Nuclear Information System (INIS)

    Under the French law of 30 December 1991 on nuclear waste management, research is conducted to recover long-lived fission products from high-level radioactive effluents generated by spent fuel reprocessing, in order to destroy them by transmutation or encapsulate them in specific matrices. Cesium extraction with mono and bis-crown calix(4)arenes (Frame 1) is a candidate for process development. These extractants remove cesium from highly acidic or basic pH media even with high salinity. A real raffinate was treated in 1994 in a hot cell to extract cesium with a calix-crown extractant. The success of this one batch experiment confirmed the feasibility of cesium decontamination from high-level liquid waste. It was then decided to develop a process flowchart to extract cesium selectively from high-level raffinate, to be included in the general scheme of long-lived radionuclide partitioning. It was accordingly decided to develop a process based on liquid-liquid extraction and hence optimize a calixarene/diluent solvent according to: - hydraulic properties: density, viscosity, interfacial tension, - chemical criteria: sufficient cesium extraction (depending on the diluent), kinetics, third phase elimination... New mono-crown-calixarenes branched with long aliphatic groups (Frame 2) were designed to be soluble in aliphatic diluents. To prevent third phase formation associated with nitric acid extraction, the addition of modifiers (alcohol, phosphate and amide) in the organic phase was tested (Frame 3). Table 1 shows examples of calixarene/diluent systems suitable for a process flowchart, and Figure 2 provides data on cesium extraction with these new systems. Alongside these improvements, a system based on a modified 1,3-di(n-octyl-oxy)2,4-calix[4]arene crown and a modified diluent was also developed, considering a mixed TPH/NPHE system as the diluent, where TPH (hydrogenated tetra propylene) is a common aliphatic industrial solvent and NPHE is nitrophenyl

  7. 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

  8. Demonstration test for decontamination technology of cesium-contaminated ash

    International Nuclear Information System (INIS)

    KEPCO Engineering and Construction Company (KEPCO E and C), architecture and engineering company of nuclear power plant, developed the 'decontamination technology of cesium-contaminated ash' in the basis of pre-owned 'decontamination technology of cesium-contaminated soil'. The new technology was demonstrated in Fukushima prefecture during 12 days from November 5, 2013, in order to verify the performance. Demonstration equipment (CEDECON-DA), with a capacity of treatment of 20 ℓ per batch, can be carried in a container in order to promote the ease of transportation and in-situ installation. Through the demonstration test it was verified the superior performance and the possibility of commercialization. This technique comprises of cesium separation and cesium coagulation processes. Briefly speaking, the principal of this process is as follows; cesium is separated from ash, detached to the coagulation and then deposited. The decontaminated ash can be disposed of into municipal landfills as conventional non-radioactive waste. The present technology is evaluated such that the disposal amount of radioactive waste will be significantly reduced. The ash with average concentration of 6,200 Bq/kg from a conventional incineration plant was used for the demonstration test. Each separate performance test has been carried out under acid, neutral and alkaline conditions, respectively. The test result for alkaline condition showed the highest decontamination ratio of 82-85% and the volume reduction ratio of 95%. Radioactive Waste Management and Nuclear Facility Decommissioning Technology Center (RANDEC) performed the radiation protection management, activity measurement and evaluation in the demonstration test results. (author)

  9. 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

  10. Strontium, cessium, and cerium radioisotope concentration in water of superficial reservoirs as determined by their accumulation in alga Cladophora glomerata

    International Nuclear Information System (INIS)

    An indirect method of measuring concentrations of strontium-90,cesium-137 and cerium-144 in water is considered. The method is bsed on the accumulation of the nuclides in Cladophora glomerata Kutz, a fresh-water alga. During 10 days in the end of July, 1975, water samples (20 l) and alga samples (about 1 kg) were taken at 14 locations more or less evenly distributed along the bank of reservoir. Some locations were in coves or issues of small rivers so that almost all morphometric features of the reservoir were taken into account. The samples were processed and radiochemically analyzed, including the radiometry of standard techniques. The counting time was so selected that the statistical error did not exceed 10 %. The radionuclide concentration was calculated per unit weight of sample (pCi/l or pCi/kg of natural alga biomass). The method may be of particular importance for those radionuclides that are rapidly absorbed by bottom sediments and at the same time intensively accumulated by the hydrobios (radioisotopes of iron, cobalt, zinc, yttrium, zirconium and some others)

  11. Radioisotope Production Plan and Strategy of Kijang Research Reactor

    International Nuclear Information System (INIS)

    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

  12. 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

  13. 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.

