WorldWideScience

Sample records for alpha-emitting radioisotopes production

  1. Bismuth-213 and actinium-225 -- generator performance and evolving therapeutic applications of two generator-derived alpha-emitting radioisotopes.

    Science.gov (United States)

    Morgenstern, Alfred; Bruchertseifer, Frank; Apostolidis, Christos

    2012-07-01

    The alpha emitters (225)Ac and (213)Bi are promising therapeutic radionuclides for application in targeted alpha therapy of cancer and infectious diseases. Both alpha emitters are available with high specific activity from established radionuclide generators. Their favourable chemical and physical properties have led to the conduction of a large number of preclinical studies and several clinical trials, demonstrating the feasibility, safety and therapeutic efficacy of targeted alpha therapy with (225)Ac and (213)Bi. This review describes methods for the production of (225)Ac and (213)Bi and gives an overview of (225)Ac/(213)Bi radionuclide generator systems. Selected preclinical studies are highlighted and the current clinical experience with (225)Ac and (213)Bi is summarized.

  2. Radioisotopes production and applications

    International Nuclear Information System (INIS)

    Dash, Ashutosh

    2015-01-01

    Application of radioisotopes for both medical and industrial applications constitutes one of the most important peaceful uses of atomic energy. The striking diffusion and the exciting perspective of radioisotope for a plethora of medical and industrial applications are mainly attributable to the penetrating and ionization properties of radiation emanating from radioisotopes. The revolutionary medical applications of radioisotopes for the diagnosis and treatment of a multitude of diseases are causing a rapid expansion of the nuclear medicine field. While the industrial uses of radioisotopes are not expanding as quickly, also require large amounts of radioisotopes. Production of radioisotopes is not only the first step, but also the most crucial for the success as well as sustainable growth of radioisotope applications. With the rapid growth and expanding areas of applications, the demands for isotopes have increased several folds. A number of radioisotopes of different physical half-life, energy of the particle or gamma emission, specific activity and chemistry are now regularly produced both at commercial centers as well as at selected nuclear science research institutes utilizing reactors and cyclotrons to meet the ever growing need

  3. Production and utilization of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Sekine, Toshiaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Matsuoka, Hiromitsu

    1999-03-01

    A plan of developing radioisotopes with a high power proton accelerator of the Neutron Science Project is presented. The status of production and utilization of radioisotopes in Japan is briefly discussed. The radioisotopes to be produced for biomedical use are discussed together with the facility for production of those radioisotopes and for research with the products. (author)

  4. Manual of radioisotope production

    International Nuclear Information System (INIS)

    1966-01-01

    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

  5. Cyclotron Production of Medical Radioisotopes

    Science.gov (United States)

    Ávila-Rodríguez, M. A.; Zárate-Morales, A.; Flores-Moreno, A.

    2010-08-01

    The cyclotron production of radioisotopes for medical applications is gaining increased significance in diagnostic molecular imaging techniques such as PET and SPECT. In this regard, radioisotope production has never been easier or more convenient until de introduction of compact medical cyclotrons in the last few decades, which allowed the use of short-lived radioisotopes in in vivo nuclear medicine studies on a routine basis. This review outlines some general considerations about the production of radioisotopes using charged particle accelerators.

  6. Administration of radioisotope production

    International Nuclear Information System (INIS)

    1964-01-01

    Current developments in atomic energy, and the administrative problems to which they give rise, were surveyed in a seminar on 'Atomic Energy for Atomic Energy Administrators' held at IAEA headquarters from 30 September to 4 October 1963. The ground covered included protection against radiation, isotopes and radiation sources, research reactors, nuclear power, legal matters, technical and scientific administration, the role of the universities, and the Agency's part in assistance to developing countries. The possibilities and limitations of radioisotope production from research reactors were discussed by Dr. G. B. Cook, of the Division of Research and Laboratories, IAEA in this paper.

  7. Production of radioisotopes using accelerators

    International Nuclear Information System (INIS)

    Qaim, S.M.

    1990-01-01

    Accelerator produced radioisotopes find applications in many fields. Most of them are ideally suited for in-vivo studies of physiological functions. A brief review of various types of accelerators used for radioisotope production is given. The 'state of art' technology relevant to the production of radioisotopes is briefly discussed. Some of the recent advances in nuclear data measurements, target development, chemical processing and quality control are described. There appears to be a definite shift from multipurpose accelerators to dedicated machines, and greater emphasis is placed now on the production of radioisotopes with high radionuclidic purity by choosing a suitable nuclear reaction in a proper energy range. (author)

  8. Radioisotope production in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-10-01

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

  9. Radioisotope production in fusion reactors

    International Nuclear Information System (INIS)

    Engholm, B.A.; Cheng, E.T.; Schultz, K.R.

    1986-01-01

    Radioisotope production in fusion reactors is being investigated as part of the Fusion Applications and Market Evaluation (FAME) study. /sup 60/Co is the most promising such product identified to date, since the /sup 60/Co demand for medical and food sterilization is strong and the potential output from a fusion reactor is high. Some of the other radioisotopes considered are /sup 99/Tc, /sup 131/l, several Eu isotopes, and /sup 210/Po. Among the stable isotopes of interest are /sup 197/Au, /sup 103/Rh and Os. In all cases, heat or electricity can be co-produced from the fusion reactor, with overall attractive economics

  10. Present status of OAP radioisotope production

    International Nuclear Information System (INIS)

    Charoen, Sakda

    2006-01-01

    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 131 I (solution and capsule), 131 I-MIBG, 131 I-Hippuran, 153 Sm-EDTMP, 153 Sm-HA, and 99m Tc-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)

  11. BEST medical radioisotope production cyclotrons

    Science.gov (United States)

    Sabaiduc, Vasile; Milton, Bruce; Suthanthiran, Krishnan; Gelbart, W. Z.; Johnson, Richard R.

    2013-04-01

    Best Cyclotron Systems Inc (BCSI) is currently developing 14 MeV, 25 MeV, 35MeV and 70MeV cyclotrons for radioisotope production and research applications as well as the entire spectrum of targets and nuclear synthesis modules for the production of Positron Emission Tomography (PET), Single Photon Emission Computed Tomography (SPECT) and radiation therapy isotopes. The company is a subsidiary of Best Medical International, renowned in the field of medical instrumentation and radiation therapy. All cyclotrons have external negative hydrogen ion sources, four radial sectors with two dees in opposite valleys, cryogenic vacuum system and simultaneous beam extraction on opposite lines. The beam intensity ranges from 400 μA to 1000 μA, depending on the cyclotron energy and application [1].

  12. BEST medical radioisotope production cyclotrons

    Energy Technology Data Exchange (ETDEWEB)

    Sabaiduc, Vasile; Milton, Bruce; Suthanthiran, Krishnan; Johnson, Richard R. [Best Cyclotron Systems Inc., 7-8765 Ash Street, Vancouver, British Columbia, V6P 6T3 (Canada); Gelbart, W. Z. [Advanced System Designs Inc., 5295 Bear Bay Road, Garden Bay, BC, V0N 1S1 (Canada)

    2013-04-19

    Best Cyclotron Systems Inc (BCSI) is currently developing 14 MeV, 25 MeV, 35MeV and 70MeV cyclotrons for radioisotope production and research applications as well as the entire spectrum of targets and nuclear synthesis modules for the production of Positron Emission Tomography (PET), Single Photon Emission Computed Tomography (SPECT) and radiation therapy isotopes. The company is a subsidiary of Best Medical International, renowned in the field of medical instrumentation and radiation therapy. All cyclotrons have external negative hydrogen ion sources, four radial sectors with two dees in opposite valleys, cryogenic vacuum system and simultaneous beam extraction on opposite lines. The beam intensity ranges from 400 {mu}A to 1000 {mu}A, depending on the cyclotron energy and application.

  13. Radioisotopes In Animal Production Research

    International Nuclear Information System (INIS)

    Eduvie, L.O.

    1994-05-01

    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. Radioisotope handling facilities and automation of radioisotope production

    International Nuclear Information System (INIS)

    2004-12-01

    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

  15. The production and application of radioisotopes

    International Nuclear Information System (INIS)

    O'Neill, W.P.; Evans, D.J.R.

    1987-01-01

    This paper outlines the historical evolution of radioisotopes from first concepts and discoveries to significant milestones in their production and the development of applications throughout the world. Regarding production, it addresses the methods that have been used at various stages during this evolution outlining the important findings that have led to further developments. With respect to radioisotope applications, the paper addresses the development of markets in industry, medicine, and agriculture and comments on the size of these markets and their rate of growth. Throughout, the paper highlights the Canadian experience and it also presents a Canadian view of emerging prospects and a forecast of how the future for radioisotopes might develop. (author)

  16. Radioisotope production at PUSPATI - five year programme

    International Nuclear Information System (INIS)

    Yusof Azuddin Ali; Abdul Rahman Mohamad Ali.

    1983-01-01

    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 -2 S -1 ) and a rotary specimen rack (flux density 0.2 x 10 13 n.cm -1 S -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)

  17. Production of radioisotopes with BR2 facilities

    International Nuclear Information System (INIS)

    Fallais, C.J.; Morel de Westfaver, A.; Heeren, L.; Baugnet, J.M.; Gandolfo, J.M.; Boeykens, W.

    1978-01-01

    After a brief account on the isotopes production evolution in the industrialized countries the irradiation devices and the types of standardized capsules used in the BR2 reactor are described as well as the thermal neutron flux. Production of most important radioisotopes like 131 Iodine, 60 Cobalt, 192 Iridium and 99 Molybdenum and their main utilizations (uses)are described. The mean specific activities and the limit of use for different radioisotopes are reported. (A.F.)

  18. Medical Radioisotopes Production Without A Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Van der Keur, H.

    2010-05-15

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

  19. 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.

  20. Commercial Superconducting Electron Linac for Radioisotope Production

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-08-13

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

  1. Development of radioisotope production in the Philippines

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-10-01

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

  2. Alternate methods for the production of radioisotopes

    International Nuclear Information System (INIS)

    Howe, S.D.; Metzger, J.D.; Smith, G.A.

    1996-01-01

    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 99m Tc for gamma-ray imaging and the use of 18 F in positron emission tomography (PET). The 99m Tc (6.01 h) is a daughter of the longer-lived precursor 99 Mo (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 99 Mo this past year when they announced their plans to purchase two MAPLE reactors for the dedicated production of 99 Mo. 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 99 Mo 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 99 Mo and tremendously higher availability of PET isotopes. We have examined the use of an existing high-current, linear accelerator for the production of 99 Mo from the fission of depleted uranium and the production of short-lived isotopes used in PET using a portable source of low-energy antiprotons

  3. Radioisotope production with electron accelerators

    International Nuclear Information System (INIS)

    Brinkman, G.A.

    1978-01-01

    The production of radio isotopes with electron accelerators proceeds mainly by secondary photons (bremsstrahlung), produced in an interaction between the electrons and the Coulomb field of the nuclei of a converter. The production yields depend on: the initial electron energy, the Z and thickness of the bremsstrahlung-converter, the Z, A and the thickness of the target, the geometric set up and the cross section for a particular reaction. In this article the production is only considered for thin bremsstrahlung converters in combination with an electron 'sweep' magnet. Simple formulae are given for the calculations of production yields under standard conditions with only sigmasub(q) (the cross section per equivalent quantum) and f (the fraction of the photons that hit the target) as variables and for the calculations of the dose rate at the production point. The units in which the yields are expressed in the literature (units of sigmasub(q) dose, electron beam intensity, monitor response) are discussed. (Auth.)

  4. HAC and production of radioisotopes and labelled compounds

    International Nuclear Information System (INIS)

    Nozaki, T.

    1984-01-01

    In this paper, the author reviews different methods for the production of radioisotopes and labelled compounds that make use of hot atom reactions. Subsequently he discusses the production of radioisotopes for radiopharmaceuticals; enrichment of (n,γ) products, recoil labelling and related methods (neutron reaction products, cyclotron production, excitation labelling, radiation and discharge induced labelling). The final section offers a survey of radioisotope production using accelerators. Only a selection of the various conditions used in practical RI production is considered. (Auth.)

  5. Present status of radioisotope production in JAERI

    International Nuclear Information System (INIS)

    Yamabayashi, Hisamichi

    1994-01-01

    Since 1962, the technology for producing a wide variety of processed radioisotopes and sealed radiation sources has been developed by using the reactors, JRR-1, JRR-2, JRR-3, JRR-4 and JMTR, and the products have been offered to domestic users. At present, 31 products of 29 nuclides are on the list of processed radioisotopes. Some of those isotopes such as P-32, S-35, Cr-51 and short lived nuclides are produced for regular distribution, but the rest are produced upon request. The radiation sources of Co-60 needles for industrial use, Ir-192 pellets for the nondestructive inspection of pipelines, Gd-153 pellets for the diagnosis of born mineral and seven kinds of brachy therapy Ir-192 and Au-198 grains are produced and distributed regularly. The organic compounds labeled with H-3 and C-14 are widely used. In fiscal year 1992, 34 batches and total amount 12 TBq of processed radioisotopes and 100 batches, 1.2 PBq of radiation sources were produced as scheduled. The development of the techniques for producing the sources emitting high energy β ray used for the diagnosis and treatment of cancer is in progress. The method of producing new isotopes is developed. (K.I.)

  6. High purity materials as targets for radioisotope production: Needs ...

    Indian Academy of Sciences (India)

    Home; Journals; Bulletin of Materials Science; Volume 28; Issue 4. High purity materials as targets for radioisotope production: Needs and challenges ... Application of radioisotopes in medicine has given birth to a new branch, viz. nuclear medicine, wherein radioisotopes are used extensively in the diagnosis and treatment ...

  7. 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)

  8. 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.

  9. 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)

  10. Actinium radioisotope products of enhanced purity

    Science.gov (United States)

    Meikrantz, David Herbert; Todd, Terry Allen; Tranter, Troy Joseph; Horwitz, E. Philip

    2010-06-15

    A product includes actinium-225 (.sup.225Ac) and less than about 1 microgram (.mu.g) of iron (Fe) per millicurie (mCi) of actinium-225. The product may have a radioisotopic purity of greater than about 99.99 atomic percent (at %) actinium-225 and daughter isotopes of actinium-225, and may be formed by a method that includes providing a radioisotope mixture solution comprising at least one of uranium-233 (.sup.233U) and thorium-229 (.sup.229Th), extracting the at least one of uranium-233 and thorium-229 into an organic phase, substantially continuously contacting the organic phase with an aqueous phase, substantially continuously extracting actinium-225 into the aqueous phase, and purifying the actinium-225 from the aqueous phase. In some embodiments, the product may include less than about 1 nanogram (ng) of iron per millicurie (mCi) of actinium-225, and may include less than about 1 microgram (.mu.g) each of magnesium (Mg), Chromium (Cr), and manganese (Mn) per millicurie (mCi) of actinium-225.

  11. Radioisotope production and distribution in Australia

    International Nuclear Information System (INIS)

    Brough, J.

    1986-01-01

    The high quality of radioactive products and services, provided by the Commercial Products Unit of Australian Atomic Energy Agency for industrial and medical applications are discussed. The production program has changed from research driven to being market driven. The Commission in fact not only manufactures radioisotopes and radiopharmaceuticals but also acts as a Centralized Dispensing Service for over sea products. The advantages associated with centralize distribution are discussed. The delivery arrangements and the existed problems are explained. With the unique experience, assistance and advice are provided for many years now to Nuclear Energy Unit at PUSPATI via staff training programs and many visits by the Commission staff to assist in the commissioning of the facilities in which enables PUSPATI to provide Malaysia and surrounding neighbour countries (on a smaller scale) with the similar type of service that the Commission does within Australia. (A.J.)

  12. Technical and economical availability of radioisotopes production in Brazil

    International Nuclear Information System (INIS)

    Lima, J.O.V.

    1981-10-01

    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.) [pt

  13. Alpha Emitting Radionuclides and Radiopharmaceuticals for Therapy

    International Nuclear Information System (INIS)

    Chérel, Michel; Barbet, Jacques

    2013-01-01

    Today, cancer treatments mainly rely on surgery or external beam radiation to remove or destroy bulky tumors. Chemotherapy is given when tumours cannot be removed or when dissemination is suspected. However, these approaches cannot permanently treat all cancers and relapse occurs in up to 50% of the patients’ population. Radioimmunotherapy (RIT) and peptide receptor radionuclide therapy (PRRT) are effective against some disseminated and metastatic diseases, although they are rarely curative. Most preclinical and clinical developments in this field have involved electron-emitting radionuclides, particularly iodine-131, yttrium-90 and lutetium-177. The large range of the electrons emitted by these radionuclides reduces their efficacy against very small tumour cell clusters or isolated tumour cells present in residual disease and in many haematological tumours (leukaemia, myeloma). The range of alpha particles in biological tissues is very short, less than 0.1 mm, which makes alpha emitters theoretically ideal for treatment of such isolated tumour cells or micro-clusters of malignant cells. Thus, over the last decade, a growing interest for the use of alpha-emitting radionuclides has emerged. Research on targeted alpha therapy (TAT) began years ago in Nantes through cooperation between Subatech, a nuclear physics laboratory, CRCNA, a cancer research centre with a nuclear oncology team and ITU (Karlsruhe, Germany). CD138 was demonstrated as a potential target antigen for Multiple Myeloma, which is a target of huge clinical interest particularly suited for TAT because of the disseminated nature of the disease consisting primarily of isolated cells and small clusters of tumour cells mainly localized in the bone marrow. Thus anti-CD138 antibodies were labelled with bismuth-213 from actinium-225/bismuth-213 generators provided by ITU and used to target multiple myeloma cells. In vitro studies showed cell cycle arrest, synergism with chemotherapy and very little induction

  14. Production of medical radioisotopes with linear accelerators.

    Science.gov (United States)

    Starovoitova, Valeriia N; Tchelidze, Lali; Wells, Douglas P

    2014-02-01

    In this study, we discuss producing radioisotopes using linear electron accelerators and address production and separation issues of photoneutron (γ,n) and photoproton (γ,p) reactions. While (γ,n) reactions typically result in greater yields, separating product nuclides from the target is challenging since the chemical properties of both are the same. Yields of (γ,p) reactions are typically lower than (γ,n) ones, however they have the advantage that target and product nuclides belong to different chemical species so their separation is often not such an intricate problem. In this paper we consider two examples, (100)Mo(γ,n)(99)Mo and (68)Zn(γ,p)(67)Cu, of photonuclear reactions. Monte-Carlo simulations of the yields are benchmarked with experimental data obtained at the Idaho Accelerator Center using a 44MeV linear electron accelerator. We propose using a kinematic recoil method for photoneutron production. This technique requires (100)Mo target material to be in the form of nanoparticles coated with a catcher material. During irradiation, (99)Mo atoms recoil and get trapped in the coating layer. After irradiation, the coating is dissolved and (99)Mo is collected. At the same time, (100)Mo nanoparticles can be reused. For the photoproduction method, (67)Cu can be separated from the target nuclides, (68)Zn, using standard exchange chromatography methods. Monte-Carlo simulations were performed and the (99)Mo activity was predicted to be about 7MBq/(g(⁎)kW(⁎)h) while (67)Cu activity was predicted to be about 1MBq/(g(⁎)kW(⁎)h). Experimental data confirm the predicted activity for both cases which proves that photonuclear reactions can be used to produce radioisotopes. Lists of medical isotopes which might be obtained using photonuclear reactions have been compiled and are included as well. Copyright © 2013 Elsevier Ltd. All rights reserved.

  15. Developments in radioisotope production and labelling of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Lambrecht, R.M.

    1998-01-01

    Recent developments in both reactor and accelerator production of radioisotopes finding applications in nuclear medicine and in biomedical research are summarised. The priorities for the production of 48 different cyclotron radioisotopes; and for 42 reactor produced radioisotopes finding biomedical applications are identified. Each includes 5 generator systems. The rapid expansion of cyclotron based radioisotope production and automated synthesis of short-lived radiopharmaceuticals with the position-emitting radionuclides continues to gain momentum. Recent feasibility studies of the cyclotron production of 186 Re, 99m Tc and of 99 Mo are cited as examples of motivation to develop accelerator alternatives to use of nuclear reactors for medical radioisotope production. Examples of SPET and PET radiopharmaceuticals labelled with 131 I, 123 I, 124 I, 18 F, and with therapeutic radionuclides are highlighted. (author)

  16. Radiation protection programme for a radioisotope production facility

    International Nuclear Information System (INIS)

    Makgato, Thutu Nelson

    2015-02-01

    The present project reviews reactor based radioisotope production facilities. An overview of techniques and methodologies used as well as laboratory facilities necessary for the production process are discussed. Specific details of reactor based production and processing of more commonly used industrial and pharmaceutical radioisotopes are provided. Ultimately, based on facilities and techniques utilized as well as the associated hazard assessment, a proposed radiation protection programme is discussed. Elements of the radiation protection programme will also consider lessons from recent incidents and accidents encountered in radioisotope production facilities. (au)

  17. Radioisotope production with a medical cyclotron

    International Nuclear Information System (INIS)

    Silvester, D.J.

    1974-01-01

    The cyclotron of Hammersmith hospital in England was completed and started the operation in 1955. The feature is in its design operable at high beam current, reaching 500μA in internal beam and 300μA in external beam. In 1960's, twelve nuclides of radioactive pharmaceuticals were produced with the cyclotron. C-11, N-13 and O-15 have been used in the form of radioactive gases such as CO or H 2 O to test lung functions. F-18 has been used for bone scanning. K-43 is employed in the research of electrolyte balancing together with Na-24 and Br-77. Fe-52 is utilized in iron ion researches as a tracer. Cs-129 is highly evaluated as an isotope for imaging cardiac clogging part. Radioisotopes must be much more used in the examination of in vivo metabolic function. For this purpose, peculiarly labelled compounds should be further developed. It is welcome that the persons paying attention to the medical prospect of cyclotrons are increasing. The author hopes to continue his endeavour to find new products made with the cyclotron for human welfare. (Wakatsuki, Y.)

  18. Production and application of radioisotopes - a Canadian perspective

    International Nuclear Information System (INIS)

    O'Neill, W.P.; Evans, D.J.R.

    1988-01-01

    This paper outlines the historical evolutions of radioisotopes from first concepts and discoveries to significant milestones in their production and the development of applications throughout the world. Regarding production, it addresses the methods that have been used at various stages during this evolution outlining the important findings that have led to further developments. With respect to radioisotope applications, the paper addresses the development of markets in industry, medicine, and agriculture and comments on the size of these markets and their rate of growth. Throughout, the paper highlights the Canadian experience and it also presents a Canadian view of emerging prospects and a forecast of how the future for radioisotopes might develop

  19. Alpha-emitting nuclides in the marine environment

    Science.gov (United States)

    Pentreath, R. J.

    1984-06-01

    The occurrence of alpha-emitting nuclides and their daughter products in the marine environment continues to be a subject of study for many reasons. Those nuclides which occur naturally, in the uranium, thorium and actinium series, are of interest because of their value in determining the rates of geological and geochemical processes in the oceans. Studies of them address such problems as the determination of rates of transfer of particulate matter, deposition rates, bioturbation rates, and so on. Two of the natural alpha-series nuclides in which a different interest has been expressed are 210Po and 226Ra, because their concentrations in marine organisms are such that they contribute to a significant fraction of the background dose rates sustained both by the organisms themselves and by consumers of marine fish and shellfish. To this pool of naturally-occurring nuclides, human activities have added the transuranium nuclides, both from the atmospheric testing of nuclear devices and from the authorized discharges of radioactive wastes into coastal waters and the deep sea. Studies have therefore been made to understand the chemistry of these radionuclides in sea water, their association with sedimentary materials, and their accumulation by marine organisms, the last of these being of particular interest because the transuranics are essentially "novel" elements to the marine fauna and flora. The need to predict the long-term behaviour of these nuclides has, in turn, stimulated research on those naturally-occurring nuclides which may behave in a similar manner.

  20. Studies on the production and application of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-09-01

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

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

    International Nuclear Information System (INIS)

    Liu Yishu

    2000-01-01

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

  2. Commercial production of radioisotopes for nuclear medicine, 1970-1980

    International Nuclear Information System (INIS)

    Lamb, J.F.

    1981-01-01

    The first small cyclotrons were installed for commercial production of radioisotopes at New England Nuclear Corporation, Billerica, Massachusetts, and at Medi-Physics, Emeryville, California. Both machines were Cyclotron Corporation Cs-22 multiple particle, fixed energy cyclotrons. In the ten years that followed, the total number of commercial radioisotope producing small accelerators has grown to ten, with four more projected for 1981. The beam energy requirement for the first accelerators was modest; 22 MeV protons, 12 MeV deuterons, 24 MeV He-4, and 31 MeV He-3; and commercial radioisotope production for nuclear medicine utilized all four particles. The first product available from cyclotron production was fluorine-18 from the 16 O( 3 He, p) 18 F reaction. Injected intravenously as no-carrier-added Na 18 F, the radionuclide quickly concentrated in bone, providing the nuclear medicine physician with diagnostic information on skeletal abnormalities including metastatic bone disease

  3. Cancer radioimmunotherapy with alpha-emitting nuclides

    Energy Technology Data Exchange (ETDEWEB)

    Couturier, Olivier [INSERM U 601, Nantes (France); Place Alexis Ricordeau, Department of Nuclear Medicine, Nantes, Cedex (France); Supiot, Stephane; Degraef-Mougin, Marie; Faivre-Chauvet, Alain; Carlier, Thomas; Chatal, Jean-Francois; Davodeau, Francois; Cherel, Michel [INSERM U 601, Nantes (France)

    2005-04-01

    In lymphoid malignancies and in certain solid cancers such as medullary thyroid carcinoma, somewhat mixed success has been achieved when applying radioimmunotherapy (RIT) with {beta}-emitters for the treatment of refractory cases. The development of novel RIT with {alpha}-emitters has created new opportunities and theoretical advantages due to the high linear energy transfer (LET) and the short path length in biological tissue of {alpha}-particles. These physical properties offer the prospect of achieving selective tumoural cell killing. Thus, RIT with {alpha}-emitters appears particularly suited for the elimination of circulating single cells or cell clusters or for the treatment of micrometastases at an early stage. However, to avoid non-specific irradiation of healthy tissues, it is necessary to identify accessible tumoural targets easily and rapidly. For this purpose, a small number of {alpha}-emitters have been investigated, among which only a few have been used for in vivo preclinical studies. Another problem is the availability and cost of these radionuclides; for instance, the low cost and the development of a reliable actinium-225/bismuth-213 generator were probably determining elements in the choice of bismuth-213 in the only human trial of RIT with an {alpha}-emitter. This article reviews the literature concerning monoclonal antibodies radiolabelled with {alpha}-emitters that have been developed for possible RIT in cancer patients. The principal radio-immunoconjugates are considered, starting with physical and chemical properties of {alpha}-emitters, their mode of production, the possibilities and difficulties of labelling, in vitro studies and finally, when available, in vivo preclinical and clinical studies. (orig.)

  4. Cancer radioimmunotherapy with alpha-emitting nuclides.

    Science.gov (United States)

    Couturier, Olivier; Supiot, Stéphane; Degraef-Mougin, Marie; Faivre-Chauvet, Alain; Carlier, Thomas; Chatal, Jean-François; Davodeau, François; Cherel, Michel

    2005-05-01

    In lymphoid malignancies and in certain solid cancers such as medullary thyroid carcinoma, somewhat mixed success has been achieved when applying radioimmunotherapy (RIT) with beta-emitters for the treatment of refractory cases. The development of novel RIT with alpha-emitters has created new opportunities and theoretical advantages due to the high linear energy transfer (LET) and the short path length in biological tissue of alpha-particles. These physical properties offer the prospect of achieving selective tumoural cell killing. Thus, RIT with alpha-emitters appears particularly suited for the elimination of circulating single cells or cell clusters or for the treatment of micrometastases at an early stage. However, to avoid non-specific irradiation of healthy tissues, it is necessary to identify accessible tumoural targets easily and rapidly. For this purpose, a small number of alpha-emitters have been investigated, among which only a few have been used for in vivo preclinical studies. Another problem is the availability and cost of these radionuclides; for instance, the low cost and the development of a reliable actinium-225/bismuth-213 generator were probably determining elements in the choice of bismuth-213 in the only human trial of RIT with an alpha-emitter. This article reviews the literature concerning monoclonal antibodies radiolabelled with alpha-emitters that have been developed for possible RIT in cancer patients. The principal radio-immunoconjugates are considered, starting with physical and chemical properties of alpha-emitters, their mode of production, the possibilities and difficulties of labelling, in vitro studies and finally, when available, in vivo preclinical and clinical studies.

  5. Cancer radioimmunotherapy with alpha-emitting nuclides

    International Nuclear Information System (INIS)

    Couturier, Olivier; Supiot, Stephane; Degraef-Mougin, Marie; Faivre-Chauvet, Alain; Carlier, Thomas; Chatal, Jean-Francois; Davodeau, Francois; Cherel, Michel

    2005-01-01

    In lymphoid malignancies and in certain solid cancers such as medullary thyroid carcinoma, somewhat mixed success has been achieved when applying radioimmunotherapy (RIT) with β-emitters for the treatment of refractory cases. The development of novel RIT with α-emitters has created new opportunities and theoretical advantages due to the high linear energy transfer (LET) and the short path length in biological tissue of α-particles. These physical properties offer the prospect of achieving selective tumoural cell killing. Thus, RIT with α-emitters appears particularly suited for the elimination of circulating single cells or cell clusters or for the treatment of micrometastases at an early stage. However, to avoid non-specific irradiation of healthy tissues, it is necessary to identify accessible tumoural targets easily and rapidly. For this purpose, a small number of α-emitters have been investigated, among which only a few have been used for in vivo preclinical studies. Another problem is the availability and cost of these radionuclides; for instance, the low cost and the development of a reliable actinium-225/bismuth-213 generator were probably determining elements in the choice of bismuth-213 in the only human trial of RIT with an α-emitter. This article reviews the literature concerning monoclonal antibodies radiolabelled with α-emitters that have been developed for possible RIT in cancer patients. The principal radio-immunoconjugates are considered, starting with physical and chemical properties of α-emitters, their mode of production, the possibilities and difficulties of labelling, in vitro studies and finally, when available, in vivo preclinical and clinical studies. (orig.)

  6. Safety evaluation for regulatory management of Australian radioisotope production facilities.

    Science.gov (United States)

    Sarkar, S

    2009-01-01

    This paper describes the approach of Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) in the regulatory management of Radioisotope Production facilities in Australia. ARPANSA is the regulatory authority for commonwealth entities operating nuclear installations including Radioisotope Production facilities. In assessing the application for operating nuclear installations the ARPANSA assessors prepare a Safety Evaluation Report, which is a recommendation to the Chief Executive Officer (CEO) of ARPANSA whether to issue a licence to site, construct, operate and decommission facilities. In particular, the CEO must take into account international best practice in radiation protection and nuclear safety when making licence decisions.

  7. Solid targets for production of radioisotopes with cyclotron

    International Nuclear Information System (INIS)

    Paredes G, L.; Balcazar G, M.

    1999-01-01

    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)

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

    International Nuclear Information System (INIS)

    Silva, A.G. da; Lemos, O.F.; Britto, J.L.O. de; Osso, J.A.; Bastos, M.A.V.; Braghirolli, A.M.S.; Chamma, D.F.S.; Newton, G.W.A.; Weinreich, R.

    1982-01-01

    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) [pt

  9. Cyclic irradiation method for production of radioisotope tracers using ...

    African Journals Online (AJOL)

    Cyclic Irradiation Method (CIM) involving repeated irradiation of samples at regular time intervals to build up activity has been adopted for the production of 82 Br, 72 Ga, 140La, 24 Na and 46 Sc isotopes using the low power Ghana Research Reactor-1. The results indicate that the specific activities of radioisotopes from ...

  10. Historical sketch of the discovery, production, and application of radioisotopes

    International Nuclear Information System (INIS)

    Williams, C.

    1975-01-01

    The Joliot-Curies made the first artificial radioisotope ( 30 P) by bombarding aluminum with alpha particles. The development of the cyclotron and other high-energy particle accelerators in the early 1930's led to the production of numerous radioisotopes in measurable quantities. By the beginning of the 1950's, with the abundant neutron fluxes available at the U. S. Atomic Commission reactors, radioisotopes of many species really became abundant. Naturally occurring radioactive lead had been used very sparingly as tracers as far back as 1918 in determining chemical solubility and in 1923 in plant uptake from lead solutions. Now many new uses were developed and tested as tracers in medical diagnosis, agricultural, and industrial chemical and metallurigical processes. Many therapeutic applications were tested. The industrial labs developed thickness and level gauges for control of various manufacturing processes. Cobalt gamma-ray irradiators were developed for medical therapy and have also been used for sterilization of surgical instruments and materials, for food preservation, and for initiation of certain chemical reactions. The most significant development in the 1960's was the rapidly increasing role of private industry in taking over the development, production, sales, as well as research, into new methods of production and applications of radioisotopes

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

    International Nuclear Information System (INIS)

    Terentyev, G.O.

    2001-01-01

    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)

  12. 77 FR 21592 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2012-04-10

    ... Applications for the Production of Radioisotopes AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim... Licensing of Non-Power Reactors: Format and Content,'' for the production of radioisotopes and NUREG-1537...: Standard Review Plan and Acceptance Criteria,'' for the production of radioisotopes. The ISG augmenting...

  13. 76 FR 63668 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2011-10-13

    ... Applications for the Production of Radioisotopes AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim... Licensing of Non-Power Reactors: Format and Content,'' for the Production of Radioisotopes and NUREG-1537...: Standard Review Plan and Acceptance Criteria,'' for the Production of Radioisotopes (chapters 7-18 of the...

  14. 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.

  15. Production capabilities in US nuclear reactors for medical radioisotopes

    International Nuclear Information System (INIS)

    Mirzadeh, S.; Callahan, A.P.; Knapp, F.F. Jr.; Schenter, R.E.

    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

  16. 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.

  17. Production of radioisotopes within a plasma focus device

    International Nuclear Information System (INIS)

    Angeli, E.; Tartari, A.; Frignani, M.; Molinari, V.; Mostacci, D.; Rocchi, F.; Sumini, M. . E-mail address of corresponding author: domiziano.mostacci@mail.ing.unibo.it

    2005-01-01

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

  18. Toxicity of inhaled alpha-emitting radionuclides - Status report

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Guilmette, R.A.; Gillett, N.A.; Diel, J.H.; Lundgren, D.L.; Hahn, F.F.; Boecker, B.B.; McClellan, R.O.

    1988-01-01

    The toxicity of inhaled alpha-emitting radionuclides is being investigated in a series of interrelated dose-response studies. Dogs, rodents, and nonhuman primates have been exposed to monodisperse or polydisperse aerosols of the oxides of 239 Pu, 238 Pu, 241 Am, or 244 Cm to measure the relative importance of average organ dose, local dose around particles, specific activity, chemical form, particle size, and number of particles inhaled to the development of biological effects. The influence of animal species, age at exposure, and pre-existing lung disease, as well as the effects of repeated exposure, are also being studied, because they may influence the toxicity of these radionuclides. (author)

  19. Production, control and utilization of radioisotopes including radiopharmaceuticals

    International Nuclear Information System (INIS)

    Muenze, R.

    1985-05-01

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

  20. Spallation production of neutron deficient radioisotopes in North America

    International Nuclear Information System (INIS)

    Jamriska, D.J.; Peterson, E.J.; Carty, J.

    1997-01-01

    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. Charged particle radioisotope production at Instituto de Engenharia Nuclear - IEN

    International Nuclear Information System (INIS)

    Lemos Junior, O.F.

    1992-05-01

    A variable energy isochronous cyclotron (CV-28) was installed in 1974 at the Instituto de Engenharia Nuclear in Rio de Janeiro, with the purpose, among others, of irradiating suitable targets to produce radioisotopes for medical diagnostic studies. This papers is an overview of the work done in the last two decades and reports the present status on the production of iodine-123 and gallium-67. (author)

  2. Production of radioisotopes with accelerators, (2)

    International Nuclear Information System (INIS)

    Shiokawa, Takanobu; Yoshihara, Kenji; Yagi, Masuo; Kondo, Kenjiro.

    1977-01-01

    Description was made as to many items which must be thought concretely in case of producing RI by using bremsstrahlung generated from an electron accelerator, and basic knowledge and general techniques necessary for it. Furthermore, actual examples of the production were mentioned. As an applied case, the utilization of accelerators to direct production of labelled compounds was also described. As basic knowledge, an electron accelerator used for creating nuclear reaction and photonuclear reaction by γ-ray and generation of bremsstrahlung, irradiation methods for efficient activation in order to produce RI efficiently, and calculation method of the number of atoms formed from photonuclear reaction by irradiation of bremsstrahlung, which has continuous spectrum of the maximum energy, were explained. (Kanao, N.)

  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. Spallation production of neutron deficient radioisotopes in North America

    International Nuclear Information System (INIS)

    Jamriska, D.J.; Peterson, E.J.; Carty, J.

    1997-01-01

    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

  5. Operation status and prospect of radioisotope production facility in HANARO

    International Nuclear Information System (INIS)

    Kim, Minjin; Jung, H.S.

    2012-01-01

    At the RIPF at HANARO, Radioisotopes for industrial and medical purpose are produced and research and development for various radioisotopes are carried out. Major products include Ir-192 for NDT, I-131 for treatment and diagnosis of thyroid cancer, Mo-99/Tc-99m Generator for imaging diagnosis of cancer. Production of radioisotope and radiopharmaceutical is being increased every year. Due to world-wide unstableness in the supply of Mo-99, a technology to produce (n,γ)Mo-99 generator at HANARO had been developed as a short term countermeasure. It will be available by the end of 2012. As a long term countermeasure, we are trying to build a new fully dedicated isotope reactor that will produce Fission Mo-99. At present, utilization of RIPF at HANARO is being increased. However when the construction of a new dedicated isotope reactor is completed in 2016, the role of the existing facility and new facility should be established accordingly so that none of the facilities are idling. In the near future, when the prospect of a utilization plan is completed, we expect an opportunity to present the result. (author)

  6. Report of a Technical Meeting on ''Alpha emitting radionuclides and radiopharmaceuticals for therapy''

    International Nuclear Information System (INIS)

    2013-01-01

    Considering the high potential of α-emitters for future development of radionuclide therapy, the International Atomic Energy Agency (IAEA) organized a Technical Meeting on ‘Alpha Emitting Radionuclides and Radiopharmaceuticals for Therapy’, from June 24 to 28, 2013, at IAEA Headquarters in Vienna with the purpose of gathering eminent Experts in the field and discuss with them the status and future perspectives of the field. Sixteen Experts and two External Observers from ten different countries, and four IAEA Technical Officers attended this meeting. Outstanding lectures have been presented covering all relevant aspects of α-therapy, which were followed by extensive discussions and analysis. Selected arguments encompassed production methods and availability of alpha-emitting radionuclides, labelling chemistry of alpha-emittting radioelements, design and development of target-specific radiopharmaceuticals, physical principles of alpha-particle dosimetry and advanced dosimetric models, biological effects of alpha radiation at the cellular level, on-going preclinical and clinical studies with new radiopharmaceuticals, results of clinical trials on the use of radium-223 chloride solutions for the treatment of metastatic bone cancer. The broad scientific background of invited components of the Experts’ panel conferred a strong interdisciplinary trait to the overall discussion and stimulated a critical analysis of this emerging unexplored field. Results of this comprehensive overview on alpha therapy, including recommendations to the Agency on suitable initiatives that may help to promote and spread the knowledge to Members States on this emerging therapeutic modality, are summarized in the present Report

  7. A novel superconducting cyclotron for therapy and radioisotope production

    Science.gov (United States)

    Calabretta, Luciano; Cuttone, Giacomo; Maggiore, Mario; Re, Maurizio; Rifuggiato, Danilo

    2006-06-01

    The design of a four sector compact superconducting cyclotron, able to accelerate up to 250 A MeV light ions with charge/mass ratio 0.5, is in progress. Light ions like 12C 6+, 10B 5+, 6Li 3+ will be extracted by electrostatic deflectors while H 2+ ions can be extracted also by stripping, therefore a beam power of 10 kW or more is available. This cyclotron can be used for radiotherapy with protons or carbon ions and also to drive a facility for production of unusual medical radioisotopes. The main parameters and some features of the machine are here presented.

  8. Development of stable isotope separation technology for radioisotope production

    International Nuclear Information System (INIS)

    Jeong, Do Young; Kim, Cheol Jung; Park, Kyung Bae

    2003-05-01

    The ultimate goal of this project is to construct the domestic production system of stable isotopes O-18 and Tl-203 used as target materials in accelerator for the production of medical radioisotopes F-18 and Tl-201, respectively. In order to achieve this goal, diode laser spectroscopic analytical system was constructed and automatic measurement computer software for the direct analysis of H 2 16 O/H 2 18 O ratio were developed. Distillation process, laser process, and membrane diffusion process were analyzed for the evaluation of O-18 production. And electromagnetic process, plasma process, and laser process were analyzed for the evaluation of Tl-203 production. UV laser system, IR laser system, and detailed system Tl-203 production were designed. Finally, current and future worldwide demand/supply of stable isotopes O-18 and Tl-203 were estimated

  9. Research reactor production of radioisotopes for medical use

    International Nuclear Information System (INIS)

    Mani, R.S.

    1985-01-01

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

  10. Production of radioisotopes within a plasma focus device

    Directory of Open Access Journals (Sweden)

    Angeli Ergisto

    2005-01-01

    Full Text Available In recent years, research conducted in the US and in Italy has demonstrated production of radioisotopes in plasma focus devices, and particularly, on what could be termed "endogenous" production, to wit, production within the plasma it self, as opposed to irradiation of tar gets. 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 re viewed, both with regards to cross section models and to experimental production of radio isotopes. Possible out comes and further development are discussed.

  11. Current status of radioisotope production in the year of 2003

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seon Duk; Bang, H. S.; Shin, B. C

    2004-02-01

    The RIPF(Radio Isotope Production Facility) is the unique facility in Korea which has been used for the isotope production. Through the survey on the radioisotope quantities of production and consumption in the domestic industry, we were trying to show the trend of isotope production. The quantities of Tc-99m, Mo-99, Cr-51, I-131 solution and I-131 capsule produced in the hot cell and clean room of RIPF were compared with the quantities at the previous year. Also the output of the labeling compound such as Hippuran, MIBG, RIHSA, Phytate, MDP, DISIDA, DTPA, etc was compared with the previous year by the radioactivity and the vial. We treated the sum of selling amount of industrial isotopes and tracer isotopes and the status of technical supports also.

  12. Energy-Recovery Linacs for Commercial Radioisotope Production

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Rolland Paul [Muplus, Inc., Newport News, VA (United States)

    2016-11-19

    Most radioisotopes are produced by nuclear reactors or positive ion accelerators, which are expensive to construct and to operate. Photonuclear reactions using bremsstrahlung photon beams from less-expensive electron linacs can generate isotopes of critical interest, but much of the beam energy in a conventional electron linac is dumped at high energy, making unwanted radioactivation. The largest part of this radioactivation may be completely eliminated by applying energy recovery linac technology to the problem with an additional benefit that the energy cost to produce a given amount of isotope is reduced. Consequently, a Superconducting Radio Frequency (SRF) Energy Recovery Linac (ERL) is a path to a more diverse and reliable domestic supply of short-lived, high-value, high-demand isotopes at a cost lower than that of isotopes produced by reactors or positive-ion accelerators. A Jefferson Lab approach to this problem involves a thin photon production radiator, which allows the electron beam to recirculate through rf cavities so the beam energy can be recovered while the spent electrons are extracted and absorbed at a low enough energy to minimize unwanted radioactivation. The thicker isotope photoproduction target is not in the beam. MuPlus, with Jefferson Lab and Niowave, proposed to extend this ERL technology to the commercial world of radioisotope production. In Phase I we demonstrated that 1) the ERL advantage for producing radioisotopes is at high energies (~100 MeV), 2) the range of acceptable radiator thickness is narrow (too thin and there is no advantage relative to other methods and too thick means energy recovery is too difficult), 3) using optics techniques developed under an earlier STTR for collider low beta designs greatly improves the fraction of beam energy that can be recovered (patent pending), 4) many potentially useful radioisotopes can be made with this ERL technique that have never before been available in significant commercial quantities

  13. Energy-Recovery Linacs for Commercial Radioisotope Production

    International Nuclear Information System (INIS)

    Johnson, Rolland Paul

    2016-01-01

    Most radioisotopes are produced by nuclear reactors or positive ion accelerators, which are expensive to construct and to operate. Photonuclear reactions using bremsstrahlung photon beams from less-expensive electron linacs can generate isotopes of critical interest, but much of the beam energy in a conventional electron linac is dumped at high energy, making unwanted radioactivation. The largest part of this radioactivation may be completely eliminated by applying energy recovery linac technology to the problem with an additional benefit that the energy cost to produce a given amount of isotope is reduced. Consequently, a Superconducting Radio Frequency (SRF) Energy Recovery Linac (ERL) is a path to a more diverse and reliable domestic supply of short-lived, high-value, high-demand isotopes at a cost lower than that of isotopes produced by reactors or positive-ion accelerators. A Jefferson Lab approach to this problem involves a thin photon production radiator, which allows the electron beam to recirculate through rf cavities so the beam energy can be recovered while the spent electrons are extracted and absorbed at a low enough energy to minimize unwanted radioactivation. The thicker isotope photoproduction target is not in the beam. MuPlus, with Jefferson Lab and Niowave, proposed to extend this ERL technology to the commercial world of radioisotope production. In Phase I we demonstrated that 1) the ERL advantage for producing radioisotopes is at high energies (~100 MeV), 2) the range of acceptable radiator thickness is narrow (too thin and there is no advantage relative to other methods and too thick means energy recovery is too difficult), 3) using optics techniques developed under an earlier STTR for collider low beta designs greatly improves the fraction of beam energy that can be recovered (patent pending), 4) many potentially useful radioisotopes can be made with this ERL technique that have never before been available in significant commercial quantities

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-03-01

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

  15. Production of Radioisotopes in Pakistan Research Reactor: Past, Present and Future

    International Nuclear Information System (INIS)

    Mushtaq, A.

    2013-01-01

    Radioisotope production to service different sectors of economic significance constitutes an important ongoing activity of many national nuclear programs. 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. The availability of short-lived radionuclides from radionuclide generators provides an inexpensive and convenient alternative to in-house radioisotope production facilities such as cyclotrons and reactors. The reactor offers large volume for irradiation, simultaneous irradiation of several samples, economy of production and possibility to produce a wide variety of radioisotopes. The accelerator-produced isotopes relatively constitute a smaller percentage of total use. (author)

  16. Automatized target devices for radioisotope production at the RITs cyclotron

    International Nuclear Information System (INIS)

    Bogdanov, P.V.; Ivanov, V.V.; Karasev, B.G.

    1981-01-01

    An automation target device intended for isotope production on the internal beam of the RITs cyclotron is decribed. The target device comprises the following main units: target head, vacuum lock, charging device, transport system for bringing the target for charging; mechanism of target discharge transport device, control interlocking and signalling control system of target radiation power. The automation target device permits radioisotope production on the cyclotron in commercial scales with automation substitution of irradiated targets. The time of substitution of one of six targets makes up only 5 min. The time of charging a new group of targets to the charge device - 60 min. Contact of the personnel with irradiated targets is practically excluded and the necessity of entering the cyclotron room for maintenance of the plant is reduced to the minimum [ru

  17. Production of I-125 radioisotope in sodium iodide solution

    International Nuclear Information System (INIS)

    Nabardi, B.; Gourani, M.

    2004-01-01

    Application: The Radioisotope Iodine-125 has rather long half-life, and high dose range of Gamma radiation. It will be used in two cases,in our radioisotope production department: 1-To label Radioimmunoassay Kits (RIA): T3, T4 and TSH for IN V ITRO investigation of Thyroid glands, in our Nuclear Medical Center in IRAN. We just started to set up Hot cell facilities and in cell equipment to supply Iodine-125 for our Radioimmunoassay Group.In this section. The above Iodine-125 will be used for labelling of their Radioimmunoassay products for Thyroid functions and also for screening of newborns for Thyroid deficiency. 2-We have also just start, the make and supply particular granules of Iodine-125 by Silver coated Iodine-125 directly and also indirectly, on the Palladium, coated Silver Wire to be used in Brachytherapy applications. Production: After filling Target with 15 g of natural Xe gas by excellent technology and closed in leak-tight allowing reactor irradiation. The target is irradiated in a nuclear reactor for 3 weeks optimally at a thermal neutron flux around Φ= 1*10 14 n.cm -2 .s -1 .After transferring irradiated target to hot cell, The aluminium capsule is opened by putting it into the punching apparatus and pushing the needle into the bottom of the aluminium capsule by turning the handle counter-clockwise. When the needle punches the aluminium. The Xe gas is released into the chimney and the I-125 radioisotope is adsorbed on the inside wall of the aluminium capsule. After this the opened aluminium capsule is pulled off from the needle by turning the handle clockwise. The opened capsule is ready to distillation. Preparation of the distillation oven and equipment: on the first occasion the oven should be heated two-times up to 550 o C for two hours each to eliminate potential contamination. After it the radioactive aluminium capsule is put into the oven and vacuum is started. This is followed by switching on the heating. The distillation is followed through

  18. Revisiting homogeneous suspension reactors for production of radioisotopes

    International Nuclear Information System (INIS)

    Pasqualini, E.E.

    2010-01-01

    Some 50 years ago in Geneva Conferences I, II and III (1955. 1958 and 1964) on the Peaceful Uses of Atomic Energy, and also in Vienna Symposium on Reactor Experiments (1961), several papers where presented by different countries referring to advances in homogeneous suspension reactors. In particular the Dutch KEMA Suspension Test Reactor (KSTR) was developed, built and successfully operated in the sixties and seventies. It was a 1MWth reactor in which a suspension (6 microns spheres) of mixed UO 2 /ThO 2 in light water was circulated in a closed loop through a sphere-shaped vessel. One of the basic ideas on these suspension reactors was to apply the fission recoil separation effect as a means of purification of the fuel: the non-volatile fission products can be adsorbed in dispersed active charcoal and removed from the liquid. Undoubtedly, this method can present some advantages and better yields for the production of Mo-99 and other short lived radioisotopes, since they have to be extracted from a liquid in which practically no uranium is present. Details are mentioned of the different aspects that have been taken into account and which ones could be added in the corresponding actualization of suspension reactors for radioisotope production. In recent years great advances have been made in nanotechnology that can be used in the tailoring of fuel particles and adsorbent media. Recently, in CNEA Buenos Aires, a new facility has been inaugurated and is being equipped and licensed for laboratory experiments and preparative synthesis of nuclear nanoparticles. RA-6 and RA-3 experimental reactors in Argentina can be used for in-pile testing. (author)

  19. The Texas A&M Radioisotope Production and Radiochemistry Program

    Energy Technology Data Exchange (ETDEWEB)

    Akabani, Gamal [Texas A & M Univ., College Station, TX (United States). Dept. of Nuclear Engineering. Dept. of Veterinary Integrative Biosciences

    2016-10-28

    The main motivation of the project at Texas A&M University was to carry out the production of critically needed radioisotopes used in medicine for diagnostics and therapy, and to establish an academic program in radionuclide production and separation methods. After a lengthy battle with the Texas A&M University Radiation Safety Office, the Texas Department of State Health Services granted us a license for the production of radionuclides in July 2015, allowing us to work in earnest in our project objectives. Experiments began immediately after licensing, and we started the assembly and testing of our target systems. There were four analytical/theoretical projects and two experimental target systems. These were for At-211 production and for Zn-62/Cu-62 production. The theoretical projects were related to the production of Mo-99/Tc-99m using a) a subcritical aqueous target system and b) production of Tc-99m from accelerator-generated Mo-99 utilizing a photon-neutron interaction with enriched Mo-100 targets. The two experimental projects were the development of targetry systems and production of At-211 and Zn-62/Cu-62 generator. The targetry system for At-211 has been tested and production of At-211 is chronic depending of availability of beam time at the cyclotron. The installation and testing of the targetry system for the production of Zn-62/Cu-62 has not been finalized. A description of the systems is described. The academic program in radionuclide production and separation methods was initiated in the fall of 2011 and, due to the lack of a radiochemistry laboratory, it was suspended. We expect to re-start the academic program at the Texas A&M Institute for Preclinical Studies under the Molecular Imaging Program.

  20. The Texas A&M Radioisotope Production and Radiochemistry Program

    Energy Technology Data Exchange (ETDEWEB)

    Akabani, Gamal [Texas A & M Univ., College Station, TX (United States)

    2016-08-31

    The main motivation of the project at Texas A&M University was to carry out the production of critically needed radioisotopes used in medicine for diagnostic and therapy, and to establish an academic program in radionuclide production and separation methods. After a lengthy battle with the Texas A&M University Radiation Safety Office, the Texas Department of State Health Services granted us a license for the production of radionuclides in July 2015, allowing us to work in earnest in our project objectives. Experiments began immediately after licensing, and we started the assembly and testing of our target systems. There were four analytical/theoretical projects and two experimental target systems. These were for At-211 production and for Zn- 62/Cu-62 production. The theoretical projects were related to the production of Mo-99/Tc-99m using (a) a subcritical aqueous target system and (b) production of Tc-99m from accelerator-generated Mo-99 utilizing a photon-neutron interaction with enriched Mo-100 targets. The two experimental projects were the development of targetry systems and production of At-211 and Zn-62/Cu-62 generator. The targetry system for At-211 has been tested and production of At-211 is chronic depending of availability of beam time at the cyclotron. The installation and testing of the targetry system for the production of Zn-62/Cu-62 has not been finalized. A description of the systems is described. The academic program in radionuclide production and separation methods was initiated in the fall of 2011; due to the lack of a radiochemistry laboratory, it was suspended. We expect to re-start the academic program at the Texas A&M Institute for Preclinical Studies under the Molecular Imaging Program.

  1. The Texas A&M Radioisotope Production and Radiochemistry Program

    International Nuclear Information System (INIS)

    Akabani, Gamal

    2016-01-01

    The main motivation of the project at Texas A&M University was to carry out the production of critically needed radioisotopes used in medicine for diagnostic and therapy, and to establish an academic program in radionuclide production and separation methods. After a lengthy battle with the Texas A&M University Radiation Safety Office, the Texas Department of State Health Services granted us a license for the production of radionuclides in July 2015, allowing us to work in earnest in our project objectives. Experiments began immediately after licensing, and we started the assembly and testing of our target systems. There were four analytical/theoretical projects and two experimental target systems. These were for At-211 production and for Zn- 62/Cu-62 production. The theoretical projects were related to the production of Mo-99/Tc-99m using (a) a subcritical aqueous target system and (b) production of Tc-99m from accelerator-generated Mo-99 utilizing a photon-neutron interaction with enriched Mo-100 targets. The two experimental projects were the development of targetry systems and production of At-211 and Zn-62/Cu-62 generator. The targetry system for At-211 has been tested and production of At-211 is chronic depending of availability of beam time at the cyclotron. The installation and testing of the targetry system for the production of Zn-62/Cu-62 has not been finalized. A description of the systems is described. The academic program in radionuclide production and separation methods was initiated in the fall of 2011; due to the lack of a radiochemistry laboratory, it was suspended. We expect to re-start the academic program at the Texas A&M Institute for Preclinical Studies under the Molecular Imaging Program.