  14. 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

  15. 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)

  16. 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...

  17. 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)

  18. 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.

  19. Monte Carlo Radiation Analysis of a Spacecraft Radioisotope Power System

    Science.gov (United States)

    Wallace, M.

    1994-01-01

    A Monte Carlo statistical computer analysis was used to create neutron and photon radiation predictions for the General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS RTG). The GPHS RTG is being used on several NASA planetary missions. Analytical results were validated using measured health physics data.

  20. 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

  1. Preparation of an annual report for a consolidated radioisotope licence

    International Nuclear Information System (INIS)

    A consolidated radioisotope licence is a single license issued by the Atomic Energy Control Board (AECB) to an institution having many users of radioactive materials. The licence is issued when the institution has fulfilled the requirements set by the AECB and has implemented policies and procedures which will ensure the maintenance of an effective radiation safety program. The consolidated licence is retained only if the results of AECB inspections are satisfactory -- or remedial action is taken promptly -- and if the institution reports regularly about the status of its radiation safety program. One aspect of this reporting procedure is an annual report. This guide describes the information that the AECB requires in the annual report. The guide applies primarily to universities and research institutions where a wide variety of radioisotope uses take place. The guide does not affect most other institutions or facilities, either because the nature and extent of their operations with radioactive materials do not lend themselves to consolidated licensing or because they are not licensed by the Radioisotopes and Transportation Division. (For example, this guide does not apply to reactors, to accelerators, or to waste management or uranium mining or refining facilities.) The information in the annual report should be specific to the consolidated radioisotope licence. Incidents, staff exposures, and waste associated with accelerators, research reactors, and waste management facilities should be excluded from this report unless they affected activities under the consolidated licence

  2. Detectors for medical radioisotope imaging: demands and perspectives

    OpenAIRE

    Lopes, M. I.; Chepel, V.

    2004-01-01

    Radioisotope imaging is used to obtain information on biochemical processes in living organisms, being a tool of increasing importance for medical diagnosis. The improvement and expansion of these techniques depend on the progress attained in several areas, such as radionuclide production, radiopharmaceuticals, radiation detectors and image reconstruction algorithms. This review paper will be concerned only with the detector technology.

  3. Mycoremediation. Fungus-based soil remediation of radioisotope contamination

    International Nuclear Information System (INIS)

    Fungal mycelia in soil can hyperaccumulate radioisotopes at up to 25,000 Bq per kg of mushrooms. Mycelium Group International (MGI) here introduces mycelial radioactive decontamination techniques (mycoremediation) that can potentially restore safe soil levels on Fukushima farmland in less than ten years with high efficiency, without loss of topsoil, and less expensively than current destructive methods. (author)

  4. 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

  5. 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

  6. 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

  7. 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.

  8. Production capabilities in US nuclear reactors for medical radioisotopes

    International Nuclear Information System (INIS)

    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

  9. 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

  10. The Radioisotopes production in tunisia, presentation of the CNSTN project

    International Nuclear Information System (INIS)

    Radio-isotopes required in medicine (nuclear medicine, neurology, cardiology, orthopedics) need a deep reflection and a scientific analysis of the problems related to the human health. The utilisation of radioisotopes in other fields such as chemistry, agriculture, industry, safety, earth sciences and environmental physics is also of great importance. In pharmaceutical companies, radioisotopes used in a laboratory of imaging for small animal to check the efficiency of drugs in vivo is touched upon in this presentation. Radioisotopes are also needed for different activities in platform dedicated to the training of radio pharmacist and radio biologist. The availability of radioisotopes in a research center such as the National Center of Nuclear Sciences and Technologies (NCNST) will improve the activity of existing skills and serve the country's development in the field of biomedical research. Tunisia has two projects of cyclotrons facilities: the first one is in the private sector and the second one is proposed by the NCNST. The realization of these projects requires a period of time estimated to two years for the feasibility study and two years more for constitution. In the meantime, it is necessary to establish a master's degree in radio-pharmacy / radio-biology to provide skills that may activate cyclotron facilities. One last test phase lasts 6 months to a year. The work within a cyclotron facility requires a rigorous and a lot of discipline (a little bit military) ordered by the risk of the isotope radioactive half-life and its radiation activity. Thus, it is necessary to provide to the staff, various training required for the functioning of the cyclotron. It is useful to insist on the importance of scientist's team which is going to put on the cyclotron and which consists of: radio-pharmacists, radio physicists experts in radiation protection, and engineer's operators of cyclotrons. It is useful to attract the attention that the specialties in the field of the