  2. The Texas A&M Radioisotope Production and Radiochemistry Program

    International Nuclear Information System (INIS)

    Akabani, Gamal; M Univ., College Station, TX

    2016-01-01

    The main motivation of the project at Texas A&M University was to carry out the production of critically needed radioisotopes used in medicine for diagnostics and therapy, and to establish an academic program in radionuclide production and separation methods. After a lengthy battle with the Texas A&M University Radiation Safety Office, the Texas Department of State Health Services granted us a license for the production of radionuclides in July 2015, allowing us to work in earnest in our project objectives. Experiments began immediately after licensing, and we started the assembly and testing of our target systems. There were four analytical/theoretical projects and two experimental target systems. These were for At-211 production and for Zn-62/Cu-62 production. The theoretical projects were related to the production of Mo-99/Tc-99m using a) a subcritical aqueous target system and b) production of Tc-99m from accelerator-generated Mo-99 utilizing a photon-neutron interaction with enriched Mo-100 targets. The two experimental projects were the development of targetry systems and production of At-211 and Zn-62/Cu-62 generator. The targetry system for At-211 has been tested and production of At-211 is chronic depending of availability of beam time at the cyclotron. The installation and testing of the targetry system for the production of Zn-62/Cu-62 has not been finalized. A description of the systems is described. The academic program in radionuclide production and separation methods was initiated in the fall of 2011 and, due to the lack of a radiochemistry laboratory, it was suspended. We expect to re-start the academic program at the Texas A&M Institute for Preclinical Studies under the Molecular Imaging Program.

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  4. High purity materials as targets for radioisotope production: Needs ...

    Indian Academy of Sciences (India)

    Unknown

    radionuclides in suitable radiochemical form, its facile detection and elegant tracer concepts are responsible for their unprecedented use. Application of radioisotopes in medicine has given birth to a new branch, viz. nuclear medicine, wherein radioisotopes are used extensively in the diagnosis and treatment of variety of dis ...

  5. Target optimization for the photonuclear production of radioisotopes.

    Science.gov (United States)

    Howard, Sean; Starovoitova, Valeriia N

    2015-02-01

    In this paper we discuss the optimum shape of a target for photonuclear production of radioisotopes using an electron linear accelerator. Different target geometries such as right cylinder, conical frustum, Gaussian volume of revolution and semi-ellipsoid have been considered for the production of (67)Cu via (68)Zn(γ,p)(67)Cu photonuclear reaction. The specific activity (SA) of (67)Cu was simulated for each target shape. Optimum ratio of radius to height for cylindrical targets was found to be between 0.2 and 0.25 for target masses ranging from 20 g to 100 g. It was shown that while some unconventional target shapes, such as semi-elliptical volume of revolution, result in slightly higher specific activities than cylindrical targets, the advantage is not significant and is outweighed by the complexity of the target production and handling. Power deposition into the target was modeled and the trade-off between the maximization of (67)Cu yield and the minimization of target heating has been discussed. The (67)Cu case can easily be extended for production of many other isotopes. Published by Elsevier Ltd.

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

    International Nuclear Information System (INIS)

    Souza, A.L.A.B. de.

    1985-01-01

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

  7. Novel production techniques of radioisotopes using electron accelerators

    Science.gov (United States)

    Lowe, Daniel Robert

    Non-traditional radioisotope production techniques using a compact, high power linear electron accelerator have been demonstrated and characterized for the production of 18F, 47Sc, 147 Pm, and 99mTc from a variety of target candidates. These isotopes are used extensively in the medical field as diagnostic and therapy radioisotopes, as well as the space industry as RTG's. Primary focus was placed on 99mTc as it constitutes approximately 80% of all diagnostic procedures in the medical community that use radioactive tracers. It was also the prime focus due to recent events at the Chalk River nuclear reactor, which caused global shortages of this isotope a few years ago. A Varian K15 LINAC was first used to show proof of principle in Las Vegas. Various samples were then taken to the Idaho Accelerator Center where they were activated using an electron LINAC capable of electron energies from 4 to 25 MeV at a beam power of approximately 1 kW. Production rates, cross sections, and viability studies were then performed and conducted to assess the effectiveness of the candidate target and the maximum production rate for each radioisotope. Production rates for 18F from lithium fluoride salts were shown to be ideal at 21MeV, namely 1.7 Ci per kg of LiF salt, per kW of beam current, per 10 hour irradiation time. As the typical hospital consumption of 18F is around 500 mCi per day, it is clear that a large amount of 18F can be made from a small (300 gram) sample of LiF salt. However, since there is no current separation process for 18F from 19F, the viability of this technique is limited until a separations technique is developed. Furthermore, the calculated cross section for this reaction is in good agreement with literature, which supports the techniques for the isotopes mentioned below. Production rates for 47Sc from vanadium oxide targets were shown to be a maximum at 25 MeV with a production rate of 2 mCi per day, assuming a 2 kW beam and a 10 kg target. While this

  8. Czechoslovak production of radioisotopes as part of international socialist economic integration

    International Nuclear Information System (INIS)

    The sixteen years' participation is discussed of the Prague Institute for the Research, Production and Use of Radioisotopes (UVVVR) in the international agreement concluded by CMEA countries on the specialization of radioisotope production. The principles of the commitments proceeding from participation in the agreement are given as are statistical data on the range and distribution of production. Czechoslovakia's economic contribution to this area of international socialist division of labour is assessed. (author). 1 tab

  9. Productivity of a nuclear chemical reactor with gamma radioisotopic sources

    International Nuclear Information System (INIS)

    Anguis T, C.

    1975-01-01

    According to an established mathematical model of successive Compton interaction processes the made calculations for major distances are extended checking the acceptability of the spheric geometry model for the experimental data for radioisotopic sources of Co-60 and Cs-137. Parameters such as the increasing factor and the absorbed dose served as comparative base. calculations for the case of a punctual source succession inside a determined volume cylinder are made to obtain the total dose, the deposited energy by each photons energetic group and the total absorbed energy inside the reactor. Varying adequately the height/radius relation for different cylinders, the distinct energy depositions are compared in each one of them once a time standardized toward a standard value of energy emitted by the reactor volume. A relation between the quantity of deposited energy in each point of the reactor and the conversion values of chemical species is established. They are induced by electromagnetic radiation and that are reported as ''G'' in the scientific literature (number of molecules formed or disappeared by each 100 e.v. of energy). Once obtained the molecular performance inside the reactor for each type of geometry, it is optimized the height/radius relation according to the maximum production of molecules by unity of time. It is completed a bibliographical review of ''G'' values reported by different types of aqueous solutions with the purpose to determine the maximum performance of molecular hydrogen as a function of pH of the solution and of the used type of solute among other factors. Calculations for the ethyl bromide production as an example of one of the industrial processes which actually work using the gamma radiation as reactions inductor are realized. (Author)

  10. Radioisotope Productions for Medical Use with Accelerator Neutrons

    Science.gov (United States)

    Minato, Futoshi; Nagai, Yasuki; Iwamoto, Nobuyuki; Iwamoto, Osamu

    2014-09-01

    Various kinds of radioactive isotopes (RIs) are widely used in nuclear medicine for diagnostics and therapy. Since the RIs are not usually present in the nature, they must be produced by nuclear reactors and accelerators. For instance, 99mTc, which is the most common RI used in diagnosis, is mainly produced by fission of highly enriched 235U (HEU) in nuclear reactors. However, use of the HEU is unfavorable in terms of nuclear security. Therefore, many methods without 235U have been studied in order to produce RIs for medical use; for example, thermal neutron capture, gamma disintegration, and proton induced reactions. We also have proposed an alternative method using accelerator neutrons besides the above methods. Technique producing high intense accelerator neutron beam as much as 1015 n/s is being developed and RI productions with the accelerator neutron have been done recently. The major advantages of the use of accelerator neutron are followings. 1) A wide variety of carrier-added and carrier-free radioisotopes can be produced using the neutrons, because a charge exchange reaction of a sample nucleus has a sizable cross section of 50 to 500 mb. 2) High transparency of neutron allows us to use a large amount of sample to co-produce other RIs by putting other samples behind the main sample in the beam direction. In this talk, we will show the features of RI productions with accelerator neutron which we have ever investigated and found, along with numerical results of RI yields calculated with Japanese Evaluated Nuclear Data Library (JENDL-4.0).

  11. Potential medical applications of the plasma focus in the radioisotope production for PET imaging

    International Nuclear Information System (INIS)

    Roshan, M.V.; Razaghi, S.; Asghari, F.; Rawat, R.S.; Springham, S.V.; Lee, P.; Lee, S.; Tan, T.L.

    2014-01-01

    Devices other than the accelerators are desired to be investigated for generating high energy particles to induce nuclear reaction and positron emission tomography (PET) producing radioisotopes. The experimental data of plasma focus devices (PF) are studied and the activity scaling law for External Solid Target (EST) activation is established. Based on the scaling law and the techniques to enhance the radioisotopes production, the feasibility of generating the required activity for PET imaging is studied. - Highlights: • Short lived radioisotopes for PET imaging are produced in plasma focus device. • The scaling law of the activity induced with plasma focus energy is established. • The potential medical applications of plasma focus are studied

  12. Targets for the production of radioisotopes and method of assembly

    Science.gov (United States)

    Quinby, Thomas C.

    1976-01-01

    A target for preparation of radioisotopes by nuclear bombardment, and a method for its assembly are provided. A metallic sample to be bombarded is enclosed within a metallic support structure and the resulting target subjected to heat and pressure to effect diffusion bonds therebetween. The bonded target is capable of withstanding prolonged exposure to nuclear bombardment without thermal damage to the sample.

  13. High purity materials as targets for radioisotope production: Needs ...

    Indian Academy of Sciences (India)

    Unknown

    emission tomography (PET) using positron emitting radionuclides. In industry, radionuclides due to their greater detection sensitivity and the fact that they ... controlled by Food & Drug Controller of the state, De- partment of Health and Nuclear Regulatory Agencies of. Figure 1. Radioisotope uses in medicine. Figure 2.

  14. Potential medical applications of the plasma focus in the radioisotope production for PET imaging

    Science.gov (United States)

    Roshan, M. V.; Razaghi, S.; Asghari, F.; Rawat, R. S.; Springham, S. V.; Lee, P.; Lee, S.; Tan, T. L.

    2014-06-01

    Devices other than the accelerators are desired to be investigated for generating high energy particles to induce nuclear reaction and positron emission tomography (PET) producing radioisotopes. The experimental data of plasma focus devices (PF) are studied and the activity scaling law for External Solid Target (EST) activation is established. Based on the scaling law and the techniques to enhance the radioisotopes production, the feasibility of generating the required activity for PET imaging is studied.

  15. Licensing criteria of positron emitting radioisotopes production accelerators in Spain

    International Nuclear Information System (INIS)

    Ramirez, M.L.; Blanes, A.; Alvarez, C.

    2001-01-01

    Full text: CSN is responsible for the licensing and injection of the radioactive facilities. In Spain several cyclotrons have been installed for production of positron emitting radionuclides for use in diagnosis and nuclear medicine investigation. At the moment there are 5 cyclotrons, the first one began to operate in Madrid in 1996 and the last two in Sevilla and Madrid in March, 2001. Of all of them only one is an autoshielded cyclotron. All accelerate negative ion (H - ), except one which, in addition, accelerates deuterons (d). The acceleration energies range between 9 to 18 MeV, current intensity varies from 50 to 100 μA. Maximum activities of radioisotope, focussing exclusively on the 18 F, being the one that they mainly produce, fluctuate between 1.4 and 5 Ci (52-85 GBq) at the end of bombardment. These facilities of isotope production consist basically of a cyclotron room in which the bombardment of the targets takes place, a control room where the machine is controlled, a technical room, a hot laboratory where the chemical synthesis of the radiopharmaceuticals: 18 F-Fluordeoxiglucose ( 18 FDG), and 13 N-Amonia takes place and finally a room for pharmaceutical quality control The radiological hazards associated to this type of facilities are related to the external radiation and contamination. Main external radiation exposure only takes place during the bombardment of the target by the accelerated particles; this interaction produces prompt and secondary gamma, X rays and neutron radiation. Additionally, residual radioactivity induced by activation of the materials of the cyclotron exists, this should be taken into account mostly during the operations of maintenance, although in the Spanish cyclotrons, of negative ion beams, the residual radioactivity is lower compared to the positive ion beam ones. Contamination risk comes as much from the radioactivity induced in the cooling liquids, as from the gas production due to the activation of the air ( 41 Ar by

  16. Low geometry counter for the absolute measurement of the activity of alpha-emitting sources

    International Nuclear Information System (INIS)

    Garcia-Torano, E.; Acena, M.L.

    1989-01-01

    A low-geometry counter is described which allows the absolute determination of the activity for alpha-emitting sources. A Si implanted detector is used to obtain the spectrum of the sample. Two samples are measured with this counter and a 2 π gridded ion chamber. The results an their uncertainties for both instruments are discussed. (Author)

  17. Current status of production and research of radioisotopes and radiopharmaceuticals in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Soenarjo, Sunarhadijoso; Tamat, Swasono R. [Center for Development of Radioisotopes and Radiopharmaceuticals, National Nuclear Energy Agency (BATAN), Kawasan Puspiptek, Serpong, Tangerang (Indonesia)

    2000-10-01

    The use of radioactive preparation in Indonesia has sharply increased during the past years, indicated by increase of the number of companies utilizing radioisotopes during 1985 to 1999. It has been clearly stressed in the BATAN's Strategic Plan for 1994-2014 that the production of radioisotopes and radiopharmaceuticals is one of five main industrial fields within the platform of the Indonesian nuclear industry. Research programs supporting the production of radioisotopes and radiopharmaceuticals as well as development of production technology are undertaken by the Research Center for Nuclear Techniques (RCNT) in Bandung and by the Radioisotope Production Center (RPC) in Serpong, involving cooperation with other research center within BATAN, universities and hospitals as well as overseas nuclear research institution. The presented paper describes production and research status of radioisotopes and radiopharmaceuticals in Indonesia after the establishment of P.T. Batan Teknologi in 1996, a government company assigned for activities related to the commercial application of nuclear technology. The reviewed status is divided into two short periods, i.e. before and after the Chairman Decree No. 73/KA/IV/1999 declaring new BATAN organizational structure. Subsequent to the Decree, all commercial requests for radioisotopes and radiopharmaceuticals are fulfilled by P.T. Batan Teknologi, while demands on novel radioactive preparations or new processing technology, as well as research and development activities should be fulfilled by the Center for the Development of Radioisotopes and Radiopharmaceuticals (CDRR) through non-commercial arrangement. The near-future strategic research programs to response to dynamic public demand are also discussed. The status of research cooperation with JAERI (Japan) is also reported. (author)

  18. Nuclear data for the production of radioisotopes in fusion materials irradiation facility

    International Nuclear Information System (INIS)

    Cheng, E.T.; Schenter, R.E.; Mann, F.M.; Ikeda, Y.

    1991-01-01

    The fusion materials irradiation facility (FMIF) is a neutron source generator that will produce a high-intensity 14-MeV neutron field for testing candidate fusion materials under reactor irradiation conditions. The construction of such a facility is one of the very important development stages toward realization of fusion energy as a practical energy source for electricity production. As a result of the high-intensity neutron field, 10 MW/m 2 or more equivalent neutron wall loading, and the relatively high-energy (10- to 20-MeV) neutrons, the FMIF, as future fusion reactors, also bears the potential capability of producing a significant quantity of radioisotopes. A study is being conducted to identify the potential capability of the FMIF to produce radioisotopes for medical and industrial applications. Two types of radioisotopes are involved: one is already available; the second might not be readily available using conventional production methods. For those radioisotopes that are not readily available, the FMIF could develop significant benefits for future generations as a result of the availability of such radioisotopes for medical or industrial applications. The current production of radioisotopes could help finance the operation of the FMIF for irradiating the candidate fusion materials; thus this concept is attractive. In any case, nuclear data are needed for calculating the neutron flux and spectrum in the FMIF and the potential production rates of these isotopes. In this paper, the authors report the result of a preliminary investigation on the production of 99 Mo, the parent radioisotope for 99m Tc

  19. Production and application of therapeutic radioisotopes. Activity on the related nuclear reaction data

    International Nuclear Information System (INIS)

    Tarkanyi, F.

    2002-01-01

    Full text: The Charged Particle Nuclear Data (CPND) Group in the ATOMKI has been involved in measurement, compilation, evaluation and application of nuclear reaction data for more than 15 years. The main field of activity is charged particle induced reactions. The research is mainly focused on non-energy related applications: medical radioisotope production, monitoring the parameters of charged particle beams, thin layer activation to control wear and corrosion. Last years we have started to extend our activities to measurements of fast neutron reaction data and charged particle reaction data related to waste transmutation. The CPND Group itself has extended experimental experience at the Debrecen MGC 20E cyclotron and at other accelerators in collaboration with universities in Hungary or laboratories in Germany (INC, Forschungszentrum Juelich), Belgium (Cyclotron Laboratory, Vrije Universiteit of Brussels), Japan (CYRIC, Tohoku University, Sendai and National Institute of Radiological Sciences, Chiba), Finland (Cyclotron Lab., Abo Akademi, Turku), Czech Republic (Nuclear Research Institute, Rez) and South-Africa (National Accelerator Centre, Faure). Activities in the field of compilation and data evaluation are done in close collaboration with IAEA in the frame of independent projects and of the Nuclear Reaction Data Center Network. Eight scientists (six physicists and two chemists) are contributing to the nuclear data project (most of them only part-time). An important field of the nuclear data activity actually lies in the medical radioisotope production. The members of ATOMKI CPND group are involved in every day radioisotope production of diagnostic radioisotopes for PET and SPECT. The team was also involved in the IAEA-CRP on development of a recommended database for production of diagnostic radioisotopes reactions for nuclear medicine by charged particle induced reactions and presently is engaged in the extension and upgrading of this database. In the field

  20. Automatic radioisotope production devices adapted to a medical cyclotron

    International Nuclear Information System (INIS)

    Crouzel, C.; Le Poec, C.; Jarry, E.; Knipper, R.; Comar, D.

    1979-01-01

    The authors describe an irradiation device set up beside a compact medical cyclotron (520.CGR-MeV cyclotron). The variable energy machine can accelerate 3-22 MeV protons, 3-13 MeV deuterons, 6-26 MeV alpha particles and 5-31 MeV helium-3 particles, the currents extracted at the maximum energies reaching 50 μA for 4 He and 3 He, 70 μA for protons and deuterons. The essential characteristics demanded of the apparatus in order to produce a regular and abundant supply of short-lived radioisotopes were as follows: - Flexibility of use or the possibility of fast, completely non-manual target changing. - Simplicity of operation: the target-holder components must be easily interchangeable and the transfer of radioisotopes from the irradiation point to the chemical laboratory must be rapid. - Working safety: the automatic target-holder cooling controls must be duplicated by manual controls. - Target cooling efficiency: these targets, whether gaseous, liquid or solid, must be able to support a high particle current. (Auth.)

  1. Production ampersand marketing of radioisotopes: A vital market for rare earths ampersand specialty metals

    International Nuclear Information System (INIS)

    Fox, C.J.

    1996-01-01

    Isotopes that spontaneously emit alpha (α) or beta (β) particles, or gamma rays (γ), are said to be radioactive. The emission process, called open-quotes decay,close quotes is precisely what makes radioactive isotopes, known as open-quotes radioisotopes,close quotes useful in a variety of applications, including nuclear medicine, commercial sterilization, manufacturing, geophysics, agriculture, and research programs in these and various other fields. Until 1960, radioisotope production was limited to government-owned nuclear reactors and particle accelerators in universities and government laboratories, primarily because the enormous cost of building these facilities could only be supported by government budgets. During this time, a few private companies managed to secure commercial rights to exploit the production capabilities of these facilities. Today, these companies and a few government agencies still provide the basis of global commercial radioisotope supply

  2. Study of surface potential contamination in radioisotope and radiopharmaceutical production facilities and alternative solutions

    International Nuclear Information System (INIS)

    Suhaedi Muhammad; Rimin Sumantri; Farida Tusafariah; Djarwanti Rahayu Pipin Soedjarwo

    2013-01-01

    Radioisotope and radiopharmaceutical production facilities that exist in their operations around the world in the form of radiological impacts of radiation exposure, contamination of surface and air contamination. Given the number of existing open source in radioisotope and radiopharmaceutical production facility, then the possibility of surface contamination in the work area is quite high. For that to protect the safety and health of both workers, the public and the environment, then the licensee must conduct an inventory of some of the potential that could result in contamination of surfaces in radioisotope and radiopharmaceutical production facilities. Several potential to cause surface contamination in radioisotope and radiopharmaceutical production facilities consist of loss of resources, the VAC system disorders, impaired production facilities, limited resources and lack of work discipline and radioactive waste handling activities. From the study of some potential, there are several alternative solutions that can be implemented by the licensee to address the contamination of the surface so as not to cause adverse radiological impacts for both radiation workers, the public or the environment. (author)

  3. The present situation of radioisotope production in cyclotron CV-28 at IEN

    International Nuclear Information System (INIS)

    Braghirolli, A.M.; Silva, A.G. da; Santos, D.F. dos; Almeida, G.L. de; Britto, J.L.Q. de; Osso Junior, J.A.; Bastos, M.A.V.

    1992-01-01

    Methods and routine production of radioisotopes are developed in the Nuclear Engineering Institute, aiming the progressive substitution of import product. A routine production of 123 I in 30 mCi/batch is installed. The 67 Ga production tests with a capacity for 300 mCi/batch are at end phase. sealed sources of 57 Co are also produced for using in gamma cameras calibration. (C.G.C.)

  4. Solid targets for production of radioisotopes with cyclotron; Blancos solidos para produccion de radioisotopos con ciclotron

    Energy Technology Data Exchange (ETDEWEB)

    Paredes G, L.; Balcazar G, M. [Instituto Nacional de Investigaciones Nucleares, Direccion de Investigacion Tecnologica, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

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

  5. An alternate approach to the production of radioisotopes for nuclear medicine applications.

    Science.gov (United States)

    D'Auria, John M; Keller, Roderich; Ladouceur, Keith; Lapi, Suzanne E; Ruth, Thomas J; Schmor, Paul

    2013-03-01

    There is a growing need for the production of radioisotopes for both diagnostic and therapeutic medical applications. Radioisotopes that are produced using the (n,γ) or (γ,n) reactions, however, typically result in samples with low specific activity (radioactivity∕gram) due to the high abundance of target material of the same element. One method to effectively remove the isotopic impurity is electro-magnetic mass separation. An Ion Source Test Facility has been constructed at TRIUMF to develop high-intensity, high-efficiency, reliable ion sources for purification of radioactive isotopes, particularly those used in nuclear medicine. In progress studies are presented.

  6. Basic Research and Feasibility Study of Radioisotope Production using 100 MeV Proton Beam

    International Nuclear Information System (INIS)

    Yoo, K. H.; Yoon, K. S.; Cho, W. J.; Park, S. I.; Han, H. S.; Yang, S. D.; Jeon, K. S.; Kim, J. H.; Yang, T. K.

    2010-04-01

    Results of the project are various nuclei, such as 82 Rb, 68 Ga, 67 Cu, 22 Na and so on, can be produced by irradiating 100 MeV proton beam, by irradiating proton beam to the nat Ga target, the 68 Ge, mother nucleus of positron emitting 68 Ga, is produced based on the nat Ga(p,x) 68 Ge reaction, the target system for the high-energy of proton beam can produce more than 2 species of radioisotope at the same time by employing tandem targets, 68 Ge/ 68 Ga generator, 82 Sr(25.34d)/ 82 Rb generator - 67 Cu production method, 70 Zn electroplating technology based on the electrochemistry, the container, whose weight is about 3 ton, is made by depleted uranium and because of the unstable situation for the supply and demand of reactor produced radioisotope, the need for the cyclotron produced radioisotopes is dramatically increased all over the world.

  7. Production and supply of radioisotopes with high-energy particle accelerators current status and future directions

    International Nuclear Information System (INIS)

    Srivastava, S.C.; Mausner, L.F.

    1994-01-01

    Although the production of radioisotopes in reactors or in low to medium energy cyclotrons appears to be relatively well established, certain isotopes can either be made only in high-energy particle accelerators or their production is more cost effective when made this way. These facilities are extremely expensive to build and operate, and isotope production is, in general, either not cost-effective or is in conflict with their primary mandate or missions which involve physics research. Isotope production using high-energy accelerators in the U.S., therefore, has been only an intermittent and parasitic activity. However, since a number of isotopes produced at higher energies are emerging as being potentially useful for medical and other applications, there is a renewed concern about their availability in a continuous and reliable fashion. In the U.S., in particular, the various aspects of the production and availability of radioisotopes from high-energy accelerators are presently undergoing a detailed scrutiny and review by various scientific and professional organizations as well as the Government. A number of new factors has complicated the supply/demand equation. These include considerations of cost versus needs, reliability factors, mission orientation, research and educational components, and commercial viability. This paper will focus on the present status and projected needs of radioisotope production with high-energy accelerators in the U.S., and will compare and examine the existing infrastructure in other countries for this purpose. The nature of the U.S. decisions to address many of the above-mentioned issues and an eventual plan of attack to resolve them are bound to have a world-wide impact in the radioisotope user communities. These will be discussed with a view to evaluating the best possible solutions in order to eliminate the shortage in the future supply of radioisotopes produced in high energy accelerators. (author)

  8. Experiences in radioisotope production in the German Democratic Republic with special reference to radiopharmaceuticals

    International Nuclear Information System (INIS)

    Muenze, R.

    1988-01-01

    Radioisotope production has been carried out in the German Democratic Republic for 30 years. Based on a 10 MW research reactor, a cyclotron and certain irradiation facilities at units of national nuclear power stations, a widespread assortment of radioisotopes is produced with emphasis to radiopharmaceuticals as the main materials. Domestic production covers the national demand in these products where the production is technologically feasible under our conditions. A complete supply of the users in the country (more than 7000 licences) is accomplished by an intense co-operation with neighbouring countries, including mutual assistance in reactor shut down periods and supply with special radioactive materials and products. International co-operation within the framework of the IAEA takes place, mainly as scientific and technological assistance to many developing countries. (author)

  9. Homogeneous aqueous solution nuclear reactors for the production of Mo-99 and other short lived radioisotopes

    International Nuclear Information System (INIS)

    2008-09-01

    Technetium-99m ( 99m Tc), the daughter of Molybdenum-99 ( 99 Mo), is the most commonly used medical radioisotope in the world. It accounts for over twenty-five million medical procedures each year worldwide, comprising about 80% of all radiopharmaceutical procedures. 99 Mo is mostly prepared by the fission of uranium-235 targets in a nuclear reactor with a fission yield of about 6.1%. Currently over 95% of the fission product 99 Mo is obtained using highly enriched uranium (HEU) targets. Smaller scale producers use low enriched uranium (LEU) targets. Small quantities of 99 Mo are also produced by neutron activation through the use of the (n, γ) reaction. The concept of a compact homogeneous aqueous reactor fuelled by a uranium salt solution with off-line separation of radioisotopes of interest ( 99 Mo, 131 I) from aliquots of irradiated fuel solution has been cited in a few presentations in the series of International Conference on Isotopes (ICI) held in Vancouver (2000), Cape Town (2003) and Brussels (2005) and recently some corporate interest has also been noticeable. Calculations and some experimental research have shown that the use of aqueous homogeneous reactors (AHRs) could be an efficient technology for fission radioisotope production, having some prospective advantages compared with traditional technology based on the use of solid uranium targets irradiated in research reactors. This review of AHR status and prospects by a team of experts engaged in the field of homogeneous reactors and radioisotope producers yields an objective evaluation of the technological challenges and other relevant implications. The meeting to develop this report facilitated the exchange of information on the 'state of the art' of the technology related to homogeneous aqueous solution nuclear reactors, especially in connection with the production of radioisotopes. This publication presents a summary of discussions of a consultants meeting which is followed by the technical

  10. Internal dosimetry from IPEN workers involved in the medical radioisotopes production

    International Nuclear Information System (INIS)

    Cesar, R.B.P.; Mesquita, C.H. de

    1988-01-01

    The internal dose from IPEN workers involved in the medical radioisotopes products is related. In the workers population, six groups were classified: development and research, routine production, quality control, package, radioprotection supervision and maintenance. The internal doses were calculated according to the methodology described by the ICRP-30, using resuls from a whole-body counter. The results described were obtained from 970 whole-body radioactivity measurements during the last three years (1985 a 1987). (author) [pt

  11. Nuclear Reactors and Production of Medical Radioisotopes: Case of the Tunisian Subcritical Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Jelassi, Haikel [CNSTN, Tunis (Turkey)

    2013-07-01

    Nuclear reactors and cyclotrons are today the main producing facilities of artificial radioisotopes. These radionuclides are widely used, in particular, in nuclear medicine, such as in radiation therapy (with use of the radioisotope Cobalt-60) and medical imaging (with use of the radioisotope technetium-99). In this framework, the Government of Tunisia has decided to install a sub-critical assembly at CNSTN. This facility will serve as an efficient tool for national human resources development and it will be also extremely useful for carrying out research projects by scientists in order to provide them with a basic understanding of the main concepts relevant to nuclear reactors. The licensing process for the installation of the facility will also bring valuable experience in the development of a nuclear infrastructure in the Country. We propose to summarize in this paper, the basic information concerning the production of radioisotopes with research reactors. We also present the state of art and useful information about the current project to implement a subcritical assembly-reactor in CNSTN (The National Centre for Nuclear Science and Technology). A project carried out with the assistance and the support of the IAEA(The international Atomic Energy Agency)

  12. Production and supply of radioisotopes with high-energy particle accelerators current status and future directions

    International Nuclear Information System (INIS)

    Srivastava, S.C.; Mausner, L.F.

    1994-01-01

    Although the production of radioisotopes in reactors or in low to medium energy cyclotrons appears to be relatively well established, especially for those isotopes that are routinely used and have a commercial market, certain isotopes can either be made only in high-energy particle accelerators or their production is more cost effective when made this way. These facilities are extremely expensive to build and operate, and isotope production is, in general, either not cost-effective or is in conflict with their primary mandate or missions which involve physics research. Isotope production using high-energy accelerators in the US, therefore, has been only an intermittent and parasitic activity. However, since a number of isotopes produced at higher energies are emerging as being potentially useful for medical and other applications, there is a renewed concern about their availability in a continuous and reliable fashion. In the US, in particular, the various aspects of the prediction and availability of radioisotopes from high-energy accelerators are presently undergoing a detailed scrutiny and review by various scientific and professional organizations as well as the Government. A number of new factors has complicated the supply/demand equation. These include considerations of cost versus needs, reliability factors, mission orientation, research and educational components, and commercial viability. This paper will focus on the present status and projected needs of radioisotope production with high-energy accelerators in the US, and will compare and examine the existing infrastructure in other countries for this purpose

  13. DISCOVERY OF AN H{alpha} EMITTING DISK AROUND THE SUPERMASSIVE BLACK HOLE OF M31

    Energy Technology Data Exchange (ETDEWEB)

    Menezes, R. B.; Steiner, J. E.; Ricci, T. V., E-mail: robertobm@astro.iag.usp.br [Instituto de Astronomia Geofisica e Ciencias Atmosfericas, Universidade de Sao Paulo, Rua do Matao 1226, Cidade Universitaria, Sao Paulo, SP CEP 05508-090 (Brazil)

    2013-01-10

    Due to its proximity, the mass of the supermassive black hole in the nucleus of the Andromeda galaxy (M31), the most massive black hole in the Local Group of galaxies, has been measured by several methods involving the kinematics of a stellar disk which surrounds it. We report here the discovery of an eccentric H{alpha} emitting disk around the black hole at the center of M31 and show how modeling this disk can provide an independent determination of the mass of the black hole. Our model implies a mass of 5.0{sup +0.8}{sub -1.0} Multiplication-Sign 10{sup 7} M{sub Sun} for the central black hole, consistent with the average of determinations by methods involving stellar dynamics, and compatible (at 1{sigma} level) with measurements obtained from the most detailed models of the stellar disk around the central black hole. This value is also consistent with the M-{sigma} relation. In order to make a comparison, we applied our simulation on the stellar kinematics in the nucleus of M31 and concluded that the parameters obtained for the stellar disk are not formally compatible with the parameters obtained for the H{alpha} emitting disk. This result suggests that the stellar and the H{alpha} emitting disks are intrinsically different from each other. A plausible explanation is that the H{alpha} emission is associated with a gaseous disk. This hypothesis is supported by the detection of traces of weaker nebular lines in the nuclear region of M31. However, we cannot exclude the possibility that the H{alpha} emission is, at least partially, generated by stars.

  14. Radioisotope production experience at the Cintichem 5-MW research reactor

    International Nuclear Information System (INIS)

    McGovern, J.J.

    1993-01-01

    The Cintichem radiochemical production facility was constructed in the late 1950s and became operational in October of 1961. The facility was originally designed and constructed by Union Carbide Corporation for research and development of nuclear technology with the ultimate objective of exploiting it commercially. Research projects were conducted in the fields of direct energy conversion for the production of electric power and chemical synthesis, neutron spectrometry, nuclear fuel cycle development, and radiochemical production. Radiochemical production for medical applications was the only development project that was successfully commercialized

  15. Effects of inhaled alpha-emitting actinides on mouse alveolar macrophages.

    Science.gov (United States)

    Morgan, A; Talbot, R J

    1992-01-01

    The effects of inhaled alpha-emitting actinides on the alveolar macrophage (AM) population of the rodent lung are reviewed and, in particular, of the effects of 239PuO2 on murine AM. The effects discussed include changes the AM pool size, macrophage diameter, mobility, phagocytic competence, and enzyme content. Finally, similarities in the dose-response relationships for the induction of nuclear aberrations by alpha emitters and in the induction of lung tumors by the same materials are noted. PMID:1327735

  16. Coordination chemistry of the 212Pb/212Bi nuclear transformation: Alpha-emitting radiopharmaceuticals

    International Nuclear Information System (INIS)

    Parks, N.J.; Harris, W.R.; Keen, C.L.; Cooper, S.R.

    1992-07-01

    Subdivisions of this project are: (a) the synthesis of prototypical thiolate and dithiocarbamate based hexacoordinate complexes, (b) radiochemical engineering for generation of no-carrier-added lead and bismuth radioelements, (c) the first isolation of bismuth-binding proteins from in vivo studies with cyclotron produced 205/206 Bi tracer, and (d) initial development of transport mechanisms for the intracellular radiobiological study of alpha emitting bismuth, and (e) the initiation of chemical equilibrium studies and biochemical pathways with cyclotron-produced, no-carrier-added, 203 Pb (T 1/2 = 51 hr)

  17. Coordination chemistry of the sup 212 Pb/ sup 212 Bi nuclear transformation: Alpha-emitting radiopharmaceuticals

    Energy Technology Data Exchange (ETDEWEB)

    Parks, N.J.; Harris, W.R.; Keen, C.L.; Cooper, S.R.

    1992-07-01

    Subdivisions of this project are: (a) the synthesis of prototypical thiolate and dithiocarbamate based hexacoordinate complexes, (b) radiochemical engineering for generation of no-carrier-added lead and bismuth radioelements, (c) the first isolation of bismuth-binding proteins from in vivo studies with cyclotron produced {sup 205/206}Bi tracer, and (d) initial development of transport mechanisms for the intracellular radiobiological study of alpha emitting bismuth, and (e) the initiation of chemical equilibrium studies and biochemical pathways with cyclotron-produced, no-carrier-added, {sup 203}Pb (T{sub 1/2} = 51 hr).

  18. Radioisotopes production for applications on the health; Produccion de radioisotopos para aplicaciones en la salud

    Energy Technology Data Exchange (ETDEWEB)

    Monroy G, F.; Alanis M, J., E-mail: fabiola.monroy@inin.gob.m [ININ, Departamento de Materiales Radiactivos, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    In the Radioactive Materials Department of the Instituto Nacional de Investigaciones Nucleares (ININ) processes have been studied and developed for the radioisotopes production of interest in the medicine, research, industry and agriculture. In particular five new processes have been developed in the last 10 years by the group of the Radioactive Materials Research Laboratory to produce: {sup 99}Mo/{sup 99m}Tc and {sup 188}W/{sup 188}Re generators, the radio lanthanides: {sup 151}Pm, {sup 147}Pm, {sup 161}Tb, {sup 166}Ho, {sup 177}Lu, {sup 131}I and the {sup 32}P. All these radioisotopes are artificial and they can be produced in nuclear reactors and some of them in particle accelerators. The radioisotope generators are of particular interest, as those of {sup 99}Mo/{sup 99m}Tc and {sup 188}W/{sup 188}Re presented in this work, because they are systems that allow to produce an artificial radioisotope of interest continually, in these cases the {sup 99m}Tc and the {sup 188}Re, without the necessity of having a nuclear reactor or an particle accelerator. They are compact systems armored and sure perfectly of manipulating that, once the radioactive material has decayed, they do not present radiological risk some for the environment and the population. These systems are therefore of supreme utility in places where it is not had nuclear reactors or with a continuous radioisotope supply, due to their time of decaying, for its cost or for logistical problems in their supply, like it is the case of many hospital centers, of research or industries in our country. (Author)

  19. Operational aspects of the radiological control in a radioisotopes plant production

    International Nuclear Information System (INIS)

    Corahua, A.

    1996-01-01

    The purpose of this paper is to inform about the results obtained in the control operations carried out by the radioprotection area of the radioisotopes plant production during 1994 and then were compared with the limits established by the regulations of radiological radioprotection. In the general inter-texture of the activities that are developed in the radioisotopes plant production, the carried out controls are: area monitoring, air monitoring, personnel monitoring, monitoring in the expedition of radioactive material and monitoring and control in the evacuation of solid and liquid wastes. The result obtained in the present paper states that the doses received by the exposed occupationally staff are below the allowed limits. (author). 3 refs

  20. Modelling study on production cross sections of {sup 111}In radioisotopes used in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Kara, Ayhan; Korkut, Turgay [Sinop Univ. (Turkey). Faculty of Engineering; Yigit, Mustafa [Aksaray Univ. (Turkey). Faculty of Science and Arts; Tel, Eyyup [Osmaniye Korkut Ata Univ. (Turkey). Faculty of Science and Arts

    2015-07-15

    Radiopharmaceuticals are radioactive drugs used for diagnosis or treatment in a tracer quantity with no pharmacological action. The production of radiopharmaceuticals is carried out in the special research centers generally using by the cyclotron systems. Indium-111 is one of the most useful radioisotopes used in nuclear medicine. In this paper, we calculated the production cross sections of {sup 111}In radioisotope via {sup 111-114}Cd(p,xn) nuclear reactions up to 60 MeV energy. In the model calculations, ALICE/ASH, TALYS 1.6 and EMPIRE 3.2 Malta nuclear reaction code systems were used. The model calculation results were compared to the experimental literature data and TENDL-2014 (TALYS-based) data.

  1. Production of medical radioisotopes in ORNL 86-Inch Cyclotron

    International Nuclear Information System (INIS)

    Skidmore, M.R.

    1975-01-01

    Procedures, targets, and costs are discussed for the production of iodine-123 at the ORNL 86-Inch Cyclotron. The cyclotron is a fixed frequency machine producing 22-MeV proton beams with currents of 3 mA. Flat plate targets are used in the bombardment of readily fabricated metals when highest production rates are necessary, while capsule targets are used when flat plate coatings are difficult or when high production rates are not required. Window targets with metal foils or powders, inorganic compounds, or isotopically enriched materials are also used. (PMA)

  2. Excitation functions and production of arsenic radioisotopes for environmental toxicology and biomedical purposes

    International Nuclear Information System (INIS)

    Basile, D.; Birattari, C.; Bonard, M.; Salomone, A.; Goetz, L.; Sabbioni, E.

    1981-01-01

    Many arsenic radionuclides have come to be used as tracers in biology and in the study of environmental pollution of both water and soil. In nuclear medicine, radioactive 74 As has been employed as a positron emitter for the localization of brain tumors, cerebral occlusive vascular lesions, arterious-venous malformations, etc. The aim of the work described was to study the excitation functions for the production of the arsenic radioisotopes from targets of natural germanium via nuclear reactions (p, xn). (author)

  3. Fixing tools of targets for radioisotope production in the RA10

    International Nuclear Information System (INIS)

    Peirone, M.; Coleff, A.; Chasseur, A.

    2012-01-01

    The RA-10 project is about the design and construction of a reactor for radioisotopes production and scientific research in the nuclear area. Most of the reactor design comes from INVAP SE, however some of the design job was performed in CNEA, i.e. the so called Outer Core Experimental Devices (DEEN) and their interfaces with the Reflector Tank were designed in CNEA and the documentation of the basic design was recently released (author)

  4. A compact and high current FFAG for the production of radioisotopes for medical application

    CERN Document Server

    Bruton, David; Edgecock, Rob; Seviour, Rebecca; Johnstone, Carol

    2017-01-01

    A low energy Fixed Field Alternating Gradient(FFAG)accelerator has been designed for the production of radioisotopes. Tracking studies have been conducted using the OPAL code, including the effects of space charge. Radioisotopes have a wide range of uses in medicine, and recent disruption to the supply chain has seen a renewed effort to find alternative isotopes and production methods. The design features separate sector magnets with non-scaling, non-linear field gradients but without the counter bends commonly found in FFAG’s. The machine is isochronous at the level of 0.3% up to at least 28MeV and hence able to operate in Continuous Wave (CW) mode. Both protons and helium ions can be used with this design and it has been demonstrated that proton beams with currents of up to 20 mA can be accelerated. An interesting option for the production of radioisotopes is the use of a thin internal target. We have shown that this design has large acceptance, ideal for allowing the beam to be recirculated through t...

  5. Radioisotope production for medical and non-medical application at the Nuclear Energy Unit (UTN)

    International Nuclear Information System (INIS)

    Mohamad Awang; Zulkifli Mohamad Hashim; Yusof Azuddin Ali

    1986-01-01

    Radioisotopes are produced by using a low power research reactor, TRIGA MARK II situated at UTN. Products intended for use as radiopharmaceuticals undergo a more stringent precaution. The solvent extraction technique used to separate 99 m TC from the radioactive solution of Potassium molybdate (K 2 99 Mo0 4 ) is explained in detail. The specific activity of 99Mo obtained at a neutron flux of 2.5 x 10 12 n/cm 2 , s ranges from 1.75 mCi 99 Mo/g MoO 3 to 6.25 mCi 99 Mo/g MoO 3 . However, the specific activity of 99 Mo obtained could be increased by a factor of 6 using the central thimble facility. There are 14 radioisotopes being currently produced. Commonly used cold kits for 99m TC labelling are also produced. Sn-MDP kit for bone scintigraphy is prepared under aseptic environment and freeze-drived. Products are terminally sterilized using γ-irradiation. Uptake studies done on laboratory animals indicate good bone uptake. A few radioisotopes and radiopharmaceuticals products to be produced by UTN in future are reviewed. (author)

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

    Directory of Open Access Journals (Sweden)

    Gizem Bakır

    2016-01-01

    Full Text Available This study presents the medical radioisotope production performance of a conceptual accelerator driven system (ADS. Lead-bismuth eutectic (LBE is selected as target material. The subcritical fuel core is conceptually divided into ten equidistant subzones. The ceramic (natural U, PuO2 fuel mixture and the materials used for radioisotope production (copper, gold, cobalt, holmium, rhenium, thulium, mercury, palladium, thallium, molybdenum, and yttrium are separately prepared as cylindrical rods cladded with carbon/carbon composite (C/C and these rods are located in the subzones. In order to obtain the flattened power density, percentages of PuO2 in the mixture of UO2 and PuO2 in the subzones are adjusted in radial direction of the fuel zone. Time-dependent calculations are performed at 1000 MW thermal fission power (Pth for one hour using the BURN card. The neutronic results show that the investigated ADS has a high neutronic capability, in terms of medical radioisotope productions, spent fuel transmutation and energy multiplication. Moreover, a good quasiuniform power density is achieved in each material case. The peak-to-average fission power density ratio is in the range of 1.02–1.28.

  7. Present situation of the production and use of radioisotopes in France

    International Nuclear Information System (INIS)

    Fisher, Charlie

    1974-01-01

    As the sole large scale producer of radioisotopes in France, the Commissariat a l'Energie Atomique is keeping up pace with all developments in medical, biological and industrial areas. This production will reach the turnover close to 40 million F in 1973. About 65% of the products will go to medical market, 10% to biology and the remaining 25% to industry. As medical products, many radioisotopes are used for in-vivo diagnosis, while radioimmunology techniques are well known in in-vitro diagnosis. There has been very few noticeable development in therapeutics. Also there is steadily increasing demand for 14 C, 3 H and 13 C-labelled materials which are used to study metabolism of natural substances and drugs. The industrial utilization of radioisotopes in France is developed by CEA as well as several industrial companies. Trend must be analyzed for the different segments of the market which includes tracer utilization, instrumentation, large source technology such as sterilization of medical supplies, activation analysis and isotopic generators. (Wakatsuki, Y.)

  8. Development of alpha-emitting radionuclide lead 212 for the potential treatment of ovarian carcinoma

    International Nuclear Information System (INIS)

    Rotmensch, J.; Atcher, R.W.; Hines, J.; Grdina, D.; Schwartz, J.S.; Toohill, M.; Herbst, A.L.

    1989-01-01

    alpha-Emitting radionuclides may be an effective alternative treatment against ovarian carcinoma because they have short half-lives and are densely ionizing, with high linear energy transfer to a depth of several cell diameters without requiring cellular oxygenation. One radionuclide that has been generated and tested in our laboratory in vitro and in vivo is lead 212 ( 212 Pb). Intraperitoneal instillation of 212 Pb prolonged survival and totally eradicated tumor in 24% of mice inoculated with the extremely virulent Ehrlich ascites-producing tumor. In vitro 212 Pb was two to four times more effective in killing human ovarian cancer cells than x-rays. Irradiation with 212 Pb increased the radiosensitivity and chromosomal aberrations of cells. In dogs, intraperitoneal instillation of 2.6 mCi of ferrous hydroxide tagged with 212 Pb caused no significant toxicity. It appears that alpha-emitting radionucides such as 212 Pb have the potential to be a new and potent treatment of ovarian carcinoma and could be effective in cases that are resistant to conventional chemotherapy or x-ray therapy

  9. Calibration and operation of continuous air monitors for alpha-emitting radionuclides

    International Nuclear Information System (INIS)

    Hoover, M.D.; Newton, G.J.

    1993-01-01

    Spectrometer-based continuous air monitors have improved our capabilities for detecting aerosols of alpha-emitting radionuclides. This paper describes basic requirements and statistical limitations in the sensitivity of alpha continuous air monitors, and presents a technical basis for selecting the energy window for detection of uranium and plutonium aerosols, correcting for interference from airborne dust, selecting filters with low pressure drop and good front surface collection characteristics, and properly using electroplated calibration sources. Sensitivity limits are described for detecting uranium or plutonium aerosols in the presence of increased concentrations of naturally occurring, alpha-emitting radon progeny radionuclides. Decreasing the lower energy boundary of the detection window from 4.3 MeV to 2.7 MeV improves by a factor of three the detection of plutonium in the presence of dust, while causing minimal additional interference from ambient radon progeny. Selection of the Millipore Fluoropore teflon membrane filter reduces both pressure drop and interference from ambient radon progeny by up to a factor of two. Field collection of ambient radon progeny can be used to verify the proper energy of alpha emissions from electroplated calibration sources. In the absence of energy verification, errors in instrument calibration may result from solid state diffusion of the electroplated calibration radionuclide into the substrate plate

  10. Production of radioisotopic gamma radiation sources in JAERI

    International Nuclear Information System (INIS)

    Katoh, Hisashi; Kogure, Hiroto; Suzuki, Kyohei

    1980-04-01

    The present state of production of gamma radiation sources in Japan Atomic Energy Research Institute (JAERI) is described. Sources of 192 Ir, 60 Co and 170 Tm for industrial and 198 Au and 192 Ir for medical applications are produced and delivered routinely by JAERI. Prefabricated assembly targets are irradiated in JRR-2, JRR-3, JRR-4 or JMTR. The irradiated targets are disassembled in a heavy density concrete cave or a lead-shielded cell, depending on the level of radioactivity. The yield of radioactivity in each target is measured with the aid of an ionization chamber. Where necessary, irradiated targets are encapsulated hermetically in capsules of aluminium, stainless steel or other material. The yield of radioactivity is estimated in relation with the burn-up of target nuclide and product nuclide. (author)

  11. Development of the radioisotope production facility for the HANARO

    International Nuclear Information System (INIS)

    Lee, Ji Bok; Wu, J. S.; Baik, S. T.

    1998-06-01

    Hot cell and related facilities were developed in the RI production building of the HANARO. 1. development of concrete H/C and related components 2. development of lead H/C and related components 3. development of the hydraulic transfer system 4. development of radiation monitoring system 5. development of purification system for Co-60 storage pool 6. development of the fire fighting system for H/C 7. development of the experimental equipment. (author). 15 figs

  12. Production of platinum radioisotopes at Brookhaven Linac Isotope Producer (BLIP

    Directory of Open Access Journals (Sweden)

    Smith Suzanne V.

    2017-01-01

    Full Text Available The accelerator production of platinum isotopes was investigated at the Brookhaven Linac Isotope Producer (BLIP. In this study high purity natural platinum foils were irradiated at 53.2, 65.7, 105.2, 151.9, 162.9 and 173.3.MeV. The irradiated foils were digested in aqua regia and then converted to their hydrochloride salt with concentrated hydrochloric acid before analyzing by gamma spectrometry periodically for at least 10 days post end of bombardment. A wide range of platinum (Pt, gold (Au and iridium (Ir isotopes were identified. Effective cross sections at BLIP for Pt-188, Pt-189, Pt-191 and Pt-195m were compared to literature and theoretical cross sections determined using Empire-3.2. The majority of the effective cross sections (<70 MeV confirm those reported in the literature. While the absolute values of the theoretical cross sections were up to a factor of 3 lower, Empire 3.2 modeled thresholds and maxima correlated well with experimental values. Preliminary evaluation into a rapid separation of Pt isotopes from high levels of Ir and Au isotopes proved to be a promising approach for large scale production. In conclusion, this study demonstrated that with the use of isotopically enriched target material accelerator production of selected platinum isotopes is feasible over a wide proton energy range.

  13. Radioisotope production with CV-28 in Rio de Janeiro

    International Nuclear Information System (INIS)

    Braghirolli, A.M.; Britto, J.L.Q. de; Bastos, M.A.V.; Aleixo, L.C.M.

    2001-01-01

    Since Brazil's nuclear program began in the seventies with the construction of Angra dos Reis Nuclear Plant, Brazilians have been excluded from participation in this technological process, primarily due to the political events of that time. This exclusivity has resulted in a major segment of the current population being unaware of the wide range of applications and benefits of nuclear technology. In the past few decades, Brazil has invested little in the development of its own nuclear technology. The progress that has been achieved is the result of the research and hard work of dedicated professionals who have struggled to bridge this technological gap since the 1970's. EEN-lnstitute of Nuclear Engineering is one of the research niches in the country that, in spite of the monopoly of knowledge, bureaucracy and insufficient resources, has been carrying out nuclear engineering projects and products. Nowadays, these are extremely useful to society in the most diverse market segments. For the past three years, IEN has invested R$ 2 million in adapting its facilities aiming at producing iodine-123 ultra-pure. In 1998 it started producing this cyclotron radiopharmaceutical in large scale, thus giving new directions to nuclear medicine in Brazil. The present policy of the IEN, regarding priorities and Institute's goals for the coming years has been defined. The Institute will concentrate its efforts on technological research, that is, identify the country's needs in nuclear engineering and providing society with methodologies, products and services that can effectively contribute to improve life quality in Brazil. The lEN's policy has been committed to quality, deadlines, costs and results as well as to research work based on the population's needs and aimed at meeting them efficiently. Several projects have been given priority, and great effort has been aimed at optimizing human and financial resources

  14. Transuranium and other alpha-emitting nuclides in the marine environment

    International Nuclear Information System (INIS)

    Pentreath, R.J.

    1980-01-01

    Marine environment contains naturally occurring alpha-emitting transuranium nuclides which are discharged from nuclear fuel reprocessing plants into the marine environment. Calculation of their potential of both the inhalation pathway and ingestion pathway to man, their residence time in the oceans, their loss to sediments, the chemical state in which they exist in sea water, their oxidation states in sea water, and their biological availability to sea organisms are discussed. The areas where data are lacking are indicated. Studies on the Windscale Site (U.K.) are extensively referred to in the discussion of above-mentioned aspects. It is brought out that the study of the naturally occurring actinides can be useful in the understanding of behaviour of man-made radionuclides in the marine environment, because many of the former are good analogues of the latter. (M.G.B.)

  15. Low level radioactive waste produced from the Radioisotope Production Laboratory in Libya

    International Nuclear Information System (INIS)

    Elwaer, S.M.; Sharif, M.F.

    2005-01-01

    The Radioisotope Production Laboratory was established in 1980. The Production program depends mainly on the research reactor IRT. At the start of operation 131 I, 51 Cr, 35 S, 24 Na , 198 Au and 32 P were produced and supplied to the users. In the Last years some facilities had been upgraded in cooperation with IAEA such as the production of 99 mTc, 131 I, and 82 Br. Little and low level radioactive waste are produced during these activities. These radioactive wastes which produced after the production are: Cation resin column, glass- wool, Alumina column, Membrane filter, Disposal Filter Assembly, Syringe and needle, Na 2 99 MoO 4 solution after repeated extraction of 99 mTc from Na 2 99 MoO 4 solution for 5-7 days. TeO 2 Target after distillation of 131 I, laboratory glassware and vials, the aluminum containers which used for irradiation and the contaminated water used for the vacuum pump during the method of dry distillation of 131 I and Animal waste, including carcasses or other biological or pathological wastes contaminated with radioisotopes. The solid waste accumulated in suitable container for storage, shipment, further treatment, or disposal. Removal of over 99% of most long and short-lived products has been achieved in this manner by using anion and cation-exchange resin. (author)

  16. Application of radioisotope methods of investigation and control techniques in tube production

    International Nuclear Information System (INIS)

    Chizh, V.A.; Drabkin, L.A.

    1975-01-01

    Various spheres of radioactive isotopes application of closed and open type in tube production are described. Due to the usage of radioactive indicator method in combination with physicochemical methods and metallography new data are obtained in the theory and practice of tube centrifugal casting, rolling and pressing. Adsorption properties of lubricants and element distribution in the joint weld region of the big diameter tubes are investigated. The application of radioactive isotopes as ionizing radiation source made it possible to develop some radioisotope methods and instruments for tube wall thickness and the wall thickness difference control. Short characteristics of such instruments are given

  17. 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

  18. Universal methods of irradiating target materials for high current accelerator radioisotope production

    International Nuclear Information System (INIS)

    Stevensen, N.R.