  11. 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)

  12. Electrode activation in cesium-free negative ion sources

    International Nuclear Information System (INIS)

    Features of emission electrode activation leading to enhancement of negative ion emission in cesium-free discharges are discussed. In some ion sources with cesium-free discharges, the emission of negative ions has been increased significantly by emission electrode activation using strong heating of the negative biased electrode by discharge plasma. A simple explanation of this enhancement is that it is due to an accumulation on the emission surface of the plasma electrode of impurities with low ionization potential that decreases in surface work function and increases the secondary emission of negative ions similar to ''Cesiation.'' The negative biasing of emission surface is important for accumulation and trapping the impurities on the emission surface. To effectively control the activation process it is important to directly detect the evolution of the work function and the impurity concentration during electrode activation with enhancement of negative ion emission.

  13. 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.)

  14. 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)

  15. 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.

  16. Strontium-90 and cesium-137 in air-borne dust

    International Nuclear Information System (INIS)

    Under the commission of Science and Technology Agency, Japan Chemical Analysis Center and prefectural public health laboratories and institutes have determined the levels of strontium-90 and cesium-137 in air-borne dust samples. Dust samples were collected by the aspiration of 3000 m3 or more air at 1.0 -- 1.5 m above the ground surface in 10 prefectural public health laboratories and institutes. The samples collected during three months were combined, and were forwarded to Japan Chemical Analysis Center after carbonization. These samples were ashed in an electric muffle furnance at Japan Chemical Analysis Center. The ash to which both some carriers and hydrochloric acid were added, was destroyed under heating. The solution was dissolved into hydrochloric and filtered, after it was added with nitric acid and heated to dryness. The filtrate was radiochemically analysed for strontium-90 and cesium-137 with low background beta-ray spectrometer. (author)

  17. Cesium and lead uptake by CSH phases of hydrated cement

    International Nuclear Information System (INIS)

    As Kd from radwaste elements in concrete systems show a wide range of values, a modelling of cesium and lead immobilization in Calcium Silicate Hydrate (CSH, xCaO.SiO2.H2O, with 0.7 (aged cements)SiOH) and precipitation equilibria. Values of Kd from cesium and lead in CSH matrix can thus be calculated with Ca/Si evolution and ionic strength effect. Predictive calculations have been carried out with success with different Ca/Si ratios, ionic strengths and liquid/solid ratios, and results are well superimposed with experimental isotherm data. If the CSH really allow accounting for the radwaste behavior in hydrated cement matrices, this model can be used in safety assessment calculations, with varying pH and [Ca2+] as cement degradation state parameters. Copyright (2001) Material Research Society

  18. New thermodynamic regularity for cesium over the whole liquid range

    CERN Document Server

    Ghatee, M H

    2001-01-01

    In this paper we derive an equation of state for liquid cesium based on a suggested potential function in accord to the characteristics large attraction and soft repulsion at the asymptotes of interaction potentials. By considering the interaction of nearest adjacent atoms in dense fluid, the equation of state predicts that the isotherm is linear function of, where is the compression factor, is the molar volume, and is the molar density. The linear parameters are identified as interaction coefficients related to attraction and repulsion, and are used to evaluate the molecular parameters with interesting implications. The isotherm is intended to resolve the particular thermodynamic properties of alkali metals, which have been known for their unusual change of the nature of intermolecular force as the characteristic metal-nonmetal transition range is approached. When applied to liquid cesium, the isotherms persist linear over the whole liquid range including the metal non-metals transition range and at the crit...