    1997-01-01

    Five cyclotrons are situated on the TRIUMF site in Vancouver, Canada spanning a range from 1 to 520 MeV. Two of these cyclotrons are used primarily for the commercial production of medical radioisotopes: the CP42 is a 250 ,μA/42 MeV single beam H - machine that has been operating for the past 15 years. The TR30 is a 2x500 ,μA/30 MeV dual beam H - cyclotron that was commissioned in 1990. To match the increasing output capabilities of these cyclotrons we have incrementally improved our external 'solid' target systems to allow up to 1 μA at 30 MeV on electroplated materials. These advancements have incorporated design changes and choices of materials that are radiation-hard to minimize repairs and maintenance. A high current gas target and various encapsulated targets are also used for medical radioisotope production. An encapsulated target to produce radioiodines from tellurium oxide by (p,n) has been built to take advantage of beam time often available on low energy PET cyclotrons. This target provides for the on-line extraction of radioiodines as well as for the conventional batch process. A new, universal target system was designed and tested. It employs many of the tried and tested advantages of other individual target system while also allowing for the universal high current irradiation of most materials such as powders, foils, metals, fluids and low point melting materials

  19. The operation status and prospect of radioisotope production facility in HANARO

    International Nuclear Information System (INIS)

    Kim, Minjin; Lim, Incheol

    2008-01-01

    Researches and production of radio-isotopes, radio-pharmaceuticals and cold kits are carried out in the Radio-isotope Production Facility (RIPF). Four concrete hot cells in Bank-1 are to produce the Ir-192 source for NDT. Eleven lead hot cells in Bank-2 are to produce Ho-166, Cr-51, P-32/33, Tc-99m, Lu-177, Sr-90/Y-90 and W-188/Re-188 for research purpose. Six lead hot cells in Bank-3 are used for the production of I-131 for diagnosis and therapy of cancer in the hospital. A hot cell in Bank-3 is also utilized for the research of I-125 and Br-82. Four lead hot cells in Bank-4 are utilized for the production of Mo-99/Tc-99m generators since 2005. The major systems including the Heat and Ventilated Air Conditioning (HVAC) system and the air cleaning system such as charcoal and HEPA filter trains to filter the radioactive contaminants are in operation. So are the systems such as power supply and distribution system, UPS, fire protection system, liquid radioactive waste collection systems. Recently, the repair work and replacements of the air cleaning system are successfully finished and the replacement of the electric power supply systems is in progress because they almost reached the lifespan of the electrical components. In order to monitor the gas effluent of the building, a continuous air monitoring system is in operation to measure the concentration of I-131, noble gas and the particle at the stack of RIPF. Modification and upgrade of the main control panel and fire alarm and receiving panel are also in consideration to utilize the state-of-the-art technology so that the remote control and supervisory of RIPF would be enabled in the near future

  20. Hot alpha-emitting particles in residue of mining and metallurgy

    International Nuclear Information System (INIS)

    Freyer, K.; Treutler, H.C.; Weiss, H.; Ghose, R.; Selchau-Hansen, K.; Enge, W.

    1998-01-01

    Industrial residues of ore processing and metallurgy partly contain significant amounts of natural radionuclides. Such fine-grained, contaminated materials e.g. are scrubber dust slurry in the Mansfeld region, known as Theisenschlamm, and tailings of the uranium ore processing. The environmental significance of these materials in particular is related to the high mobility of its fine grain fractions by air and on the water path. By autoradiography using solid state nuclear track detectors the homogeneity of the distribution of alpha-emitting radionuclides in the above mentioned materials has been investigated. It has been found that beside a homogeneous background distribution of the alpha activity single spots with significant higher activity concentration exist in form of hot particles. Its concentration in different contaminated materials has been determined. A surfactant treatment process has been applied to separate uranium tailings material in different grain size fractions. The fractions have been characterized chemically, radiometrically and with respect to the amount of alpha-active hot particles. (orig.) [de

  1. The Origin and Evolution of Low-Redshift (z<2) Lyman Alpha Emitting Galaxies

    Science.gov (United States)

    Dey, Arjun; Reddy, Naveen; Prescott, Moire; Brodwin, Mark; Xu, Lei

    2010-08-01

    Low luminosity galaxies contribute significantly to the mass and star-formation density of the universe at early epochs. Ly(alpha) emitting galaxies (LAEs) are powerful probes of the low-luminosity end of the luminosity function, and are also used to place constraints on the reionization epoch and the early mass assembly of galaxies. Most LAE studies have focused primarily on high redshifts (z~3-7) where the physical nature and large-scale context of LAEs remain largely unconstrained. In order to remedy this situation, we have begun a survey for LAEs at 1.8LAEs, and spectroscopically confirmed our selection method. Here, we propose to extend our spectroscopic study to the UDS field, which has existing deep Spitzer imaging, and is targeted for deep near-IR imaging by the Hubble Multi-Cycle Treasury Program. The near- and mid-IR data coupled with spectroscopic redshifts are essential for determining the age and mass distributions of the LAEs. Our study will create the largest sample (~100) of spectroscopically confirmed LAEs with existing deep near- and mid-IR imaging, and will thus provide robust measurements of the stellar masses, ages, and reddening of LAEs, enabling us to directly determine their significance in the z~1.9 universe.

  2. A Low-Redshift (z< 2) Search for Lyman Alpha Emitting Galaxies

    Science.gov (United States)

    Prescott, Moire; Dey, Arjun; Reddy, Naveen

    2007-02-01

    Ly(alpha)-emitting (LAE) galaxy studies are powerful probes of the reionization epoch. However, these studies have primarily focused on high redshifts (z~3-7) and known overdensities, where the physical nature and large-scale context of LAEs remain largely unconstrained. We propose a search for LAEs at redshifts 1.7LAEs to examine the evolution of the LAE luminosity function (LF), their clustering properties, and the relationship between LAEs and UV-selected populations at these redshifts. While continuum-selected studies have targeted the bright- end of the galaxy LF, the low redshifts targeted in this survey combined with the use of Ly(alpha) line emission allow us to probe the faint-end which may contribute significantly to the total SFR density. By focusing on zLAEs in ways not feasible at higher redshifts. The survey will increase the number of galaxies known within the redshift `desert,' and uncover any luminous, spatially extended Ly(alpha) `blobs' in the field. In addition, unlike z> 2 LAE studies in which high equivalent width low- z interlopers can be culled only with spectroscopic campaigns, our proposed survey will not be contaminated by any low-z line- emitting populations. This project is part of the PI's thesis.

  3. Specific radioactivity of neutron induced radioisotopes: assessment methods and application for medically useful 177Lu production as a case.

    Science.gov (United States)

    Le, Van So

    2011-01-19

    The conventional reaction yield evaluation for radioisotope production is not sufficient to set up the optimal conditions for producing radionuclide products of the desired radiochemical quality. Alternatively, the specific radioactivity (SA) assessment, dealing with the relationship between the affecting factors and the inherent properties of the target and impurities, offers a way to optimally perform the irradiation for production of the best quality radioisotopes for various applications, especially for targeting radiopharmaceutical preparation. Neutron-capture characteristics, target impurity, side nuclear reactions, target burn-up and post-irradiation processing/cooling time are the main parameters affecting the SA of the radioisotope product. These parameters have been incorporated into the format of mathematical equations for the reaction yield and SA assessment. As a method demonstration, the SA assessment of 177Lu produced based on two different reactions, 176Lu (n,γ)177Lu and 176Yb (n,γ) 177Yb (β- decay) 177Lu, were performed. The irradiation time required for achieving a maximum yield and maximum SA value was evaluated for production based on the 176Lu (n,γ)177Lu reaction. The effect of several factors (such as elemental Lu and isotopic impurities) on the 177Lu SA degradation was evaluated for production based on the 176Yb (n,γ) 177Yb (β- decay) 177Lu reaction. The method of SA assessment of a mixture of several radioactive sources was developed for the radioisotope produced in a reactor from different targets.

  4. A proton-driven, intense, subcritical, fission neutron source for radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

    Jongen, Y. [Chemin du Cyclotron, Louvain-la-Neuve (Belgium)

    1995-10-01

    {sup 99m}Tc, the most frequently used radioisotope in nuclear medicine, is distributed as {sup 99}Mo=>{sup 99m}Tc generators. {sup 99}Mo is a fission product of {sup 235}U. To replace the aging nuclear reactors used today for this production, the author proposes to use a spallation neutron source, with neutron multiplication by fission. A 150 MeV, H{sup {minus}} cyclotron can produce a 225 kW proton beam with 50% total system energy efficiency. The proton beam would hit a molten lead target, surrounded by a water moderator and a graphite reflector, producing around 0.96 primary neutron per proton. The primary spallation neutrons, moderated, would strike secondary targets containing a subcritical amount of {sup 235}U. The assembly would show a k{sub eff} of 0.8, yielding a fivefold neutron multiplication. The thermal neutron flux at the targets location would be 2 {times} 10{sup 14} n/cm{sup 2}.s, resulting in a fission power of 500 to 750 kW. One such system could supply the world demand in {sup 99}Mo, as well as other radioisotopes. Preliminary indications show that the cost would be lower than the cost of a commercial 10 MW isotope production reactor. The cost of operation, of disposal of radiowaste and of decommissioning should be significantly lower as well. Finally, the non-critical nature of the system would make it more acceptable for the public than a nuclear reactor and should simplify the licensing process.

  5. Radioisotope conveyor ash meter

    International Nuclear Information System (INIS)

    Savelov, V.D.

    1994-01-01

    Radioisotope conveyor ash meter realizes persistent measuring of ashiness of coal and products of its enrichment on the belt conveyor without contact. The principle of ash meter acting is based on functional dependence of the gamma radiation flows backscattering intensity of radioisotope sources from the ash volume content in the controlled fuel. Facility consists from the ashiness transducer and the processing and control device

  6. Transmission factors for neutrons produced by radioisotopes production used in PET

    International Nuclear Information System (INIS)

    Hernandez G, D.; Cruzate, J.A.

    1996-01-01

    The dose transmission factor for normal concrete and the neutrons produced in the 18 O(p,n) 18 F and 13 C(p,n) 13 N reactions are presented in this paper. These transmission factors permit to simplify the calculation of the necessary accelerator shielding to be used in the radioisotope production for positron emission tomography. The energy distributions of the neutrons resulting from the irradiation of thick targets, with 10 to 13 MeV protons, were determined using the thin target cross sections, the energy loss per path length and the energy balance of the reaction (Q-equation). The one dimensional discrete ordinate transport code ANISN and the conversion coefficients from fluence to dose, presented in the ICRP Publication 51 were employed to obtain the transmission factors. (authors). 12 refs., 3 figs., 2 tabs

  7. Production and radiochemical separation of 203Pb radioisotope for nuclear medicine

    International Nuclear Information System (INIS)

    Szuecs, Z.; Takacs, S.; Andrasi, D.; Kovacs, B.

    2012-01-01

    Complete text of publication follows. The heavy metal pollution due to their industrial production, waste repository or accident as the cyanide spill in river Tisza in 2002, increase the scientific interest for using an ideal trace isotope for monitoring these type of events. The lead is one of the most toxic and commonly used heavy metal, its poisoning is often deadly because very difficult to recognize and identify. The neuro-scientific study of biodegradation effect of lead could be an impressive scientific field of application of 203 Pb radioisotope. However the targeted radionuclide therapy especially the α-emitting radioisotope therapy is also strongly interested to find an ideal tracer for the 213 Bi and 212 Pb therapy. Therefore the 203 Pb is a potential radioisotope for this role due to its radiation behaviour and as heavy metal element. The 203 Tl(p,n) 203 Pb nuclear reaction was chosen for the production. The irradiation was done at the compact cyclotron of Atomki with proton beam 14.5 MeV energy and beam current of 7 μAs. The thickness of the target material was 840 μm, the irradiation time was 3 hours and the produced activity was 40 MBq at EOB. It corresponds to 1.87 MBq/μAh physical yield of the reaction which correlating with the cross section curve. A new technique was developed for target preparation. The metal Tl was pressed into a copper backing and covered with a HAWAR foil with thickness of 11 μm. The covering foil saved the surface of the Tl from the oxidation and also transferred the dissipating heat to the cooling He gas. The back side of the target was cooled with pressured cold water. The irradiated Tl target was pressed out from the copper backing, which had only the thickness of 0.2 mm. Then the Thallium was dissolved in nitric acid. The excess acid was evaporated slowly. The nitrate form was transferred to chloride form by 8 mol/dm 3 HCl and the Thallium was kept in 3+ oxidation stage by hydrogen peroxide. The separation was

  8. Alternating sample changer and an automatic sample changer for liquid scintillation counting of alpha-emitting materials

    International Nuclear Information System (INIS)

    Thorngate, J.H.

    1977-08-01

    Two sample changers are described that were designed for liquid scintillation counting of alpha-emitting samples prepared using solvent-extraction chemistry. One operates manually but changes samples without exposing the photomultiplier tube to light, allowing the high voltage to remain on for improved stability. The other is capable of automatically counting up to 39 samples. An electronic control for the automatic sample changer is also described

  9. Summary report of the consultants' meeting on nuclear data for production of therapeutic radioisotopes

    International Nuclear Information System (INIS)

    Haight, R.C.; Paviotti-Corcuera, R.

    2002-04-01

    This report summarizes the presentations, recommendations and conclusions of the Consultants' Meeting on Nuclear Data for Production of Therapeutic Radioisotopes. The purpose of this meeting was to discuss scientific and technical matters related to the subject and to advise the IAEA Nuclear Data Section (NDS) on the need and possible formation of a Coordinated Research Programme (CRP). Accurate and complete knowledge of nuclear data are essential for the production of radionuclides for therapy to achieve the specific activity and purity required for efficient and safe clinical application. The Consultants recommended updating and completing the data for production of radionuclides that are recognized to be important in therapy. In addition, the consultants recommend investigating other radionuclides that have a potential interest and for which there exists a medical rationale for therapeutic use. To date no serious effort has been devoted to evaluation of nuclear data for the reactor and accelerator production of therapeutic radionuclides. The IAEA is in the unique and privileged position to address this important public health related problem. Therefore, the consultants highly recommend the formation of a CRP with the title: 'Nuclear Data for Production of Therapeutic Radionuclides.' (author)

  10. HETDEX: Developing the HET's Second Generation Low Resolution Spectrograph for Probing Lyman-alpha Emitting Galaxies

    Science.gov (United States)

    Chonis, Taylor S.; Hill, G. J.; Lee, H.; Tuttle, S. E.; Vattiat, B. L.; Gebhardt, K.; Finkelstein, S. L.; Adams, J. J.; HETDEX Collaboration

    2012-01-01

    HETDEX will map the power spectrum of 0.8 million blindly discovered Lyman-alpha Emitting Galaxies (LAE) using a revolutionary new array of massively replicated fiber-fed spectrographs dubbed the Visible Integral-Field Replicable Unit Spectrograph (VIRUS). In the era of the Hobby-Eberly Telescope wide-field upgrade and VIRUS, the current Low Resolution Spectrograph (LRS) must be replaced with a fiber instrument. We discuss the development of the second generation LRS (LRS2), which is a multi-channel instrument based on the VIRUS design. In its current design phase, it is fed by a 287 fiber microlens coupled integral field unit that covers 7” x 12” with 0.62” resolution. The instrument covers 3720 Å to 4700 Å at R ≈ 1900 and 4600 Å to 7000 Å at R ≈1200. With the purpose of making the instrument ideal for follow-up observations of LAE in the HETDEX survey, we discuss the science drivers for selecting the instrument's spectral resolution. We test the utility of the instrument and pilot a future study with LRS2 by presenting R ≈ 2000 spectra taken with the VIRUS prototype spectrograph (VIRUS-P) in a high-resolution mode at the McDonald Observatory Harlan J. Smith 2.7 m telescope. These LAE were originally discovered in the HETDEX Pilot Survey and their Lyman-alpha line profiles are constrained by near-infrared observations of rest-frame optical emission lines that set the systemic redshift of the galaxies. We discuss the velocity offsets of the Lyman-alpha line from the systemic line center and compare the line profiles to theoretical predictions and to similar observations for Lyman-break galaxies. Our observations provide an example of how LRS2 can be used to probe Lyman-alpha emission in 2 < z < 3 star forming galaxies.

  11. HETDEX and the Evolution of The Physical Properties of Lyman-Alpha Emitting Galaxies

    Science.gov (United States)

    Ciardullo, Robin; Gronwall, C.; Blanc, G.; Finkelstein, S.; Gawiser, E.; Gebhardt, K.; HETDEX Collaboration

    2012-05-01

    Beginning in Spring 2013, the Hobby-Eberly Telescope Dark Energy Experiment (HETDEX) will begin a three year survey of two large regions of sky using VIRUS, an array of blue-sensitive integral-field spectrographs set to cover the wavelength range between 3500 to 5500 Angstroms at R = 800 resolution. These data will cover roughly 300 square degrees in the north (centered near 13 hours, +53 deg) and 140 square degrees along the equator (centered around 1.5 hours), have a filling factor of 1 in 4.5, and detect over 800,000 Lyman-alpha emitting galaxies (LAEs) in the redshift range 1.9 LAE's power spectrum, these data will also revolutionize our knowledge of the emission-line universe. Using HETDEX, we will be able to explore the 3-D clustering of LAEs, measure their halo masses, and explore their physical properties over a wide range of galactic environments. In preparation for HETDEX, we have undertaken a 3 year pilot survey of the COSMOS, GOODS-N, MUNICS-S2, and XMM-LSS regions of sky using VIRUS-P, a proto-type integral-field spectrograph placed on the McDonald 2.7-m telescope. This survey covered 169 square arcmin and discovered 104 LAEs with a median line luminosity of log L = 43.03 ergs/s. We will present the physical properties of the LAEs found in the pilot survey, and discuss how their line-luminosities, equivalent widths, star-formation rates, dust content, and Ly-alpha escape fraction change with redshift. We will also discuss the implications of the these observations for the main HETDEX survey.

  12. Radio-isotope production scale-up at the University of Wisconsin

    Energy Technology Data Exchange (ETDEWEB)

    Nickles, Robert Jerome [Univ of Wisconsin

    2014-06-19

    Our intent has been to scale up our production capacity for a subset of the NSAC-I list of radioisotopes in jeopardy, so as to make a significant impact on the projected national needs for Cu-64, Zr-89, Y-86, Ga-66, Br-76, I-124 and other radioisotopes that offer promise as PET synthons. The work-flow and milestones in this project have been compressed into a single year (Aug 1, 2012- July 31, 2013). The grant budget was virtually dominated by the purchase of a pair of dual-mini-cells that have made the scale-up possible, now permitting the Curie-level processing of Cu-64 and Zr-89 with greatly reduced radiation exposure. Mile stones: 1. We doubled our production of Cu-64 and Zr-89 during the grant period, both for local use and out-bound distribution to ≈ 30 labs nationwide. This involved the dove-tailing of beam schedules of both our PETtrace and legacy RDS cyclotron. 2. Implemented improved chemical separation of Zr-89, Ga-66, Y-86 and Sc-44, with remote, semi-automated dissolution, trap-and-release separation under LabView control in the two dual-mini-cells provided by this DOE grant. A key advance was to fit the chemical stream with miniature radiation detectors to confirm the transfer operations. 3. Implemented improved shipping of radioisotopes (Cu-64, Zr-89, Tc-95m, and Ho-163) with approved DOT 7A boxes, with a much-improved FedEx shipping success compared to our previous steel drums. 4. Implemented broad range quantitative trace metal analysis, employing a new microwave plasma atomic emission spectrometer (Agilent 4200) capable of ppb sensitivity across the periodic table. This new instrument will prove essential in bringing our radiometals into FDA compliance needing CoA’s for translational research in clinical trials. 5. Expanded our capabilities in target fabrication, with the purchase of a programmable 1600 oC inert gas tube furnace for the smelting of binary alloy target materials. A similar effort makes use of our RF induction furnace, allowing

  13. A novel approach to the production of medical radioisotopes: the homogeneous SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2015-01-01

    In 2009, the unexpected 15-month outage of the Canadian NRU nuclear reactor resulted in a sudden 30% world shortage, with higher shortages experienced in North America than in Europe. Commercial radioisotope production is from just eight nuclear reactors, most being aging systems near the end of their service life. This paper proposes a more efficient production and distribution model. Tc-99m unit doses would be distributed to regional hospitals from ten integrated 'industrial radiopharmacies', located at existing licensed nuclear reactor sites in North America. At each site, one or more 20 kW Homogeneous SLOWPOKE nuclear reactors would deliver 15 litres of irradiated aqueous uranyl sulfate fuel solution daily to industrial-scale hot cells, for extraction of Mo-99; and the low-enriched uranium would be recycled. Purified Mo-99 would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily for road delivery to all of the nuclear medicine hospitals within a 3-hour range. At the current price of $20 per unit dose, the annual gross income from 10 sites would be approximately $360 million. The Homogeneous SLOWPOKE reactor evolved from the inherently safe SLOWPOKE-2 research reactor, with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors at the end-of-core life, enabling them to continue their primary missions of research and education, together with full time commercial radioisotope production. The Homogeneous SLOWPOKE reactor was modelled using both deterministic and probabilistic reactor simulation codes. The homogeneous fuel mixture is a dilute aqueous solution of low-enriched uranyl sulfate containing approximately 1 kg of U-235. The reactor is controlled by mechanical absorber rods in the beryllium reflector. Safety analysis was carried out for both normal operation and transient conditions. The most severe

  14. A novel approach to the production of medical radioisotopes: the homogeneous SLOWPOKE reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [retired, Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Royal Canadian Navy, Ottawa, Ontario (Canada)

    2015-03-15

    In 2009, the unexpected 15-month outage of the Canadian NRU nuclear reactor resulted in a sudden 30% world shortage, with higher shortages experienced in North America than in Europe. Commercial radioisotope production is from just eight nuclear reactors, most being aging systems near the end of their service life. This paper proposes a more efficient production and distribution model. Tc-99m unit doses would be distributed to regional hospitals from ten integrated 'industrial radiopharmacies', located at existing licensed nuclear reactor sites in North America. At each site, one or more 20 kW Homogeneous SLOWPOKE nuclear reactors would deliver 15 litres of irradiated aqueous uranyl sulfate fuel solution daily to industrial-scale hot cells, for extraction of Mo-99; and the low-enriched uranium would be recycled. Purified Mo-99 would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily for road delivery to all of the nuclear medicine hospitals within a 3-hour range. At the current price of $20 per unit dose, the annual gross income from 10 sites would be approximately $360 million. The Homogeneous SLOWPOKE reactor evolved from the inherently safe SLOWPOKE-2 research reactor, with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors at the end-of-core life, enabling them to continue their primary missions of research and education, together with full time commercial radioisotope production. The Homogeneous SLOWPOKE reactor was modelled using both deterministic and probabilistic reactor simulation codes. The homogeneous fuel mixture is a dilute aqueous solution of low-enriched uranyl sulfate containing approximately 1 kg of U-235. The reactor is controlled by mechanical absorber rods in the beryllium reflector. Safety analysis was carried out for both normal operation and transient conditions. The most severe

  15. IPENS's social role in scientific and technological development of radioisotope and radiopharmaceutical production - (1950 -1980)

    International Nuclear Information System (INIS)

    Gordon, Ana Maria P.L.

    2009-01-01

    Some facts and figures are present in the existent interaction between the Instituto de Pesquisas Energeticas e Nucleares (IPEN) and the medical community. Among other characteristics, the IPEN has a permanent seat in the Biology and Nuclear Medicine Society and, the present Radiopharmacy Center, has had the continuous concern, since the Instituto de Energia Atomica (IEA) creation until today (2009), to perform an excellent approach with the medical faculty. In the past, some physicians would complete their courses in Europe and in the United States of America, and there noticed the importance of radioisotopes applications in medicine, mainly, in the beginning of these activities, with the I-131. Returning to Brazil, they requested that the former IEA, today IPEN researchers used the research reactor IEA-R1, installed in Sao Paulo, at Universidade Sao Paulo (USP) campus, for radioisotopes production. Then, in the late 1959, the first production line from the I-131 took place. The IPEN starts to accomplish what was planned as one of its targets, at the act of its official creation on August 31, 1956. From 1961 on, there was a continuous flux of I-131 and other radiopharmaceuticals production. The recovery and analysis of these happenings, in the Brazilian society cultural historic context, were partially published in different previous works. Nevertheless, history is dynamic and gains new interpretations, in the present research, from the reading of novel research sources, both primary and secondary, not explores so far - reports, interviews with IPEN researchers and papers published or divulged in meetings, either scientific or bureaucratic. This research is part of project supported by the Fundacao de Amparo a Pesquisa do Estado de Sao Paulo (FAPESP), with the aim, among others, of contributing for the analysis of the transformations occurred in all of the IPEN research lines, plus the social role of this institution for science and technology development. The

  16. Production and world-wide distribution of radioisotopes and allied products from NTP at Pelindaba, South Africa

    International Nuclear Information System (INIS)

    Louw, P.A.

    2001-01-01

    Nuclear Technology Products (NTP) a business division of the South African Nuclear Energy Corporation Ltd. (NECSA) is today a leading supplier of a range or radioisotope and supporting products to markets throughout the world. To achieve this status in the face of large technological, logistical and business barriers to entry has required the development of integrated and effective processes from a diverse and unconsolidated range of expertise and other resources. The various facilities and competencies established at NECSA over a period of 40 years had as their objective the accomplishment of strictly non-commercial strategic imperatives. Major emphasis was placed at Pelindaba on development of the capability to beneficiate the country's resources of uranium which are extracted as a by-product of gold mining. Fuel enrichment processes (using a method unique to NECSA) and nuclear fuel fabrication facilities were developed and commissioned during the period 1975 - 1990 and substantial quantities of enriched and depleted uranium material was produced. A small amount of locally produced, highly enriched fuel has been used to power the 20 MW SARARI -1 Research Reactor at Pelindaba which has been in operation since 1965. Major political and economic changes affecting South Africa gave rise, in the late 1980s, to the necessity for a fundamental strategic reorientation of NECSA. Over a period of time the fuel enrichment and fabrication programmes were terminated and ever greater emphasis was placed on development of businesses from established, diverse facilities and competencies with the objective of promoting increased financial independence and long term viability for the organisation. It was at this time that NTP the business responsible for production and marketing of radiation-based products at NECSA, was established. The various developments which facilitated the capacity of NTP to accede to its current position as a significant and growing provider of

  17. Production and Clinical Applications of Radiopharmaceuticals and Medical Radioisotopes in Iran.

    Science.gov (United States)

    Jalilian, Amir Reza; Beiki, Davood; Hassanzadeh-Rad, Arman; Eftekhari, Arash; Geramifar, Parham; Eftekhari, Mohammad

    2016-07-01

    During past 3 decades, nuclear medicine has flourished as vibrant and independent medical specialty in Iran. Since that time, more than 200 nuclear physicians have been trained and now practicing in nearly 158 centers throughout the country. In the same period, Tc-99m generators and variety of cold kits for conventional nuclear medicine were locally produced for the first time. Local production has continued to mature in robust manner while fulfilling international standards. To meet the ever-growing demand at the national level and with international achievements in mind, work for production of other Tc-99m-based peptides such as ubiquicidin, bombesin, octreotide, and more recently a kit formulation for Tc-99m TRODAT-1 for clinical use was introduced. Other than the Tehran Research Reactor, the oldest facility active in production of medical radioisotopes, there is one commercial and three hospital-based cyclotrons currently operational in the country. I-131 has been one of the oldest radioisotope produced in Iran and traditionally used for treatment of thyrotoxicosis and differentiated thyroid carcinoma. Since 2009, (131)I-meta-iodobenzylguanidine has been locally available for diagnostic applications. Gallium-67 citrate, thallium-201 thallous chloride, and Indium-111 in the form of DTPA and Oxine are among the early cyclotron-produced tracers available in Iran for about 2 decades. Rb-81/Kr-81m generator has been available for pulmonary ventilation studies since 1996. Experimental production of PET radiopharmaceuticals began in 1998. This work has culminated with development and optimization of the high-scale production line of (18)F-FDG shortly after installation of PET/CT scanner in 2012. In the field of therapy, other than the use of old timers such as I-131 and different forms of P-32, there has been quite a significant advancement in production and application of therapeutic radiopharmaceuticals in recent years. Application of (131)I

  18. Evaluation of the population dose due to the gaseous emission of a radioisotopes production unit

    International Nuclear Information System (INIS)

    Gordon, A.M.P.L.; Jacomino, V.M.F.; Sordi, G.-M.A.A.

    1990-05-01

    In order to control the emission of gaseous radioactive iodine from the unit responsible for the production of radioisotopes of IPEN-CNEN/SP, a discharge monitoring is carried out. In 1988 an activity of 65 GBq of I-131 was discharged to the environment. Based upon this value and the site analysis, the effective equivalent dose in the general public was evaluated for normal operation and for an incidental discharge. The evaluation was carried out by using a diffusion atmospheric model, 500 to 7000 m away from the discharge point and using 8 different wind direction sectors. The critical group was identified as being the people who lives 3000 m far from the discharge point, in the diffusion sector NW. The dose evaluated at this point is 10 9 times lower than the annual dose limit for individual of the public, according to Radiological Protection Standards. The derived limit for discharge of iodine was also evaluated and it was concluded that the IPEN-CNEN/SP can increase their production up to a level which results in an annual discharge of 1,5 x 10 12 of I-131. (author) [pt

  19. Production and supply of radioisotopes with reactors in north america and europe current status and future prospects

    International Nuclear Information System (INIS)

    Trevena, I.

    1994-01-01

    Reactors have played a key pole in the production of radioactive isotopes for medical applications for the past 50 years. This paper reviews current and future capabilities for the production and supply of radioactive isotopes used in nuclear medicine. It focuses primarily on the supply of fission product molybdenum-99, which is used to produce technetium-99m, the radioisotope most widely employed in nuclear medicine procedures. The significant infrastructure required for the production and supply of molybdenum-99 is detailed, and the capabilities of the major commercial suppliers in North America and Europe are discussed. Plans for increasing production capabilities in the future are also reviewed. (author)

  20. Operational Readiness Review Plan for the Radioisotope Thermoelectric Generator Materials Production Tasks

    Science.gov (United States)

    Cooper, R. H.; Martin, M. M.; Riggs, C. R.; Beatty, R. L.; Ohriner, E. K.; Escher, R. N.

    1990-04-19

    In October 1989, a US shuttle lifted off from Cape Kennedy carrying the spacecraft Galileo on its mission to Jupiter. In November 1990, a second spacecraft, Ulysses, will be launched from Cape Kennedy with a mission to study the polar regions of the sun. The prime source of power for both spacecraft is a series of radioisotope thermoelectric generators (RTGs), which use plutonium oxide (plutonia) as a heat source. Several of the key components in this power system are required to ensure the safety of both the public and the environment and were manufactured at Oak Ridge National Laboratory (ORNL) in the 1980 to 1983 period. For these two missions, Martin Marietta Energy Systems, Inc. (Energy Systems), will provide an iridium alloy component used to contain the plutonia heat source and a carbon composite material that serves as a thermal insulator. ORNL alone will continue to fabricate the carbon composite material. Because of the importance to DOE that Energy Systems deliver these high quality components on time, performance of an Operational Readiness Review (ORR) of these manufacturing activities is necessary. Energy Systems Policy GP 24 entitled "Operational Readiness Process" describes the formal and comprehensive process by which appropriate Energy Systems activities are to be reviewed to ensure their readiness. This Energy System policy is aimed at reducing the risks associated with mission success and requires a management approved "readiness plan" to be issued. This document is the readiness plan for the RTG materials production tasks.

  1. Present status of research on Re-186 radiopharmaceuticals at Radioisotope Production Center

    Energy Technology Data Exchange (ETDEWEB)

    Mutalib, A. [Radioisotope Production Center, National Atomic Energy Agency Kawasan PUSPIPTEK, Serpong (Indonesia)

    1998-10-01

    Rhenium shows a close chemical similarity to technetium and is suitable for radiotherapy because the {beta}-emitting radionuclides {sup 186}Re (t{sub 1/2} 90 h, E{sub {beta}} = 1.1 MeV, E{sub {gamma}} = 137 keV) and {sup 188}Re (t{sub 1/2} = 17 h, E{sub {beta}} = 2.1 MeV). The {gamma}-emission associated with decay of {sup 186}Re is also useful in scintigraphy. The research on {sup 186}Re radiopharmaceuticals at Radioisotope Production Center has been carried out since April 1997. Interest in radioimmunotherapy (RIT) led us to the development of labeling antibodies with rhenium isotopes. Although there are several methods for coupling radiometal to antibody, we prefer an indirect labeling method in which a bifunctional chelating agent is used for coupling of {sup 186}Re to monoclonal antibodies. In this report we outline the study on the preparation of {sup 186}Re DMSA-TFP as precursor for labeling with monoclonal antibody. (author)

  2. Coordination chemistry of the {sup 212}Pb/{sup 212}Bi nuclear transformation: Alpha-emitting radiopharmaceuticals. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Parks, N.J.; Harris, W.R.; Keen, C.L.; Cooper, S.R.

    1992-07-01

    Subdivisions of this project are: (a) the synthesis of prototypical thiolate and dithiocarbamate based hexacoordinate complexes, (b) radiochemical engineering for generation of no-carrier-added lead and bismuth radioelements, (c) the first isolation of bismuth-binding proteins from in vivo studies with cyclotron produced {sup 205/206}Bi tracer, and (d) initial development of transport mechanisms for the intracellular radiobiological study of alpha emitting bismuth, and (e) the initiation of chemical equilibrium studies and biochemical pathways with cyclotron-produced, no-carrier-added, {sup 203}Pb (T{sub 1/2} = 51 hr).

  3. Dosimetry of bone metastases in targeted radionuclide therapy with alpha-emitting (223)Ra-dichloride.

    Science.gov (United States)

    Pacilio, Massimiliano; Ventroni, Guido; De Vincentis, Giuseppe; Cassano, Bartolomeo; Pellegrini, Rosanna; Di Castro, Elisabetta; Frantellizzi, Viviana; Follacchio, Giulia Anna; Garkavaya, Tatiana; Lorenzon, Leda; Ialongo, Pasquale; Pani, Roberto; Mango, Lucio

    2016-01-01

    Ra-dichloride is an alpha-emitting radiopharmaceutical used in the treatment of bone metastases from castration-resistant prostate cancer. Image-based dosimetric studies remain challenging because the emitted photons are few. The aim of this study was to implement a methodology for in-vivo quantitative planar imaging, and to assess the absorbed dose to lesions using the MIRD approach. The study included nine Caucasian patients with 24 lesions (6 humeral head lesions, 4 iliac wing lesions, 2 scapular lesions, 5 trochanter lesions, 3 vertebral lesions, 3 glenoid lesions, 1 coxofemoral lesion). The treatment consisted of six injections (one every 4 weeks) of 50 kBq per kg body weight. Gamma-camera calibrations for (223)Ra included measurements of sensitivity and transmission curves. Patients were statically imaged for 30 min, using an MEGP collimator, double-peak acquisition, and filtering to improve the image quality. Lesions were delineated on (99m)Tc-MDP whole-body images, and the ROIs superimposed on the (223)Ra images after image coregistration. The activity was quantified with background, attenuation, and scatter correction. Absorbed doses were assessed deriving the S values from the S factors for soft-tissue spheres of OLINDA/EXM, evaluating the lesion volumes by delineation on the CT images. In 12 lesions with a wash-in phase the biokinetics were assumed to be biexponential, and to be monoexponential in the remainder. The optimal timing for serial acquisitions was between 1 and 5 h, between 18 and 24 h, between 48 and 60 h, and between 7 and 15 days. The error in cumulated activity neglecting the wash-in phase was between 2 % and 12 %. The mean effective half-life (T 1/2eff) of (223)Ra was 8.2 days (range 5.5-11.4 days). The absorbed dose (D) after the first injection was 0.7 Gy (range 0.2-1.9 Gy. Considering the relative biological effectiveness (RBE) of alpha particles (RBE = 5), D RBE = 899 mGy/MBq (range 340-2,450 mGy/MBq). The

  4. Extension of the irradiation system at TIARA for production of radioisotopes to be used in plant physiology

    International Nuclear Information System (INIS)

    Ishioka, N.S.; Watanabe, S.; Fujimaki, S.; Sakamoto, K.; Matsuhashi, S.

    2005-01-01

    A target irradiation system for radioisotope production at the TIARA AVF cyclotron facility has been improved for extending physiological studies of plants. Experiments using a position imaging technique require a variety of positron-emitting radioisotopes and their labelled compounds. Therefore, a compact revolver equipped with six target cambers for gas and liquid targets were newly constructed, in addition to the original target irradiation system consisting of two solid target chambers and one gas target chamber, placed on the movable table. The control system was also reconstructed with a local area network for communication between the control station beside the irradiation port and the hot laboratory. Use of this system enables us to produce routinely positron-emitting tracers for plant physiology. (author)

  5. Regulations of 1 March 1983 relating to production, imports and sales of radioisotopes

    International Nuclear Information System (INIS)

    1983-01-01

    These regulations were issued by the Ministry of Health and Social Affairs, pursuant to the Act of 19th June 1938 on the use of radium and X-rays etc. The Regulations came into force on the date they were issued. They apply to radioisotopes used for industrial, commercial, agricultural, medical and scientific purposes. (NEA) [fr

  6. Automatic system of production, transfer and processing of coin targets for the production of metallic radioisotopes

    Science.gov (United States)

    Pellicioli, M.; Ouadi, A.; Marchand, P.; Foehrenbacher, T.; Schuler, J.; Dick-Schuler, N.; Brasse, D.

    2017-05-01

    The work presented in this paper gathers three main technical developments aiming at 1) optimizing nuclide production by the mean of solid targets 2) automatically transferring coin targets from vault to hotcell without human intervention 3) processing target dilution and purification in hotcell automatically. This system has been installed on a ACSI TR24 cyclotron in Strasbourg France.

  7. submitter Development of a Superconducting Magnet for a Compact Cyclotron for Radioisotope Production

    CERN Document Server

    Garcia-Tabares, Luis; Calero, Jesus; Gutierrez, Jose L; Munilla, Javier; Obradors, Diego; Perez, Jose M; Toral, Fernando; Iturbe, Rafael; Minguez, Leire; Gomez, Jose; Rodilla, Elena; Bajko, Marta; Michels, Matthias; Berkowitz, Daniel; Haug, Friedrich

    2016-01-01

    The present paper describes the development process of a low critical temperature superconducting magnet to be installed in a compact cyclotron producing single-dose radioisotopes for clinical and preclinical applications. After a brief description of the accelerator, the magnet development process is described, starting from the magnetic, mechanical, quench, and thermal calculations, continuing with the designing process, particularly the support structure of the magnet and the cryogenic supply system, to finish with the fabrication and the first tests than have been performed.

  8. Thyroid Dose Estimation Using WBC and I-131 Concentration in Working Area of Radioisotope Production at Normal Operation

    International Nuclear Information System (INIS)

    Tedjasari, R S; Lubis, E

    1996-01-01

    Thyroid dose estimation at Radioisotope Production Centre workers using WBC and calculation based on I-131 concentration in working area has been done. The aim of this research is to get the relation between WBC result and calculation using I-131 concentration in working area. The result indicates differences in a range of 3,2% to 53,2%. These differences caused of parameters which influence the calculation are not accurate. These results also indicate that dose estimation using WBC is relatively batter and more accurate but need to have certain information about time of intake

  9. Production of medical radioisotopes in the ORNL High Flux Isotope Reactor (HFIR) for cancer treatment and arterial restenosis therapy after PTCA

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Beets, A.L.; Mirzadeh, S.; Alexander, C.W.; Hobbs, R.L.

    1998-01-01

    The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) represents an important resource for the production of a wide variety of medical radioisotopes. In addition to serving as a key production site for californium-252 and other transuranic elements, important examples of therapeutic radioisotopes which are currently routinely produced in the HFIR for distribution include dysprosium-166 (parent of holmium-166), rhenium-186, tin-117m and tungsten-188 (parent of rhenium-188). The nine hydraulic tube (HT) positions in the central high flux region permit the insertion and removal of targets at any time during the operating cycle and have traditionally represented a major site for production of medical radioisotopes. To increase the irradiation capabilities of the HFIR, special target holders have recently been designed and fabricated which will be installed in the six Peripheral Target Positions (PTP), which are also located in the high flux region. These positions are only accessible during reactor refueling and will be used for long-term irradiations, such as required for the production of tin-117m and tungsten-188. Each of the PTP tubes will be capable of housing a maximum of eight HT targets, thus increasing the total maximum number of HT targets from the current nine, to a total of 57. In this paper the therapeutic use of reactor-produced radioisotopes for bone pain palliation and vascular brachytherapy and the therapeutic medical radioisotope production capabilities of the ORNL HFIR are briefly discussed

  10. Production of medical radioisotopes in the ORNL High Flux Isotope Reactor (HFIR) for cancer treatment and arterial restenosis therapy after PTCA

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Beets, A.L.; Mirzadeh, S.; Alexander, C.W.; Hobbs, R.L.

    1998-06-01

    The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) represents an important resource for the production of a wide variety of medical radioisotopes. In addition to serving as a key production site for californium-252 and other transuranic elements, important examples of therapeutic radioisotopes which are currently routinely produced in the HFIR for distribution include dysprosium-166 (parent of holmium-166), rhenium-186, tin-117m and tungsten-188 (parent of rhenium-188). The nine hydraulic tube (HT) positions in the central high flux region permit the insertion and removal of targets at any time during the operating cycle and have traditionally represented a major site for production of medical radioisotopes. To increase the irradiation capabilities of the HFIR, special target holders have recently been designed and fabricated which will be installed in the six Peripheral Target Positions (PTP), which are also located in the high flux region. These positions are only accessible during reactor refueling and will be used for long-term irradiations, such as required for the production of tin-117m and tungsten-188. Each of the PTP tubes will be capable of housing a maximum of eight HT targets, thus increasing the total maximum number of HT targets from the current nine, to a total of 57. In this paper the therapeutic use of reactor-produced radioisotopes for bone pain palliation and vascular brachytherapy and the therapeutic medical radioisotope production capabilities of the ORNL HFIR are briefly discussed.

  11. Production of Medical Radioisotopes in the ORNL High Flux Isotope Reactor (HFIR) for Cancer Treatment and Arterial Restenosis Therapy after PTCA

    Science.gov (United States)

    Knapp, F. F. Jr.; Beets, A. L.; Mirzadeh, S.; Alexander, C. W.; Hobbs, R. L.

    1998-06-01

    The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) represents an important resource for the production of a wide variety of medical radioisotopes. In addition to serving as a key production site for californium-252 and other transuranic elements, important examples of therapeutic radioisotopes which are currently routinely produced in the HFIR for distribution include dysprosium-166 (parent of holmium-166), rhenium-186, tin-117m and tungsten-188 (parent of rhenium-188). The nine hydraulic tube (HT) positions in the central high flux region permit the insertion and removal of targets at any time during the operating cycle and have traditionally represented a major site for production of medical radioisotopes. To increase the irradiation capabilities of the HFIR, special target holders have recently been designed and fabricated which will be installed in the six Peripheral Target Positions (PTP), which are also located in the high flux region. These positions are only accessible during reactor refueling and will be used for long-term irradiations, such as required for the production of tin-117m and tungsten-188. Each of the PTP tubes will be capable of housing a maximum of eight HT targets, thus increasing the total maximum number of HT targets from the current nine, to a total of 57. In this paper the therapeutic use of reactor-produced radioisotopes for bone pain palliation and vascular brachytherapy and the therapeutic medical radioisotope production capabilities of the ORNL HFIR are briefly discussed.

  12. A sequential method for the determination of 210Pb, 226Ra, and uranium and thorium radioisotopes by LSC and alpha-spectrometry.

    Science.gov (United States)

    Lozano, J C; Tomé, F Vera; Rodríguez, P Blanco; Prieto, C

    2010-01-01

    A procedure for the determination of (210)Pb, and alpha-emitting radioisotopes of uranium, thorium, and radium from the same aliquot of a sample has been proposed. The key step consisted in the recovery of Pb(II) and Ra by precipitation of insoluble Pb(NO(3))(2), the uranium and thorium radioisotopes remaining in solution. Afterwards, the fractions were handled by specific, well consolidated procedures. Lead-210 was determined by the LSC technique while the uranium, thorium, and radium radioisotopes were measured with silicon alpha-spectrometers. The procedure was applied to a reference sample and several environmental samples obtaining satisfactory results. Copyright 2009 Elsevier Ltd. All rights reserved.

  13. Reactor-produced therapeutic radioisotopes

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.

    2002-01-01

    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

  14. Production of medical radioisotopes in the ORNL high flux isotope reactor (HFIR) for cancer treatment and arterial restenosis therapy after PICA

    Science.gov (United States)

    Knapp, F. F.; Beets, A. L.; Mirzadeh, S.; Alexander, C. W.; Hobbs, R. L.

    1999-01-01

    The High Flux Isotope Reactor ( HFIR) at the Oak Ridge National Laboratory ( ORNL) represents an important resource for the production of a wide variety of medical radioisotopes. First beginning operation in 1965, the high thermal neutron flux (2.5×1015 neutrons/cm2/sec at 85 MW) and versatile target irradiation and handling facilities provide the opportunity for production of a wide variety of neutron-rich medical radioisotopes of current interest for therapy. In addition to serving as a key production site for californium-252 and other transuranic elements, important examples of therapeutic radioisotopes which are currently routinely produced in the HFIR for distribution include dysprosium-166 (parent of holmium-166), rhenium-186, tin-117 m and tungsten-188 (parent of rhenium-188). The nine hydraulic tube ( HT) positions in the central high flux region permit the insertion and removal of targets at any time during the operating cycle (22-24 days) and have traditionally represented a major site for production of medical radioisotopes. To increase the irradiation capabilities of the HFIR, special target holders have recently been designed and fabricated which will be installed in the six Peripheral Target Positions ( PTP), which are also located in the high flux region. These positions are only accessible during reactor refueling and will be used for long-term irradiations, such as required for the production of tin-117 m and tungsten-188. Each of the PTP tubes will be capable of housing a maximum of eight HT targets, thus increasing the total maximum number of HT targets from the current nine, to a total of 57. In this paper the therapeutic use of reactor-produced radioisotopes for bone pain palliation and vascular brachytherapy and the therapeutic medical radioisotope production capabilities of the ORNL HFIR are briefly discussed.

  15. Cyclotron production of molecules labelled with short-lived radioisotopes β+ emitters (15O, 13N, 11C) and their clinical uses

    International Nuclear Information System (INIS)

    Bougharouat, B.

    1981-01-01

    Clinical use of three short-lived radioisotopes: 15 O, 13 N and 11 C is studied on two complementary aspects. A production and purification system is realized; detection instruments in medical use are studied. The production of labelled molecules with the three radiotracers 15 O, 13 N, 11 C from the target bombardment with charged and accelerated particles was studied [fr

  16. Radioisotope method for characterization of vegetable tannins, extracted from waste of forestry production in Cuba

    International Nuclear Information System (INIS)

    Santana Romero, J.L.; Martinez Luzardo, F.; Codorniu Hernandez, E.; Vargas Guerra, L.; Melo Cala, P.; Garcia Guillen, M.; Isaac Olive, K.; Estevez, P.; Roque Cordoba, A.; Benitez, M.

    2002-01-01

    Vegetable tannins are polyphenolic plants secondary metabolites, widely distributed in all parts of trees and herbs. The role of these substances in many metabolic processes is very important. Vegetable tannins have been implicated as probable antinutritional factors, decreasing the assimilation of diet protein assimilation by cattle. On the other hand, protective antioxidant and antimutagenic properties have been ascribed for these compounds. Characterization of vegetable tannins is important in order to find new sources of natural raw materials with medical and pharmaceutical applications. Protein precipitation capacity as a function of pH, competitive protein and ADN binding assays and the determination of tannins concentration are described. Radioisotope labeled protein and tannins were used in all of the determinations. (author)

  17. NO OVERDENSITY OF LYMAN-ALPHA EMITTING GALAXIES AROUND A QUASAR AT z  ∼ 5.7

    Energy Technology Data Exchange (ETDEWEB)

    Mazzucchelli, C.; Bañados, E.; Decarli, R.; Farina, E. P.; Venemans, B. P.; Walter, F. [Max Planck Institute für Astronomy, Königstuhl 17, D-69117 Heidelberg (Germany); Overzier, R. [Observatório Nacional, Rua José Cristino, 77. CEP 20921-400, São Cristóvão, Rio de Janeiro-RJ (Brazil)

    2017-01-01

    Bright quasars, observed when the universe was less than one billion years old ( z  > 5.5), are known to host massive black holes (∼10{sup 9} M {sub ⊙}) and are thought to reside in the center of massive dark matter overdensities. In this picture, overdensities of galaxies are expected around high-redshift quasars. However, observations based on the detection of Lyman-break galaxies (LBGs) around these quasars do not offer a clear picture: this may be due to the uncertain redshift constraints of LBGs, which are solely selected through broadband filters. To circumvent such uncertainties, we here perform a search for Lyman-alpha emitting galaxies (LAEs) in the field of the quasar PSO J215.1512–16.0417 at z  ∼ 5.73, through narrowband deep imaging with FORS2 at the Very Large Telescope. We study an area of 37 arcmin{sup 2}, i.e., ∼206 comoving Mpc{sup 2} at the redshift of the quasar. We find no evidence of an overdensity of LAEs in the quasar field with respect to blank-field studies. Possible explanations for these findings may be that our survey volume is too small, or that the strong ionizing radiation from the quasar hinders galaxy formation in its immediate proximity. Another possibility is that these quasars are not situated in the dense environments predicted by some simulations.

  18. Production of radioisotopes by cyclotron at the Instituto de Engenharia Nuclear - an evaluation of the present stage of development

    International Nuclear Information System (INIS)

    Almeida, G.L. de; Britto, J.L.Q. de; Osso Junior, J.A.; Bastos, M.A.V.; Braghirolli, A.M.S.; Chamma, D.F.S.; Silva, A.G. da

    1984-01-01

    Since 1974 a variable energy isochronous cyclotron (CV-28) is operating at Instituto de Engenharia Nuclear in Rio de Janeiro, with the main purpose of producing radioisotopes for medical diagnosis. To accomplish this, besides the conventional chemical laboratories and related facilities, hot chemistry laboratories with their specific equipment and remote handling devices had to be designed and constructed at this Institute, and are still being developed, due to a lack of engineering companies working in this field. Other equipment, intrinsically related to cyclotrons like high power density target holders, collimators etc. were also conceived and constructed. Among the produced raioisotopes, high purity gallium-67 and indium-111 have been periodically sent to hospitals and some efforts are still being made in order to improve and simplify the chemical processing as well as the operational procedures. Some work has also been devoted to the development and improvement of methods for the production of iodine-123, bromine-77 and thallium-201. (Author) [pt

  19. Twenty years of publishing and editorial activities of the Institute for Research, Production and Application of Radioisotopes (UVVVR)

    International Nuclear Information System (INIS)

    Peknice, J.R.

    1979-01-01

    The publishing and editorial activities are reviewed of the Institute for the Research, Production and Application of Radioisotopes during the past twenty years. In 1959 it was decided to start the publishing of the bulletin RADIOISOTOPY which, at first, appeared occasionaly and later as a periodical (bimonthly). The diversity of contributions led to the creation of two further specialized non-series periodical SBORNIK PRACI Z OBLASTI JADERNE VEDY A TECHNIKY and UVVVR REPORTS (the latter in English). All these titles are sponsored by the Czechoslovak Atomic Energy Commission. The paper contains further a number of tables illustrating the publishing activities, number of authors and subscribers, exchange with foreign institutions, detailed instructions for authors, a number of valuable conversion tables and references to a choice of literature useful for editorial and publishing work. (author)

  20. Masters Thesis- Criticality Alarm System Design Guide with Accompanying Alarm System Development for the Radioisotope Production Laboratory in Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Greenfield, Bryce A. [Univ. of New Mexico, Albuquerque, NM (United States)

    2009-12-01

    A detailed instructional manual was created to guide criticality safety engineers through the process of designing a criticality alarm system (CAS) for Department of Energy (DOE) hazard class 1 and 2 facilities. Regulatory and technical requirements were both addressed. A list of design tasks and technical subtasks are thoroughly analyzed to provide concise direction for how to complete the analysis. An example of the application of the design methodology, the Criticality Alarm System developed for the Radioisotope Production Laboratory (RPL) of Richland, Washington is also included. The analysis for RPL utilizes the Monte Carlo code MCNP5 for establishing detector coverage in the facility. Significant improvements to the existing CAS were made that increase the reliability, transparency, and coverage of the system.

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

    International Nuclear Information System (INIS)

    2002-10-01

    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

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

    International Nuclear Information System (INIS)

    2000-10-01

    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.)

  3. Radiopharmaceuticals in positron emission tomography: Radioisotope productions and radiolabelling procedures at the Austin and Repatriation Medical Centre

    Energy Technology Data Exchange (ETDEWEB)

    Tochon-Danguy, H.J.; Sachinidis, J.I.; Chan, J.G.; Cook, M. [Austin and Repatriation Medical Centre, Melbourne, VIC (Australia). Centre for Positron Emission Tomography

    1997-10-01

    Positron Emission Tomography (PET) is a technique that utilizes positron-emitting radiopharmaceuticals to map the physiology, biochemistry and pharmacology of the human body. Positron-emitting radioisotopes produced in a medical cyclotron are incorporated into compounds that are biologically active in the body. A scanner measures radioactivity emitted from a patient`s body and provides cross-sectional images of the distribution of these radiolabelled compounds in the body. It is the purpose of this paper to review the variety of PET radiopharmaceuticals currently produced at the Austin and Repatriation Medical Centre in Melbourne. Radioisotope production, radiolabelling of molecules and quality control of radiopharmaceuticals will be discussed. A few examples of their clinical applications will be shown as well. During the last five years we achieved a reliable routine production of various radiopharmaceuticals labelled with the four most important positron-emitters: oxygen-15 (t,{sub 1/2}=2min), nitrogen-13 (t{sub 1/2}= 10 min), carbon-11 (t{sub 1/2}=20 min) and fluorine-18 (t{sub 1/2}= 110 min). These radiopharmaceuticals include [{sup 15}O]oxygen, [{sup 15}O]carbon monoxide, [{sup 15}O]carbon dioxide, [{sup 15}O]water, [{sup 13}N]ammonia, [{sup 11}C]flumazenil, [{sup 11}C]SCH23390, [{sup 18}F]fluoromisonidazole and [{sup 18}F]fluoro-deoxy-glucose ([{sup 18}F]FDG). In addition, since the half life of [{sup 18}F] is almost two hours, regional distribution can be done, and the Austin and Repatriation Medical Centre is currently supplying [{sup 18}F]FDG in routine to other hospitals. Future new radiopharmaceuticals development include a [{sup 18}F]thymidine analog to measure cell proliferation and a [{sup 11}C]pyrroloisoquinoline to visualize serotonergic neuron abnormalities. (authors) 23 refs., 2 tabs.

  4. Radiopharmaceuticals in positron emission tomography: Radioisotope productions and radiolabelling procedures at the Austin and Repatriation Medical Centre

    International Nuclear Information System (INIS)

    Tochon-Danguy, H.J.; Sachinidis, J.I.; Chan, J.G.; Cook, M.

    1997-01-01

    Positron Emission Tomography (PET) is a technique that utilizes positron-emitting radiopharmaceuticals to map the physiology, biochemistry and pharmacology of the human body. Positron-emitting radioisotopes produced in a medical cyclotron are incorporated into compounds that are biologically active in the body. A scanner measures radioactivity emitted from a patient's body and provides cross-sectional images of the distribution of these radiolabelled compounds in the body. It is the purpose of this paper to review the variety of PET radiopharmaceuticals currently produced at the Austin and Repatriation Medical Centre in Melbourne. Radioisotope production, radiolabelling of molecules and quality control of radiopharmaceuticals will be discussed. A few examples of their clinical applications will be shown as well. During the last five years we achieved a reliable routine production of various radiopharmaceuticals labelled with the four most important positron-emitters: oxygen-15 (t, 1/2 =2min), nitrogen-13 (t 1/2 = 10 min), carbon-11 (t 1/2 =20 min) and fluorine-18 (t 1/2 = 110 min). These radiopharmaceuticals include [ 15 O]oxygen, [ 15 O]carbon monoxide, [ 15 O]carbon dioxide, [ 15 O]water, [ 13 N]ammonia, [ 11 C]flumazenil, [ 11 C]SCH23390, [ 18 F]fluoromisonidazole and [ 18 F]fluoro-deoxy-glucose ([ 18 F]FDG). In addition, since the half life of [ 18 F] is almost two hours, regional distribution can be done, and the Austin and Repatriation Medical Centre is currently supplying [ 18 F]FDG in routine to other hospitals. Future new radiopharmaceuticals development include a [ 18 F]thymidine analog to measure cell proliferation and a [ 11 C]pyrroloisoquinoline to visualize serotonergic neuron abnormalities. (authors)

  5. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Canadian Forces (Canada)

    2014-07-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as {sup 99}Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as {sup 99}Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO{sub 2}SO{sub 4}) with 994.2 g of {sup 235}U (enrichment at 20%) providing an excess reactivity at operating temperature (40 {sup o}C) of 3.8 mk for a molality determined as 1.46 mol kg{sup -1} for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 {sup o}C. Peak temperature and power were determined as 83 {sup o}C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the

  6. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2014-01-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as 99 Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as 99 Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO 2 SO 4 ) with 994.2 g of 235 U (enrichment at 20%) providing an excess reactivity at operating temperature (40 o C) of 3.8 mk for a molality determined as 1.46 mol kg -1 for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 o C. Peak temperature and power were determined as 83 o C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the temperature and void coefficients are

  7. Radioisotopes and radiopharmaceuticals catalogue

    International Nuclear Information System (INIS)

    2002-01-01

    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)

  8. Radioisotope programme in Iran

    International Nuclear Information System (INIS)

    Owlya, A.