  19. Strontium-90 and cesium-137 in air-borne dust

    International Nuclear Information System (INIS)

    The levels of strontium-90 and cesium-137 in airborne dust have been determined by Japan Chemical Analysis Center under the contact with Science and Technology Agency. Dust samples were collected at 1.0 -- 1.5m above the ground surface with electrostatic precipitators or on filter papers by each prefectural public health laboratories and institutes in 9 prefectures, and these samples were forwarded to Japan Chemical Analysis Center after the carbonization. These samples were asked in an electric muffle furnance at Japan Chemical Analysis Center. The ask to which both some carriers and hydrochloric acid were added, was destroyed under heating. The solution was dissolved into hydrochloric acid and filtered, after it was added with nitric acid and heated to dryness. The filtrate was analysed for strontium-90 and cesium-137 using the method recommended by science and Technology Agency. (author)

  20. 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)

  1. Migration behavior of cesium in compacted sodium montmorillonite

    International Nuclear Information System (INIS)

    For safety assessments of geological disposal of high-level radioactive wastes, it is important to study the migration behavior of radioactive nuclides in compacted bentonite. In the present study, the apparent diffusion coefficients and activation energies of the diffusion were determined for cesium ions in compacted montmorillonite, a major clay mineral in bentonite. The activation energies obtained in the present study were 32.9 to 52.9 kJ mol-1, clearly higher than for the diffusion of cesium ions in free water, 16.2 kJ mol-1. The activation energies for Na-montmorillonite specimens with dry densities of 1.0, 1.2, and 1.4 x 103 kg m-3 were similar at approximately 34 kJ mol-1. When the dry density of the Na-montmorillonite specimens increases, the activation energy also increases, to reach 52.9 kJ mol-1 at 1.8 x 103 kg m-3. These findings suggest that the cesium in the compacted Na-montmorillonite diffuses with a different process from that in free water. Basal spacings were determined by the X-ray diffraction method for water-saturated, compacted Na-montmorillonite specimens. Three-water layer hydrate in the interlamellar space was observed for the Na-montmorillonite with dry densities of 1.0, 1.2, and 1.4 x 103 kg m-3, where the activation energies for the diffusion were nearly constant. Only the two-water layer hydrate was found in the Na-montmorillonite with dry densities of 1.6 and 1.8 x 103 kg m-3, in which the activation energy increases with the dry density. It is possible that the basal spacing could affect the migration behavior of cesium in compacted Na-montmorillonite. (author)

  2. 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

  3. 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.

  4. Cesium dihydrophosphate monocrystal growth and certain of their properties

    International Nuclear Information System (INIS)

    Crystals of cesium dihydrophosphate (centrisymmetrical, monoclinic, point symmetric group 2/m) are obtained by methods involving solvent evaporation and temperature reduction. At -122 deg C, a ferroelectric phase transition occurs, and at 230 and 265 deg C first-kind transitions, which are not accompanied by composition changes. CsH2PO4 solubility substantially increases with higher medium acidity, and remains approximately constant in alkali medium

  5. Behaviour of radioactive cesium in northern boreal forest ecosystems

    International Nuclear Information System (INIS)

    Full text: In 1997-2001 a large number of environmental samples have been collected from the Muddusjaervi area in Finnish Lappland. These samples include soil, water, sediment, vegetation and fish samples. Radioactive contamination in this subarctic environment has mainly resulted from the nuclear weapons test fallout in the 1950s and 1960s. Chernobyl accident did not considerably increase the contamination level in this area. The Laboratory of Radiochemistry, University of Helsinki, has been studying the behaviour of fallout radionuclides in the environment and in food chains in Lappland from the beginning of the 1960s. The study area lies in the middle of northern reindeer herding area where accumulation of radioactive cesium has been observed in food chains. In this paper we report on the behaviour of radioactive cesium in soil columns. The soil in this area is typically nutrient-poor podzolic soil. Altogether thirty soil columns were collected and they were divided into horizons (litter, organic and mineral layers). The activity concentrations of the horizons were determined by gamma spectrometry. In general, cesium has been concentrated mainly in the litter and organic layers and it has not been migrated considerably to mineral layers. To study the long term behaviour of cesium in soil the activity concentrations have been compared to those found in earlier decades and to the activity concentrations earlier determined for other radionuclides, especially for Pu. A further major objective was to study runoff of radionuclides from ground to lakes and brooks and therefore many of the soil samples were collected from various distances from lakes and brooks. (author)

  6. Detection of the actinides and cesium from environmental samples

    Science.gov (United States)

    Snow, Mathew Spencer

    Detection of the actinides and cesium in the environment is important for a variety of applications ranging from environmental remediation to safeguards and nuclear forensics. The utilization of multiple different elemental concentrations and isotopic ratios together can significantly improve the ability to attribute contamination to a unique source term and/or generation process; however, the utilization of multiple elemental "signatures" together from environmental samples requires knowledge of the impact of chemical fractionation for various elements under a variety of environmental conditions (including predominantly aqueous versus arid conditions). The research reported in this dissertation focuses on three major areas: 1. Improving the understanding of actinide-mineral interactions at ultra-low concentrations. Chapter 2 reports a batch sorption and modeling study of Np(V) sorption to the mineral goethite from attomolar to micromolar concentrations. 2. Improving the detection capabilities for Thermal Ionization Mass Spectrometry (TIMS) analyses of ultra-trace cesium from environmental samples. Chapter 4 reports a new method which significantly improves the chemical yields, purification, sample processing time, and ultimately, the detection limits for TIMS analyses of femtogram quantities of cesium from a variety of environmental sample matrices. 3. Demonstrating how actinide and cesium concentrations and isotopic ratios from environmental samples can be utilized together to determine a wealth of information including environmental transport mechanisms (e.g. aqueous versus arid transport) and information on the processes which generated the original material. Chapters1, 3 and 5 demonstrate these principles using Pu, Am, Np, and Cs concentrations and isotopic ratios from contaminated soils taken near the Subsurface Disposal Area (SDA) of Idaho National Laboratory (INL) (a low level radioactive waste disposal site in southeastern Idaho).

  7. 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.

  8. 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

  9. 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.

  10. Extraction of rubidium and cesium from micas following sulfate-extraction technology

    International Nuclear Information System (INIS)

    Results are presented of semicommercial tests of procedure of rubidium and cesium extraction from micas. Micas has been processed by the 40% solution of sulphuric acid at boiling temperature. Separate extraction of cesium and rubidium from the solution with arylalkylsubstituted phenol has been conducted after alum crystallization and decomposition by lime. Pure rubidium carbonate and technical cesium carbonate with their 80 and 95% extraction, respectively, are prepared

  11. Investigations of the method of sodium decontamination from cesium and tritium aiming its utilization or disposal

    International Nuclear Information System (INIS)

    Effective methods of removing cesium and tritium from sodium are submitted. It is shown, that the cleaning from cesium with consecutive use of portions of carbon materials will allow on the orders to reduce amount of sorbent, in which is concentrated cesium. For cleaning from tritium technological process with use of a cold trap and special dosage hydrogen in sodium is offered. The data on required time of cleaning and depth of cleaning at various capacity of hydrogen source are given. (author)

  12. 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.

  13. 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.

  14. 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.

  15. Transition of cesium in food chains [after Chernobyl catastrophe

    International Nuclear Information System (INIS)

    An investigation of 25,000 samples of foodstuffs and feedstuffs in Czechoslovakia, contaminated by fall-out cesium after the accident in the Chernobyl nuclear power plant, performed from May 5, 1986 to March 31, 1988, revealed that both the values of cesium transfer-factors in food--animal tissues--milk transitions and the values of biological half-life of cesium are functions of internal and external conditions of contamination. Organism individuality as the main internal condition causes the variance of about +/- 50% of the mean value of the respective transfer-factor. Through the external conditions, mainly the environmental contamination level, type of ingested food and time of ingestion, the mean values of transfer-factors are influenced up to 500%, e.g. to the value of 0.5. But this value converges with growing up contamination of food and environment to the limit of 0.3. The first two to three biological half-lives after the last ingestion of contaminated food are up to ten-times shorter than those at stabilized state

  16. Cesium transfer to agricultural crops for three years after Chernobyl

    International Nuclear Information System (INIS)

    In 1986 about 50 farms in the fallout region were selected for sampling at fixed sites of the soil surface layer and of the grassland and grain crops to come. The aim was to cover the different soil types and the farming practices of the region during studies on the transfer levels and on the change with time in transfer of cesium to the crops. It was found that the transfer level, as expected, was much higher for the grassland than for the grain crops. However, within both groups of considerable variation in the transfer level for the same year as measured by the transfer factors has occurred. For the former crops it can be concluded that the transfer factor during year 1 depends on the interception capacity of the plant cover and on the dilution by growth i.e on soil fertility and on fertilization level. In the following years the cesium TF-value for the grass cover was reduced by a factor from 2 to about 10. The reduction rate differed above all between the organic soils and the mineral soils and should largely depend on the type of the grass cover, on the different cesium fixing capacities of the two soil groups and on the potassium fertilization level. On ploughed land the transfer by root uptake to grain crops was about one magnitude lower than the transfer to the hey crops. (orig.)