    1985-01-01

    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)

  9. The Supply of Medical Radioisotopes. Market impacts of converting to low-enriched uranium targets for medical isotope production

    International Nuclear Information System (INIS)

    Westmacott, Chad; Cameron, Ron

    2012-01-01

    The reliable supply of molybdenum-99 ( 99 Mo) and its decay product, technetium-99m ( 99m Tc), is a vital component of modern medical diagnostic practices. At present, most of the global production of 99 Mo is from highly enriched uranium (HEU) targets. However, all major 99 Mo-producing countries have recently agreed to convert to using low-enriched uranium (LEU) targets to advance important non-proliferation goals, a decision that will have implications for the global supply chain of 99 Mo/ 99m Tc and the long-term supply reliability of these medical isotopes. This study provides the findings and analysis from an extensive examination of the 99 Mo/ 99m Tc supply chain by the OECD/NEA High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR). It presents a comprehensive evaluation of the potential impacts of converting to the use of LEU targets for 99 Mo production on the global 99 Mo/ 99m Tc market in terms of costs and available production capacity, and the corresponding implications for long-term supply reliability. In this context, the study also briefly discusses the need for policy action by governments in their efforts to ensure a stable and secure long-term supply of 99 Mo/ 99m Tc

  10. Manual for reactor produced radioisotopes

    International Nuclear Information System (INIS)

    2003-01-01

    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

  11. 78 FR 15009 - Consideration of Withdrawal From Commercial Production and Distribution of the Radioisotope...

    Science.gov (United States)

    2013-03-08

    ... DEPARTMENT OF ENERGY Consideration of Withdrawal From Commercial Production and Distribution of... its consideration of DOE withdrawal from the commercial production and distribution of germanium-68... Statement of Policy, referenced above. In summary, DOE's evaluation will include consideration of: a...

  12. Tailoring medium energy proton beam to induce low energy nuclear reactions in ⁸⁶SrCl₂ for production of PET radioisotope ⁸⁶Y.

    Science.gov (United States)

    Medvedev, Dmitri G; Mausner, Leonard F; Pile, Philip

    2015-07-01

    This paper reports results of experiments at Brookhaven Linac Isotope Producer (BLIP) aiming to investigate effective production of positron emitting radioisotope (86)Y by the low energy (86)Sr(p,n) reaction. BLIP is a facility at Brookhaven National Laboratory designed for the proton irradiation of the targets for isotope production at high and intermediate proton energies. The proton beam is delivered by the Linear Accelerator (LINAC) whose incident energy is tunable from 200 to 66 MeV in approximately 21 MeV increments. The array was designed to ensure energy degradation from 66 MeV down to less than 20 MeV. Aluminum slabs were used to degrade the proton energy down to the required range. The production yield of (86)Y (1.2+/-0.1 mCi (44.4+/-3.7) MBq/μAh) and ratio of radioisotopic impurities was determined by assaying an aliquot of the irradiated (86)SrCl2 solution by gamma spectroscopy. The analysis of energy dependence of the (86)Y production yield and the ratios of radioisotopic impurities has been used to adjust degrader thickness. Experimental data showed substantial discrepancies in actual energy propagation compared to energy loss calculations. Copyright © 2015 Elsevier Ltd. All rights reserved.

  13. Management system in the dose assessment due to the intake of 131I in occupationally exposed workers (OEW) in a radioisotope production plant

    International Nuclear Information System (INIS)

    Koga, Roberto; Jara, Raul; Defilippi, Luis; Osores, Jose

    2015-01-01

    This article presents the evaluation and management processes due to the incorporation of 131 I in occupationally exposed workers (OEW) of a Radioisotope Production Plant by in vivo measurement of the retained activity of this radionuclide in thyroid. The procedures for the occupational control of the OWE were established, including intermediate checks and calibration of the equipment according to the NTP ISO/IEC 17025:2006 standard. (author)

  14. Semi-Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for October 1, 2001 Through March 31, 2002

    Energy Technology Data Exchange (ETDEWEB)

    J. P. Moore, JPM

    2002-05-22

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS). This report has been divided into three sections to reflect program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2002. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for new radioisotope power systems. The last section is dedicated to studies related to the production of {sup 238}Pu.

  15. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for October 1, 2002 Through September 30, 2003

    Energy Technology Data Exchange (ETDEWEB)

    King, J.F.

    2004-05-18

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS). This report has been divided into three sections to reflect program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2003. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for new radioisotope power systems. The last section is dedicated to studies related to the production of {sup 238}Pu.

  16. Production and purification of Scandium-47: A potential radioisotope for cancer theranostics.

    Science.gov (United States)

    Deilami-Nezhad, Leila; Moghaddam-Banaem, Leila; Sadeghi, Mahdi; Asgari, Mehdi

    2016-12-01

    In this study, production of 47 Sc radionuclide by irradiating the natural titanium dioxide powder (TiO 2 ) in the fast neutron flux (~3*10 13 ncm -2 s -1 ) for 4 days in Tehran Research Reactor (TRR, Iran) and separation from titanium target was investigated. The study showed the feasibility of production 47 Sc by TRR. The separation efficiency and radiochemical purity (ScCl 3 ) of radio-scandium, 47 Sc radionuclide purity were obtained 98%, 99% and 88% respectively. Copyright © 2016 Elsevier Ltd. All rights reserved.

  17. Automation drying unit molybdenum-zirconium gel radioisotope production technetium-99M for nuclear medicine

    International Nuclear Information System (INIS)

    Chakrova, Y.; Khromushin, I.; Medvedeva, Z.; Fettsov, I.

    2014-01-01

    Full text : Since 2001 the Institute of Nuclear Physics of the Republic of Kazakhstan has began production of radiopharmaceutical based on technetium-99m from irradiated reactor WWR-K of natural molybdenum, which allows to obtain a solution of technetium-99m of the required quality and high volume activity. In 2013 an automated system is started, which is unique and urgent task is to develop algorithms and software in Python, as well as the manufacture of certain elements of technological systems for automated production

  18. Hospital-based proton linear accelerator for particle therapy and radioisotope production

    Science.gov (United States)

    Lennox, Arlene J.

    1991-05-01

    Taking advantage of recent advances in linear accelerator technology, it is possible for a hospital to use a 70 MeV proton linac for fast neutron therapy, boron neutron capture therapy, proton therapy for ocular melanomas, and production of radiopharmaceuticals. The linac can also inject protons into a synchrotron for proton therapy of deep-seated tumors. With 180 μA average current, a single linac can support all these applications. This paper presents a conceptual design for a medical proton linac, switchyard, treatment rooms, and isotope production rooms. Special requirements for each application are outlined and a layout for sharing beam among the applications is suggested.

  19. Successes and problems in the development of medical radioisotope production in Russia

    Science.gov (United States)

    Zhuikov, B. L.

    2016-05-01

    There are many challenges that face radionuclide production and application for medical diagnostics and therapy in Russia. In this article, the development of novel production methods for medical radionuclides (82Sr, 82Sr/82Rb-generator, 117mSn, 225Ac, etc.) at the Institute for Nuclear Research, RAS is described, providing an example of how supporting basic nuclear facilities, backing fundamental research, granting scientists and medical specialists freedom in choosing a research area, and effective international collaboration involving developed countries combine to enable progress in the field.

  20. Development of Code for Simulation of Acceleration of Ions from Internal Source to End of Extraction System in Cyclotrons and Preliminary Design Study of 8MeV Cyclotron for Production of Radioisotopes

    CERN Document Server

    Kostromin, Sergey

    2006-01-01

    Development of Code for Simulation of Acceleration of Ions from Internal Source to End of Extraction System in Cyclotrons and Preliminary Design Study of 8MeV Cyclotron for Production of Radioisotopes

  1. 78 FR 1848 - Plutonium-238 Production for Radioisotope Power Systems for National Aeronautics and Space...

    Science.gov (United States)

    2013-01-09

    ... effective. In addition, the escalating cost estimate of proposed new construction at INL did not favor the... for Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production... other Federal agencies; and (3) conducting research and development activities for civilian use of...

  2. Dual-label radioisotope method for simultaneously measuring bacterial production and metabolism in natural waters

    International Nuclear Information System (INIS)

    Jonas, B.J.; Tuttle, J.H.; Stoner, D.L.; Ducklow, H.W.

    1988-01-01

    Bacterial production and amino acid metabolism in aquatic systems can be estimated by simultaneous incubation of water samples with both tritiated methyl-thymidine and 14 C-labeled amino acids. This dual-label method not only saves time, labor, and materials, but also allows determination of these two parameters in the same microbial subcommunity. Both organic carbon incorporation and respiration can be estimated. The method is particularly suitable for large-scale field programs and has been used successfully with eutrophic estuarine samples as well as with oligotrophic oceanic water. In the mesohaline portion of Chesapeake Bay, thymidine incorporation ranged seasonally from 2 to 635 pmol liter -1 h -1 and amino acid turnover rates ranged from 0.01 to 28.4% h -1 . Comparison of thymidine incorporation with amino acid turnover measurements made at a deep, midbay station in 1985 suggested a close coupling between bacterial production and amino acid metabolism during most of the year. However, production-specific amino acid turnover rates increased dramatically in deep bay waters during the spring phytoplankton bloom, indicating transient decoupling of bacterial production from metabolism. Ecological features such as this are readily detectable with the dual-label method

  3. Use of radiations and radioisotopes in studies of animal production. Proceedings of symposium. Programme and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-01

    Forty-seven papers discuss radionuclide tracer techniques for metabolic, nutritional, and reproductive studies on domestic animals, radiation effects on the survival of parasites, uses of radiation in the preparation of vaccines against pathogenic bacteria and parasites, radiation processing of food for animals, and the radiopreservation of fish, meat, and dairy products. (CH)

  4. Five Years of Cyclotron Radioisotope Production Experiences at the First PET-CT in Venezuela

    International Nuclear Information System (INIS)

    Colmenter, L.; Coelho, D.; Esteves, L. M.; Ruiz, N.; Morales, L.; Lugo, I.; Sajo-Bohus, L.; Liendo, J. A.; Greaves, E. D.; Barros, H.; Castillo, J.

    2007-01-01

    Five years operation of a compact cyclotron installed at PET-CT facility in Caracas, Venezuela is given. Production rate of 18 F labeled FDG, operation and radiation monitoring experience are included. We conclude that 18 FDG CT-PET is the most effective technique for patient diagnosis

  5. Dosimetry of bone metastases in targeted radionuclide therapy with alpha-emitting {sup 223}Ra-dichloride

    Energy Technology Data Exchange (ETDEWEB)

    Pacilio, Massimiliano [Azienda Ospealiera San Camillo Forlianini, Rome (Italy). Dept. of Medical Physics; Ventroni, Guido; Mango, Lucio [Azienda Ospealiera San Camillo Forlianini, Rome (Italy). Dept. of Nuclear Medicin; De Vincentis, Giuseppe; Di Castro, Elisabetta; Frantellizzi, Viviana; Follacchio, Giulia Anna; Garkavaya, Tatiana [Rome Univ. (Italy). Dept. of Radiological, Oncological and Anatomo Pathological Sciences; Cassano, Bartolomeo; Lorenzon, Leda [Rome Univ. (Italy). Postgraduate School of Medical Physics; Pellegrini, Rosanna; Pani, Roberto [Rome Univ. (Italy). Dept. of Molecular Medicine; Ialongo, Pasquale [Azienda Ospealiera San Camillo Forlianini, Rome (Italy). Dept. of Radiology

    2016-01-15

    Ra-dichloride is an alpha-emitting radiopharmaceutical used in the treatment of bone metastases from castration-resistant prostate cancer. Image-based dosimetric studies remain challenging because the emitted photons are few. The aim of this study was to implement a methodology for in-vivo quantitative planar imaging, and to assess the absorbed dose to lesions using the MIRD approach. The study included nine Caucasian patients with 24 lesions (6 humeral head lesions, 4 iliac wing lesions, 2 scapular lesions, 5 trochanter lesions, 3 vertebral lesions, 3 glenoid lesions, 1 coxofemoral lesion). The treatment consisted of six injections (one every 4 weeks) of 50 kBq per kg body weight. Gamma-camera calibrations for {sup 223}Ra included measurements of sensitivity and transmission curves. Patients were statically imaged for 30 min, using an MEGP collimator, double-peak acquisition, and filtering to improve the image quality. Lesions were delineated on {sup 99m}Tc-MDP whole-body images, and the ROIs superimposed on the {sup 223}Ra images after image coregistration. The activity was quantified with background, attenuation, and scatter correction. Absorbed doses were assessed deriving the S values from the S factors for soft-tissue spheres of OLINDA/EXM, evaluating the lesion volumes by delineation on the CT images. In 12 lesions with a wash-in phase the biokinetics were assumed to be biexponential, and to be monoexponential in the remainder. The optimal timing for serial acquisitions was between 1 and 5 h, between 18 and 24 h, between 48 and 60 h, and between 7 and 15 days. The error in cumulated activity neglecting the wash-in phase was between 2 % and 12 %. The mean effective half-life (T{sub 1/2eff}) of {sup 223}Ra was 8.2 days (range 5.5-11.4 days). The absorbed dose (D) after the first injection was 0.7 Gy (range 0.2-1.9 Gy). Considering the relative biological effectiveness (RBE) of alpha particles (RBE = 5), D{sub RBE} = 899 mGy/MBq (range 340-2,450 mGy/MBq). The

  6. Radioisotope trithiol complexes

    Science.gov (United States)

    Jurisson, Silvia S.; Cutler, Cathy S.; Degraffenreid, Anthony J.

    2016-08-30

    The present invention is directed to a series of stable radioisotope trithiol complexes that provide a simplified route for the direct complexation of radioisotopes present in low concentrations. In certain embodiments, the complex contains a linking domain configured to conjugate the radioisotope trithiol complex to a targeting vector. The invention is also directed to a novel method of linking the radioisotope to a trithiol compound to form the radioisotope trithiol complex. The inventive radioisotope trithiol complexes may be utilized for a variety of applications, including diagnostics and/or treatment in nuclear medicine.

  7. Beam Energy Deposition from PS Booster and Production Rates of Selected Medical Radioisotopes in the CERN-MEDICIS Target

    OpenAIRE

    Gonsalves, Basil; Barlow, Roger; Dos Santos Augusto, Ricardo Manuel; Lee, Sangcheol; Stora, Thierry

    2016-01-01

    CERN-MEDICIS uses the scattered (ca. 90%) 1.4 GeV, 2 uA protons delivered by the PS Booster to the ISOLDE target, which would normally end up in the beam dump. After irradiation, the MEDICIS target is transported back to an offline isotope mass separator, where the produced isotopes are mass separated, and are then collected. The required medical radioisotopes are later chemically separated in the class A laboratory. The radioisotopes are transported to partner hospitals for processing and pr...

  8. Development of an accelerator driven neutron activator for medical radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

    Abbas, Kamel [Via Fermi 2749, I-21020 Ispra (Italy)], E-mail: kamel.abbas@jrc.it; Buono, Stefano; Burgio, Nunzio; Cotogno, Giulio; Gibson, Neil; Maciocco, Luca; Mercurio, Giovanni; Santagata, Alfonso; Simonelli, Federica; Tagziria, Hamid [Via Fermi 2749, I-21020 Ispra (Italy)

    2009-04-01

    A compact, accelerator driven, neutron activator based on a modified version of the Adiabatic Resonance Crossing (ARC) concept has been developed, with the aim of efficiently utilising ion-beam generated neutrons for the production of radioactive nanoparticles for brachytherapy. Extensive Monte Carlo simulations have been carried out to optimise the design of the activator, which is based on a hybrid approach, coupling a lead buffer and a graphite reflector. Computational Fluid Dynamic methods have been used for the thermal-hydraulic design of the neutron-generating beryllium target to ensure efficient water cooling under high proton beam currents. The facility has been tested under various experimental configurations, and the activation yields of different materials, measured with {gamma}-spectrometry techniques, have been compared with theoretical predictions. In this paper the main elements of the activator are described, and calculated and measured results for pure Au, Mo, Ho, and Re foils as well as for Re and Ho nanoparticle samples are presented. A satisfactory agreement between experiment and theory was found, confirming that the improved ARC activator developed in this work is suitable for isotope production for certain applications such as brachytherapy.

  9. Lutetium-177 - Broad Production Capabilities are Expected to Stimulate Clinical Applications of this Important Therapeutic Radioisotope

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.

    2009-01-01

    Lutetium-177 (Lu-177) is of broad interest for therapeutic applications where the deposition of localized radiation can benefit from the limited soft tissue penetration of the 0.497 MeV beta particle (max. = 2.76 mm). Examples of Lu-177 therapeutic strategies include treatment of small SS2/SS5-expressing tumors with targeted peptides and radiosynovectomy. Emission of a 208 keV gamma photon (11 %) allows imaging for evaluation of localization and biokinetics, and for targeting applications, correlation of uptake with therapeutic response. A broad spectrum of research reactors with even modest thermal neutron flux (e.g. > 1 x 10 14 ) can produce carrier-added Lu-177 with sufficient specific activity (SA) > 10 Ci/mg Lu by the 'direct' approach by irradiation of Lu-176. For low SA applications, thermal flux of > 10 13 in low-medium flux reactors provides sufficient SA (> 0.5 mCi Lu-177/mg) for preparation of Lu-EDTMP for synovectomy. Although relative Lu-177m/Lu-177 activity levels from 'direct' production can be very low (> 10 -5 ), the Lu-177m impurity levels can present an issue with radioactive waste storage requirements at some institutions. The alternative 'indirect' approach using decay of reactor produced ytterbium-177 available from by neutron irradiation of enriched Yb-176 targets provides no-carrier-added (nca) Lu-177 (theoretical SA = 109 Ci/mg Lu). Purification of the microscopic levels of nca Lu-177 from macroscopic Yb levels at the high multi Curie production level is a more challenging approach, since production yields are relatively low even at high thermal flux (e.g. 2 x 10 15 neutrons/cm 2 /sec). In addition, high mass Lu/Yb separation is especially time consuming, can generate significant waste, and the relatively expensive Yb-176 target material (> 97%, ∼ $ 20/mg) must be recovered, re-purified and used for subsequent target preparation. However, a number of effective methods for the Lu/Yb separation and Yb recovery have been reported, and even

  10. Radioisotope techniques in oil wells

    International Nuclear Information System (INIS)

    Jain, Prabuddha

    1998-01-01

    Radioisotope techniques are quite useful in oil exploration and exploitation. Nuclear logging offers a way of gathering information on porosity, permeability, fluid saturations, hydrocarbon types and lithology. Some of the interesting applications in well drilling are determining depth of filtrate invasion, detection of lost circulation, drill-bit erosion control; primary cement measurements and well completions such as permanent tubular markers, perforation position marking, detection of channeling behind casing and gravel pack operations. Radioisotopes have been successfully used in optimizing production processes such as production profiling injection profiling, corrosion measurements and well to well tracer tests. (author)

  11. Specific features of the desion of a cyclotron for radioisotope production

    International Nuclear Information System (INIS)

    Akulova, N.V.; Bogdanov, P.V.; Ivanov, V.V.

    1979-01-01

    Results of development of an isochronous cyclotron for commercial production of Co 57 and Ga 67 isotopes are described. The accelerator is intended for proton acceleration up to 25 MeV at 1000-1500 mA intensity of inner beam and 200 mA intensity of external beam. An axial ion source with a hot cathode will be used in the cyclotron. Outer diameter of armour type electromagnet is 3130 mm, mass - 75 t, diameter of poles-150 cm and mean induction of magnetic field in a working gap amounts to 12 kgs. Accelerating chamber vessel is made of steel in the form of thick-wall hollow cylinder having 3130 mm outer diameter, 330 mm thickness and 380 mm height. Resonance system represents a quarter-wave line operating on 16.6 MHZ-frequency. Vacuum system is designed to produce and maintain residual pressure of 6.7x10 -4 Pa and 2.7x10 -3 Pa in the accelerating chamber which can be provided with two NDM-2 ion-getter pumps with an arc evaporator. The suggested constructive solution for electromagnet, accelerating chamber of the cyclotron and pumping system permitted to arrange the accelerator on the whole and to considerably decrease the level of ionizing radiations inside the chamber [ru

  12. Radioisotope research, production, and processing at the University of Missouri Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ehrhardt, G.J.; Ketring, A.R.; Ja, Wei; Ma, D.; Zinn, K.; Lanigan, J.

    1995-12-31

    The University of Missouri Research Reactor (MURR) is a 10 MW, light-water-cooled and moderated research reactor which first achieved criticality in 1996 and is currently the highest powered university-owned research reactor in the U.S. For many years a major supplier of reactor-produced isotopes for research and commercial purposes, in the last 15 years MURR has concentrated on development of reactor-produced beta-particle emitters for experimental use in nuclear medicine therapy of cancer and rheumatoid arthritis. MURR has played a major role in the development of bone cancer pain palliation with the agents {sup 153}Sm EDTMP and {sup 186}Re/{sup 188}Re HEDP, as well as in the use of {sup 186}Re, {sup 177}Lu, {sup 166}Ho, and {sup 105}Rh for radioimmunotherapy and receptor-agent-guided radiotherapy. MURR is also responsible for the development of therapeutic, {sup 90}Y-labeled glass microspheres for the treatment of liver tumors, a product ({sup 90}Y Therasphere{trademark}) which is currently an approved drug in Canada. MURR has also pioneered the development of {sup 188}W/{sup 188}Re and {sup 99}Mo/{sup 99m}Tc gel generators, which make the use of low specific activity {sup 188}W and {sup 99}Mo practical for such isotope generators.

  13. The production of radioisotopes for medical applications by the adiabatic resonance crossing (ARC) technique

    CERN Document Server

    Froment, P; Delbar, T; Ryckewaert, G; Tilquin, I; Vervier, J

    2002-01-01

    The Transmutation by Adiabatic Resonance Crossing (TARC) technique has been proposed by Rubbia (Resonance enhanced neutron captures for element activation and waste transmutation, CERN-LHC/97-0040EET, 1997; TARC collaboration, Neutron-driven nuclear transmutation by adiabatic resonance crossing, CERN-SL-99-036EET, 1999; Abanades et al., Nucl. Instr. and Meth. A 487 (2002) 577) for element activation and waste transmutation. We investigate the possibility to use this technique for the industrial production of **9**9Mo and **1**2**5Xe by resonance neutron capture in **9**8Mo and **1**2**4Xe, respectively. Their daughters, i.e. **9**9**mTc and **1**2**5I, are widely used in medical applications. The high neutron flux needed is produced by bombarding a thick Be target with 65 or 75 MeV proton beam (few microamperes). This target is placed at the centre of a large cubic lead assembly (1.6 m side, purity: 99.999%). The neutrons are progressively slowed down by elastic scattering on lead, and their energies "scan" t...

  14. Radioisotope research, production, and processing at the University of Missouri Research Reactor

    International Nuclear Information System (INIS)

    Ehrhardt, G.J.; Ketring, A.R.; Ja, Wei; Ma, D.; Zinn, K.; Lanigan, J.

    1995-01-01

    The University of Missouri Research Reactor (MURR) is a 10 MW, light-water-cooled and moderated research reactor which first achieved criticality in 1996 and is currently the highest powered university-owned research reactor in the U.S. For many years a major supplier of reactor-produced isotopes for research and commercial purposes, in the last 15 years MURR has concentrated on development of reactor-produced beta-particle emitters for experimental use in nuclear medicine therapy of cancer and rheumatoid arthritis. MURR has played a major role in the development of bone cancer pain palliation with the agents 153 Sm EDTMP and 186 Re/ 188 Re HEDP, as well as in the use of 186 Re, 177 Lu, 166 Ho, and 105 Rh for radioimmunotherapy and receptor-agent-guided radiotherapy. MURR is also responsible for the development of therapeutic, 90 Y-labeled glass microspheres for the treatment of liver tumors, a product ( 90 Y Therasphere trademark) which is currently an approved drug in Canada. MURR has also pioneered the development of 188 W/ 188 Re and 99 Mo/ 99m Tc gel generators, which make the use of low specific activity 188 W and 99 Mo practical for such isotope generators

  15. ANNUAL TECHNICAL PROGRESS REPORT OF RADIOISOTOPE POWER SYSTEMS MATERIALS PRODUCTION AND TECHNOLOGY PROGRAM TASKS FOR OCTOBER 1, 2010 THROUGH SEPTEMBER 30, 2011

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2012-05-01

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration (NASA) for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, the Oak Ridge National Laboratory (ORNL) produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. These components were also produced for the Pluto New Horizons and Mars Science Lab missions launched in January 2006 and November 2011respectively. The ORNL has been involved in developing materials and technology and producing components for the DOE for nearly four decades. This report reflects program guidance from the Office of RPS for fiscal year (FY) 2011. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new RPS. Work has also been initiated to establish fabrication capabilities for the Light Weight Radioisotope Heater Units.

  16. Production of medical radioisotopes with high specific activity in photonuclear reactions with γ-beams of high intensity and large brilliance

    Science.gov (United States)

    Habs, D.; Köster, U.