  17. Example of cesium sorption database in natural minerals

    International Nuclear Information System (INIS)

    In the database of the National Institute for Materials Science (MatNavi), the adsorption data of cesium, strontium, and iodine have been published. Among these data, the authors picked up the data of cesium adsorption against natural ores, which were measured and compiled by the authors, graphically expressed them for clarifying the overall trends, and described each mineral’s adsorption characteristics and future challenges. The partition coefficients for the following minerals are compiled: bentonite, acid clay, montmorillonite, beidellite, vermiculite, illite, mordenite, zeolite, etc. Many of the recorded data in MatNavi are the data obtained in the systems without existence of a large amount of competing ions. On the other hand, in the accumulated water at the Fukushima Daiichi Nuclear Power Station, competing ions due to seawater are contained. In the immersion liquid of incineration fly ash and the immersion liquid of plants/vegetation, too, competing ions are considered to be contained. Accumulation of adsorption data under different solution conditions are considered important. In addition, the concentrations of radioactive cesium in decontamination target are lower values by 5-7 orders, compared with the lower limit of 0.01 ppm in the existing data. In face of experiments, the influence of adsorption to containers and filters cannot be neglected. (A.O.)

  18. 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

  19. 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)

  20. Radioisotope applications for troubleshooting and optimizing industrial processes

    International Nuclear Information System (INIS)

    This brochure is intended to present the state-of -the-art in techniques for gamma scanning and neutron backscattering for troubleshooting inspection of columns, vessels, pipes, and tanks in many industrial processing sectors. It aims to provide not only an extensive description of what can be achieved by the application of radioisotope sealed sources but also sound experience-based guidance on all aspects of designing, carrying out and interpreting the results of industrial applications. Though it is written primarily for radioisotope practitioners, the brochure is also intended to function as an ambassador for the technology by promoting its benefits to governments, to the general public and to industrial end-users

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

    Energy Technology Data Exchange (ETDEWEB)

    1991-07-01

    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.

  2. When are fume-cupboards necessary in hospital radioisotope laboratories

    International Nuclear Information System (INIS)

    Suggestions are made for procedures likely to require the provision of efficient fume-cupboards in hospital radioisotope laboratories. All such departments undertaking in vivo radioisotope procedures will require a supply of sterile materials, but only some of these will also require a fume-cupboard, since the use of a relatively inexpensive aseptic cabinet, without air flow and exhaust system, may suffice for such procedures as the labelling of blood cells or plasma. Efficient fume-cupboards may be required in hospital laboratories that are routinely concerned with the elution of generators of isotopes such as 99Tcsup(m) and 113Insup(m), the sterilization of radiopharmaceuticals (e.g. technetium-sulphur colloid) requiring the use of a pressure cooker, and the storage and handling of therapeutic quantities of 131I. Copious general ventilation of isotope rooms may be preferable to the too frequent incorporation of unnecessary fume-cupboards. (U.K.)

  3. 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.

  4. 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

  5. Detectors for medical radioisotope imaging: demands and perspectives

    Science.gov (United States)

    Lopes, M. I.; Chepel, V.

    2004-10-01

    Radioisotope imaging is used to obtain information on biochemical processes in living organisms, being a tool of increasing importance for medical diagnosis. The improvement and expansion of these techniques depend on the progress attained in several areas, such as radionuclide production, radiopharmaceuticals, radiation detectors and image reconstruction algorithms. This review paper will be concerned only with the detector technology. We will review in general terms the present status of medical radioisotope imaging instrumentation with the emphasis put on the developments of high-resolution gamma cameras and PET detector systems for scinti-mammography and animal imaging. The present trend to combine two or more modalities in a single machine in order to obtain complementary information will also be considered.

  6. Detectors for medical radioisotope imaging: demands and perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, M.I. E-mail: isabel@lipc.fis.uc.pt; Chepel, V

    2004-11-01

    Radioisotope imaging is used to obtain information on biochemical processes in living organisms, being a tool of increasing importance for medical diagnosis. The improvement and expansion of these techniques depend on the progress attained in several areas, such as radionuclide production, radiopharmaceuticals, radiation detectors and image reconstruction algorithms. This review paper will be concerned only with the detector technology. We will review in general terms the present status of medical radioisotope imaging instrumentation with the emphasis put on the developments of high-resolution gamma cameras and PET detector systems for scinti-mammography and animal imaging. The present trend to combine two or more modalities in a single machine in order to obtain complementary information will also be considered.

  7. 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...

  8. 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)

  9. 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

  10. Radioactive cesium dynamics derived from hydrographic observations in the Abukuma River Estuary, Japan.

    Science.gov (United States)

    Kakehi, Shigeho; Kaeriyama, Hideki; Ambe, Daisuke; Ono, Tsuneo; Ito, Shin-Ichi; Shimizu, Yugo; Watanabe, Tomowo

    2016-03-01

    Large quantities of radioactive materials were released into the air and the ocean as a result of the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident, caused by the 2011 Tohoku earthquake and the subsequent major tsunami off the Pacific coast. There is much concern about radioactive contamination in both the watershed of the Abukuma River, which flows through Fukushima Prefecture, and its estuary, where it discharges into the sea in Miyagi Prefecture. We investigated radioactive cesium dynamics using mixing diagrams obtained from hydrographic observations of the Abukuma River Estuary. Particulate radioactive cesium dominates the cesium load in the river, whereas the dissolved form dominates in the sea. As the salinity increased from <0.1 to 0.1-2.3, the mixing diagram showed that dissolved radioactive cesium concentrations increased, because of desorption. Desorption from suspended particles explained 36% of dissolved radioactive cesium in estuarine water. However, the dissolved and particulate radioactive cesium concentrations in the sea decreased sharply because of dilution. It is thought that more than 80% of the discharged particulate radioactive cesium was deposited off the river mouth, where the radioactive cesium concentrations in sediment were relatively high (217-2440 Bq kg(-1)). Radioactive cesium that was discharged to the sea was transported southward by currents driven by the density distribution. PMID:26698826

  11. 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)

  12. 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.

  13. Radioactive cesium content in selected food products. Pt. 1. Radioactive cesium content in dried milk (1987-1988)

    International Nuclear Information System (INIS)

    The content of radioactive cesium in dried and dried skimmed milk from selected dairies was double determined. The highest content was found in samples from milk from OSM Siedlce (98 Bq/kg) and skimmed milk from Radzyn Podlaski and Ostroleka, (the former 90, the latter 62 Bq/kg). The lowest level of radioactive cesium was observed in samples from dried milk from Sieradz, Slups, Wrzesnia, Olecko and Elblag (about or below 10 Bq/kg). Although those levels of contamination with radiocesium did not exceed values recommended by FAO they were determined as high for year 1987/88 as compared milk dates from previous 1985 year. (author). 13 refs, 4 tabs

  14. 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.)

  15. Development of transportation package for medical and industrial radioisotope

    International Nuclear Information System (INIS)

    All radioisotope transport packages are imported from abroad. The objective of this study is to develop the RI transport package combining transportable and economical efficiencies. This report describes the objective of project, necessaries, state of related technology, scope and results, proposal for application etc. The scope of the project consist of safety evaluation of medical RI package, preliminary safety evaluation of industrial RI package and evaluation for application of high efficiency shielding material

  16. Application of radioisotopes in oil, gas and petrochemical industries

    International Nuclear Information System (INIS)

    The fundaments and the methodology of the principal radioisotope techniques used in the construction and operation of oil-pipes are described. These techniques deal with gamma radiography of weids, scraper tracking, leak localization in underground pipes and interface detection. The practical use of the mathematical formulas deduced during the theoretical treatment of each method is illustrated through several examples of application. A proceeding for the design of an interface detector based on gamma ray attenuation is presented

  17. 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)

  18. Radioisotope diagnostics of lung pathology in children by clinical data

    International Nuclear Information System (INIS)

    Analysis of clinical data (118 patients) shows convincingly that radioisotope investigations play an important role in recognition of lung pathology in children. Diagnostic value of the method increases especially in those cases when clinical-roentgenological diagnostics of this pathology turns out to be difficult. Expressiveness of scannographic signs permits to differentiate different forms of lung pathology and alongside with this to observe dynamics of pathological processes in lungs which makes it possible to perform selective therapeutic tactics in either concrete situation

  19. 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)

  20. Radioisotopes and fungicide research- present status and future prospects

    International Nuclear Information System (INIS)

    The developments in pesticides and radioisotopes fields were so near to each other that at a very early stage in this history, both became linked together and their usefulness was recognised for faster development. The purpose of this communication is to illustrate the present status these techniques in fungicide research by drawing suitable examples and also to bring out the directions in which future research will be going with the aid of these tools. 72 refs