    2011-05-01

    We study the production of radioisotopes for nuclear medicine in ( γ, xn+ yp) photonuclear reactions or ( γ, γ') photoexcitation reactions with high-flux [(1013-1015) γ/s], small diameter ˜(100 μm)2 and small bandwidth (Δ E/ E≈10-3-10-4) γ beams produced by Compton back-scattering of laser light from relativistic brilliant electron beams. We compare them to (ion, xn+ yp) reactions with (ion = p,d, α) from particle accelerators like cyclotrons and (n, γ) or (n,f) reactions from nuclear reactors. For photonuclear reactions with a narrow γ-beam the energy deposition in the target can be managed by using a stack of thin target foils or wires, hence avoiding direct stopping of the Compton and pair electrons (positrons). However, for ions with a strong atomic stopping only a fraction of less than 10-2 leads to nuclear reactions resulting in a target heating, which is at least 105 times larger per produced radioactive ion and often limits the achievable activity. In photonuclear reactions the well defined initial excitation energy of the compound nucleus leads to a small number of reaction channels and enables new combinations of target isotope and final radioisotope. The narrow bandwidth γ excitation may make use of the fine structure of the Pygmy Dipole Resonance (PDR) or fluctuations in γ-width leading to increased cross sections. Within a rather short period compared to the isotopic half-life, a target area of the order of (100 μm)2 can be highly transmuted, resulting in a very high specific activity. ( γ, γ') isomer production via specially selected γ cascades allows to produce high specific activity in multiple excitations, where no back-pumping of the isomer to the ground state occurs. We discuss in detail many specific radioisotopes for diagnostics and therapy applications. Photonuclear reactions with γ-beams allow to produce certain radioisotopes, e.g. 47Sc, 44Ti, 67Cu, 103Pd, 117 m Sn, 169Er, 195 m Pt or 225Ac, with higher specific activity

  17. Simulations on Nickel target preparation and separation of Ni(II)-Cu(II) matrix for production of radioisotope 64Cu

    International Nuclear Information System (INIS)

    Sunarhadijoso Soenarjo; Wira Y Rahman; Sriyono; Triyanto

    2011-01-01

    The simulations on Nickel target preparation and separation of Ni(II)-Cu(II) matrix has been carried out as a preliminary study for production of medical radioisotope Cu-64 based on nuclear reaction of 64 Ni (p,n) 64 Cu. The nickel target preparation was performed by means of electroplating method using acidic solution of nickel chloride - boric acid mixture and basic solution of nickel sulphate - nickel chloride mixture on a silver - surfaced-target holder. The simulated solution of Ni(II) - Cu(II) matrix was considered as the solution of post-proton-irradiated nickel target containing both irradiated nickel and radioactive copper, but in the presented work the proton irradiation of nickel target was omitted, while the radioactive copper was originally obtained from neutron irradiation of CuO target. The separation of radioactive copper from the nickel target matrix was based on anion exchange column chromatography in which the radiocopper was conditioned to form anion complex CuCl 4 2- and retained on the column while the nickel was kept in the form of Ni 2+ cation and eluted off from the column. The retained radioactive copper was then eluted out the column in the condition of dilute HCl changing back the copper anion complex into Cu 2+ cation. It was found that the electroplating result from the acidic solution was more satisfied than that from the basic solution. By conditioning the matrix solution at HCl 6 M, the radioactive copper was found in the forms of Cu 2+ and CuCl 4 2- while the nickel was totally in the form of Ni 2+ . In the condition of HCl 9 M, the radioactive copper was mostly in the form of CuCl 4 2- while the nickel was found as both Ni 2+ and NiCl 4 2- . The best condition of separation was in HCl 8 M in which the radioactive copper was mostly in the form of CuCl 4 2- while the nickel was mostly in the form of Ni 2+ . The retained CuCl 4 2- was then changed back into Cu 2+ cation form and eluted out the column by using HCl 0.05 M. The

  18. Production of High Specific Activity Radioisotopes via the Szilard-Chalmers Method, Using the UC-Irvine TRIGA® Reactor

    OpenAIRE

    Safavi-Tehrani, Leila

    2016-01-01

    ABSTRACT OF THE DISSERTATIONProduction of High Specific Activity Radioisotopes via the Szilard-Chalmers Method, Using the UC-Irvine TRIGA® ReactorByLeila Safavi-TehraniDoctor of Philosophy in Chemical and Biochemical EngineeringUniversity of California, Irvine, 2016Professor Mikael Nilsson, Chair Radioactive isotopes have become an important imaging, diagnostic and therapeutic tool in the medical field. For example, the neutron rich samarium isotope of 153Sm has been proven to have desirable ...

  19. The Calculation of Self-Disposal Date by Analyzing the Radioactive Contamination of Air Filters Disused in Radioisotope Production Facility

    International Nuclear Information System (INIS)

    Kim, Sung Ho; Lee, Bu Hyung; Kwon, Soo Il

    2016-01-01

    The aim of the study is to decrease the diffusion of air contamination which occurred in radiation work places handle radioisotope under the permissible level. Accordingly, we replaced used air filter with a new one at the appropriate time , and computed disposal dates for disposing used air filters by calculate radioactive contamination. Air filter contaminated by radioactivity is possible to be self-disposed on condition that all detected nuclides is below permissible level according to Nuclear Safety and Security Commission (NSSC) notification No. 2014-003. Radioisotope, produced by 30, 50 MeV cyclotron and carried from other institutions, is used to treat patients, diagnose diseases, and research technology in Korea Institute of Radiological and Medical Sciences (KIRAMS). With unsealed sources generate radioactive contamination in air, it is important to use fume hood or hot cell. The accurate date needs to be calculated by the equation for calculation of self disposal date. If disposal date is in 1000 days, disposal for external institution is required. With increasing the number of medical institute which was related to use the radioisotopes, the importance of radioactive safety management was increased. As disposing radioactive waste, in particular, is the procedure of inspecting for releasing radioactive waste to outside, appropriate action and continuous research are required at a radioactive safety management.

  20. Synthesis and granulation of a titanosilicate with adsorption capacity for Cs to be used for treating de ILLW of the Ezeiza Radioisotope Production Plant

    International Nuclear Information System (INIS)

    Curi, Rodrigo; Bianchi, Hugo L; Luca, Vittorio

    2012-01-01

    The sitinakite structured titanosilicate is widely used for treating ILLW thanks to its capacity for adsorbing both Cs-137 and Sr-90. Its effectiveness lies in its incredibly high selectivity for such radioisotopes, which makes it useful in complex isotope solutions and even in strong acid and alkaline conditions. In Argentina, an off-the-shelve titanosilicate was used in Ezeiza's radioisotope production plant. Because of commercial restrictions, it is no longer available so an inhouse production is being developed. The aim of this project consists of the following: 1. Synthesis of titanosilicate and structural characterization 2. Adsorption kinetics of Cs + 3. Upscale of the synthesis process 4. Assessment of the influence of synthesis temperature and time on product crystallinity 5. Measurement of adsorption capacity of commercial titanosilicates IE910, IE911 and novel RC15H 6. Separative performance column essay and breakthrough plot 7. Chemical and radiolysis resistance of the adsorbent powder binder Polyacrylonitrile (PAN) in contact with the actual waste Throughout this work we have studied the optimum synthesis conditions capable of rendering a sitinakite structured titanosilicate, assessed its Cs + adsorption kinetics, adsorption capacity, crystal phase and purity via DRX, particle size with Laser Light Scattering technique. We have also conducted column breakthrough experiments and tried the chemical and radiolysis resistance of the final product (author)

  1. Neutron activation analysis (NAA), radioisotope production via neutron activation (PNA) and fission product gas-jet (GJA)

    Energy Technology Data Exchange (ETDEWEB)

    Gaeggeler, H.W. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-11-01

    Three different non-diffractive applications of neutrons are outlined, neutron activation analysis, production of radionuclides, mostly for medical applications, and production of short-lived fission nuclides with a so-called gas-jet. It is shown that all three devices may be incorporated into one single insert at SINQ due to their different requests with respect to thermal neutron flux. Some applications of these three facilities are summarized. (author) 3 figs., 1 tab., 8 refs.

  2. Application of radioisotopes in pharmaceutical research

    International Nuclear Information System (INIS)

    Khujaev, S.

    2004-01-01

    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 69m Zn; FERAMED, labeled by radioisotope 59 Fe; COBAVIT, labeled by radioisotope 57 Co; VUC, labeled by radioisotope 57 Co

  3. The radioisotopes and radiations program

    International Nuclear Information System (INIS)

    1982-01-01

    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.) [es

  4. Studies on application of radiation and radioisotopes

    International Nuclear Information System (INIS)

    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

    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)

  5. First research co-ordination meeting on development of reference charged particle cross section data base for medical radioisotope production. Summary report

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1996-03-01

    The present report contains the summary of the First Research Co-ordination Meeting on ''Development of Reference Charged Particle Cross Section Data Base for Medical Radioisotope Production'', held at the IAEA Headquarters, Vienna, from 15 to 17 November 1995. The project focuses on monitor reactions and production reactions for gamma emitters and positron emitters induced with light charged particles of incident energies up to about 100 MeV. Summarized are technical discussions and the resulting work plan of the Coordinated Research Programme, including actions and deadlines. Attached are an information sheet on the project, the agenda and a list of participants of the meeting. Also attached is brief information on the adjacent Consultant's Meeting on ''Automated Synthesis Systems for the Cyclotron Production of 18 F and 123 I and their Labeled Radiopharmaceuticals''. (author)

  6. Agricultural application of radioisotopes

    International Nuclear Information System (INIS)

    Agrawal, H.M.

    2001-01-01

    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)

  7. Safe use of radioisotopes.

    Science.gov (United States)

    Meisenhelder, Jill; Bursik, Steve

    2007-07-01

    The pursuit of scientific knowledge has been considerably advanced by the use of biochemical molecules that incorporate radioisotopes at specific sites. The fate of these labeled molecules, and/or the radiolabeled products that result from biochemical reactions in which the parent molecule was involved, can be traced using a variety of instruments that detect radioactivity. This appendix begins with a discussion of the principles of radioactivity in order to provide the reader/user with knowledge on which to base a common sense approach to the safe use of isotopes. The characteristics of isotopes most commonly used in a molecular biology laboratory are then detailed, as well as the safety precautions and monitoring methods peculiar to each one. Detection and imaging methods used in experimental analysis are reviewed. Finally, an outline of an orderly response to a spill of radioactive material is presented. (c) 2007 by John Wiley & Sons, Inc.

  8. Packaging and transport of radioisotopes

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1976-01-01

    The importance of radioisotope traffic is emphasized. More than a million packages are being transported each year, mostly for medical uses. The involvement of public transport services and the incidental dose to the public (which is very small) are appreciably greater than for movements connected with the nuclear fuel cycle. Modern isotope packages are described, and an outline given of the problems of a large radioisotope manufacturer who has to package many different types of product. Difficulties caused by recent uncoordinated restrictions on the use of passenger aircraft are mentioned. Some specific problems relating to radioisotope packaging are discussed. These include the crush resistance of Type A packages, the closure of steel drums, the design of secure closures for large containers, the Type A packaging of liquids, leak tightness criteria of Type B packages, and the use of 'unit load' overpacks to consign a group of individually approved packages together as a single shipment. Reference is made to recent studies of the impact of radioisotope shipments on the environment. Cost/benefit analysis is important in this field - an important public debate is only just beginning. (author)

  9. Annual Technical Progress Report of Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2007 Through September 30,2008

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2009-04-01

    The Office of Radioisotope Power Systems (RPS) of the Department of Energy (DOE) provides RPS for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration (NASA) for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of RPS for fiscal year (FY) 2008. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new RPS.

  10. Annual Technical Progress Report of the Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2008 through September 30, 2009

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2010-05-01

    The Office of Space and Defense Power Systems of the U. S. Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators (RTG) were supplied by the DOE to the National Aeronautics and Space Administration (NASA) for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, the Oak Ridge National Laboratory (ORNL) produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. ORNL has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2009. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new RPS.

  11. Study of the excitation function for the deuteron induced reaction on 64Ni(d,2n) for the production of the medical radioisotope 64Cu.

    Science.gov (United States)

    Daraban, L; Rebeles, R Adam; Hermanne, A

    2009-04-01

    The production of (64)Cu, a radioisotope of considerable interest for the application in nuclear medicine for PET imaging and radioimmunotherapy, was investigated by deuteron bombardment of enriched (64)Ni target up to E(d)=20.5 MeV. The experimental excitation function for the reaction (64)Ni(d,2n)(64)Cu was measured using the stacked foil irradiation technique followed by HPGe gamma-ray analysis at 1346 keV and is compared with earlier literature values. Cross-section data for the (64)Ni(d,p)(65)Ni reaction are determined for the first time. Thick target yields are derived and compared with results of other production routes.

  12. Radioisotopes: Today's Applications.

    Science.gov (United States)

    Department of Energy, Washington, DC. Nuclear Energy Office.

    Radioisotopes are useful because of their three unique characteristics: (1) radiation emission; (2) predictable radioactive lives; and (3) the same chemical properties as the nonradioactive atoms of that element. Researchers are able to "order" a radioisotope with the right radiation, half-life, and chemical property to perform a given task with…

  13. Industrial radioisotope applications

    International Nuclear Information System (INIS)

    Smith, S.W.

    1992-01-01

    Radioisotope-based technology is playing an increasing role in investigating problems. The main benefit of the technology is that investigations can be carried out with no disruption to the operating process of the plant. Some of the radioisotope-based technology available from the Atomic Energy Corporation of South Africa is presented. 3 figs., 1 ill

  14. Cost-benefit aspects of radioisotope methods

    International Nuclear Information System (INIS)

    Jankowski, L.

    1986-01-01

    The cost-benefit relations in the complex application of radioisotpe techniques increased in the last years to up to 1/10 to 1/15. The most essential cause of this trend is the increase of the capacity of production processes, controlled and automatized by means of radioisotopes, and the solution of qualitatively new technological problems of a high economic relevance. A collection of statistical data about the expediture and benefit of different radioisotopes techniques is presented. (author)

  15. Radioisotopes for therapy: an overview

    International Nuclear Information System (INIS)

    Venkatesh, Meera

    2006-01-01

    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, 30 P, by bombardment of 27 Al 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)

  16. Radioisotope measurement system

    International Nuclear Information System (INIS)

    Villanueva Ruibal, Jose

    2007-01-01

    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) [es

  17. Radioisotope Power Systems for Outer Planet Missions

    Science.gov (United States)

    Wahlquist, E. J.

    2001-01-01

    A summary of the Department of Energy's (DOE) capabilities and ongoing program efforts to develop and provide radioisotope power systems to support space exploration missions will be presented. The Office of Nuclear Energy, Science and Technology (DOE/NE) within DOE is responsible for the development, assembly, testing, acceptance, and delivery of radioisotope power systems to the National Aeronautics and Space Administration (NASA). To that end, DOE/NE is maintaining a program and facility infrastructure at various DOE laboratories and production sites ensuring the viability of future missions that will require radioisotope power systems. This infrastructure includes facilities to manufacture key components, process and encapsulate plutonium-238, and assemble, test, and accept the systems. DOE also pursues a low level technology program committed to the continued evolution of energy conversion technologies with applicability to radioisotope power systems. In addition, DOE recently made a decision to pursue re-establishing the domestic capability to produce plutonium-238 as part of DOE's commitment to maintaining the infrastructure necessary to produce and deliver radioisotope power systems. The currently available US inventory of plutonium-238 is sufficient to provide one radioisotope power system of roughly the same power level as each of the three units used on the Cassini spacecraft. Until the domestic production is realized, plutonium-238 requirements can be met through an existing contract with Russia.

  18. Economical Radioisotope Power

    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 to...

  19. Radioisotopes in industry

    International Nuclear Information System (INIS)

    Popple, B.N.

    1977-01-01

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Richards, M.P.

    1983-08-01

    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. (MHR)

  1. 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.

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

    International Nuclear Information System (INIS)

    Richards, M.P.

    1983-08-01

    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

  3. SU-E-T-588: Optimization of Imaging Following 223Ra Administration in Targeted Alpha-Emitting Radionuclide Therapy of Bone Metastases

    Energy Technology Data Exchange (ETDEWEB)

    Benabdallah, N; Bernardini, M [Hopital Europeen George Pompidou, Paris, Ile de France (France); Desbree, A [Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-roses, Ile-de-France (France); Labriolle-Vaylet, C de [Hopital Trousseau, Paris, Ile de France (France); Franck, D [Institut de Radioprotection et de Suretu Nucleaire, Fontenay Aux Roses, Ile de France (France)

    2015-06-15

    Purpose: With a growing demand of alpha-emitting radiopharmaceuticals, especially Xofigo ({sup 223}RaCl{sub 2}) which is used in the treatment of metastatic bone disease, the optimization of dosimetry becomes necessary. Indeed, in Europe, as stated on the council directive 2013/59/euratom, exposures of target volumes for radiotherapeutic purposes shall be individually planned taking into account that doses to non-target volumes and tissues shall be as low as reasonably achievable. To that aim, the possibility of imaging {sup 223}Ra was first investigated. Methods: The experiments were conducted at the Hopital Europeen Georges Pompidou with an Infinia Hawkeye 4 gamma camera, equipped with a medium-energy collimator. Imaging parameters, such as sensibility, spatial resolution and energy spectrum, were determined using several physical phantoms with a source of 6 MBq of {sup 223}Ra. Bone metastases were modeled with a NEMA Body Phantom to investigate image degradation based on the concentration of {sup 223}Ra. Results: The acquired energy spectrum allowed to visualize several photon peaks: at 85, 154 and 270 keV. Camera sensitivity measured from the phantom study was 102.3 cps/MBq for the 85 keV ± 20 %, 89.9 cps/MBq for the 154 ± 20 % window and 65.4 cps/MBq for the 270 ± 10 % window. The spatial resolution (full-width at half-maximum) was respectively 1.7, 1.9 and 1.8 cm for the three energy windows. SPECT/CT images of NEMA Body Phantom without and with attenuation have permitted to determine the best reconstruction parameters. Conclusion: This study has demonstrated that it is possible to obtain clinically relevant information from images of {sup 223}Ra. All these results will be valuable to analyze biodistribution imaging of the radiopharmaceutical in the patient body and go further in the reconstruction of patient images in order to personalize the dosimetry.

  4. Markets for reactor-produced non-fission radioisotopes

    International Nuclear Information System (INIS)

    Bennett, R.G.

    1995-01-01

    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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    Simmons, J.L.; Gano, S.R.

    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

  7. Radioisotopic cerebral studies

    International Nuclear Information System (INIS)

    Ducassou, D.

    1982-01-01

    In addition to the increase in dependability of conventional radioisotopic studies (gamma angio encephalography, gamma encephalography), the use of a tomography unit with emitted gamma photons allows improved use of newly developed radioactive tracers, such as 123 I iodoamphetamine. Its lipid solubility permits a true parenchymatous brain image to be obtained. The importance of these new easily diffusing tracers depends on the fact that they are able to provide information concerning the physiology and physiopathology of the brain, non invasively. The availability of metabolically active molecules marked with 11 C, 15 O or 13 N has pemitted the non invasive in vivo study of detailed physiological, biochemical and pharmacological mechanisms. Future development of radioisotopic investigations in the diagnosis of neurological problems must take into consideration computed tomography currently available and Nuclear Magnetic Resonance in the near future. Data obtained from dynamic, metabolic and functional studies will increase the diagnostic application of radioisotopic examinations, especially in etiological investigations [fr

  8. 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

  9. 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...

  10. Securing a better future for all: Nuclear techniques for global development and environmental protection. NA factsheet on radioisotope production and radiation technology contributing to better health care and a cleaner environment

    International Nuclear Information System (INIS)

    2012-01-01

    Radioisotope and radiation technology finds numerous applications in a wide variety of fields, most importantly in medicine, industry, agriculture and the environment. However, in order to take full advantage of the benefits offered by this technology, it is essential to provide the necessary infrastructure as well as qualified personnel. The IAEA strives to promote worldwide availability of products and facilities in order to offer the benefits of radioisotope products and radiation technology to developing countries. In particular, the IAEA helps Member States to achieve self-sufficiency in the production of radioisotopes and radiopharmaceuticals, strengthen quality assurance practices and regulatory compliance as well as facilitate human resources development. The multipronged need based approach includes providing advice, assistance and capacity building support for: Development, production and quality assurance of reactor and accelerator based medical isotopes and radiopharmaceuticals for both the diagnosis and treatment of diseases, especially cancer; Establishment of irradiation facilities and utilization of gamma radiation, electron beam and X ray technology for varied applications, including tackling pollutants, wastewater treatment, sterilization of medical products, disinfestation of food grains, and synthesis and characterization of advanced materials; Application of radiation and isotopes in industrial process management.

  11. Actual and future situations of the use of radioisotopes

    International Nuclear Information System (INIS)

    Paredes G, L.C.

    2005-01-01

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Burlison, J.S. (comp.)

    1982-09-01

    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.

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    1982-09-01

    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

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    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

  15. Radioisotope applications in nephrology

    International Nuclear Information System (INIS)

    Rocha, A.F.G. da

    1976-01-01

    A short review of renal physiology and arterial vessels of the kidney is done, and the concept of renal filtration fraction is discussed. A table shows the main radioisotopes used in nephrological studies. The investigation methods for renal study involving the use of radioisotopes are treated, such as: isotopic nephrogram, with characteristic graphs for some renal diseases; renal blood flow and glomerular filtration, with a curve of radioactive decay for the blood, after orto-hippurate I.V. injection, a table describing the biological compartiments of hippuran and a curve for the calculus of the glomerular filtration; renal scintigraphy, with renal scintiscanning and nephrogram using a scintillation chamber [pt

  16. Radioisotope Power Supply, Phase I

    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...

  17. Determination of the optimal conditions for simultaneous production of 73SE and 75SE radioisotopes in a 30 MeV cyclotron

    International Nuclear Information System (INIS)

    Pejman Rowshanfazad; Amirreza Jalilian; Mahsheed Sabet

    2004-01-01

    Purpose: 73 Se and 75 Se radioisotopes are widely used in medicine, industry and agriculture. 75 Se is used in high activity brachytherapy (1), assessment of pancreatic exocrine function (2, 3), study of bile acids and evaluation of illeal function (4, 5, 6), industrial radiography (7, 8) and as a tracer in the assessment of chemical, biochemical, biophysical processes, metabolic research and agricultural studies. 73 Se is used in pancreas scanning (9), hyperthyroidism diagnosis(10), adrenal scanning (11), tumor detection (12, 13, 14), detection of brain dopamine receptors (15), parathyroid tumor detection (10) and detection of brain blood flow (16). These radioisotopes were selected to be produced in the country according to their wide range of applications. The idea of simultaneous production of 73 Se and 75 Se arouse after the completion of primary studies. Important physical characteristics of these radioisotopes are shown in table l. Methods: 1 Selection of the Best Reaction. Various nuclear reactions which may be used for the production of 73 Se and 75 Se are shown in table 2 (17, 18, 19). Among the above reactions, those which use α and 3 He as the projectile particles were discarded since high energy and high intensity beams of α and 3 He are not available in the country at present. Those reactions which used 74 Se and 76 Se as the target material could not be used, since these isotopes have low isotopic values (0.87% and 9.02% respectively), and their chemical separation processes are difficult, expensive and time-taking, due to the equal chemical properties of the product and the target material (20). Thus 75 As(p, n) 75 Se seemed to be the most appropriate reaction for the production of 75 Se. The 75 As(d, 4n) 73 Se reaction is not as suitable as 75 As(p, 3n) 73 Se, because of the lower radionuclidic purity of the product (18). Thus the best reaction for the production of 73 Se was determined to be 75 As(p, 3n) 73 Se. There was no need for an isotopic

  18. Magnetic iron oxide and manganese-doped iron oxide nanoparticles for the collection of alpha-emitting radionuclides from aqueous solutions

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, Matthew J.; Carter, Jennifer C.; Warner, Cynthia L.; Warner, Marvin G.; Addleman, Raymond S.

    2016-10-31

    Magnetic nanoparticles are well known to possess chemically active surfaces and high surface areas that can be employed to extract a range of ions from aqueous solutions. Additionally, their paramagnetic property provides a convenient means for bulk collection of the material from solution after the targeted ions have been adsorbed. Herein, two nanoscale amphoteric metal oxides, each possessing useful magnetic attributes, were evaluated for their ability to collect both naturally occurring radioactive isotopes (polonium (Po), radium (Ra), and uranium (U)) as well as the transuranic element americium (Am) from a suite of naturally occurring aqueous matrices. The nanomaterials include commercially available paramagnetic magnetite (Fe3O4) and magnetite that was modified to incorporate manganese (Mn) into the crystal structure. The chemical stability of these nanomaterials was evaluated in Hanford Site, WA ground water between the natural pH (~8) and pH 1 (acidified with HCl). Whereas the magnetite was observed to have good stability over the pH range, the Mn-doped material was observed to leach Mn at low pH. The materials were evaluated in parallel to characterize their uptake performance of the aforementioned alpha-emitting radionuclide spikes from Hanford Site ground water across a range of pH (from ~8 down to 2). In addition, radiotracer uptake experiments were performed on Columbia River water, seawater, and human urine at their natural pH and at pH 2. Despite the observed leaching of Mn from the Mn-doped nanomaterial in the lower pH range, it exhibited generally superior analyte extraction performance compared to the magnetite, and analyte uptake was observed across a broader pH range. The uptake behavior of the various radiotracers on these two materials at different pH levels can generally be explained by the amphoteric nature of the nanoparticle surfaces. Finally, the rate of sorption of the radiotracers on the two materials in unacidified groundwater was

  19. Radio-isotope generator

    International Nuclear Information System (INIS)

    Benjamins, H.M.

    1983-01-01

    A device is claimed for interrupting an elution process in a radioisotope generator before an elution vial is entirely filled. The generator is simultaneously exposed to sterile air both in the direction of the generator column and of the elution vial

  20. 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.

  1. Development and selection of fungal and bacterial mutants using ionizing radiation and radioisotopes for improved enzyme production (cellulase and coagulase)

    International Nuclear Information System (INIS)

    Markov, K.I.

    1975-01-01

    Ultraviolet and gamma radiations, chemical mutagens, and combinations of chemical and physical mutagens were used in order to obtain mutants of Bacillus mesentericus and Trichoderma viridae with a higher production of coagulase and cellulase, respectively. It was possible to isolate mutant strains, with enzyme activity increased by a factor of 2 and 3

  2. Productivity of a nuclear chemical reactor with gamma radioisotopic sources; Rendimiento de un reactor quimico-nuclear con fuentes radioisotopicas gamma

    Energy Technology Data Exchange (ETDEWEB)

    Anguis T, C

    1975-07-01

    According to an established mathematical model of successive Compton interaction processes the made calculations for major distances are extended checking the acceptability of the spheric geometry model for the experimental data for radioisotopic sources of Co-60 and Cs-137. Parameters such as the increasing factor and the absorbed dose served as comparative base. calculations for the case of a punctual source succession inside a determined volume cylinder are made to obtain the total dose, the deposited energy by each photons energetic group and the total absorbed energy inside the reactor. Varying adequately the height/radius relation for different cylinders, the distinct energy depositions are compared in each one of them once a time standardized toward a standard value of energy emitted by the reactor volume. A relation between the quantity of deposited energy in each point of the reactor and the conversion values of chemical species is established. They are induced by electromagnetic radiation and that are reported as ''G'' in the scientific literature (number of molecules formed or disappeared by each 100 e.v. of energy). Once obtained the molecular performance inside the reactor for each type of geometry, it is optimized the height/radius relation according to the maximum production of molecules by unity of time. It is completed a bibliographical review of ''G'' values reported by different types of aqueous solutions with the purpose to determine the maximum performance of molecular hydrogen as a function of pH of the solution and of the used type of solute among other factors. Calculations for the ethyl bromide production as an example of one of the industrial processes which actually work using the gamma radiation as reactions inductor are realized. (Author)

  3. Survey of industrial radioisotope savings

    International Nuclear Information System (INIS)

    1965-01-01

    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

  4. Industrial radioisotope economics. Findings of the study group

    International Nuclear Information System (INIS)

    1965-01-01

    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

  5. 38 years of collaboration and friendship between Germany (east) and Cuba in the field of radioisotope production

    International Nuclear Information System (INIS)

    Novotny, Dieter; Wagner, Gerhard; Thieme, Stefan; Novotny, Holger

    2016-01-01

    Nowadays the Centro de Isotopos (CENTIS) is the most complex radioactive facility in Cuba. Today its 20th anniversary is celebrated and one can look back on a very special collaboration which was also contributing to this story of success. The relationship between Cuba and Germany was present from the former times with much scientific exchange and friendship, including the older and successive the younger generations as well. Within the latest projects an electrochemical 90 Sr/ 90 Y generator was installed at CENTIS and a production facility for 99 Mo/ 99 mTc generators is now under construction. (author)

  6. NTP Radioisotopes SOC Ltd

    International Nuclear Information System (INIS)

    Letule, T.

    2017-01-01

    NTP Radioisotopes SOC Ltd, a wholly owned subsidiary of the South African Nuclear Energy Corporation (NECSA). Supplies around 20% of the world's medical radioisotopes used. NTP is a pioneer in the introduction and growth of nuclear medicine as in South Africa. Nuclear medicine is the medical specialty that involves the use of radioactive isotopes in the diagnosis and treatment of diseases. Nuclear medicine contributes to enhancing the lives of the society. There is a compelling need for nuclear medicine to be promoted and utilized in the rest of Africa, due to the increasing prevalence of cancer. Cancer is rapidly becoming a public health crisis in low-income and middle-income countries. In sub-Saharan Africa, patients often present with advanced disease

  7. Alpha radioisotopes Ac-225 and Bi-213: a production and labelling of antibodies and peptides for clinical use

    Energy Technology Data Exchange (ETDEWEB)

    Bruchertseifer, Frank, E-mail: frank.bruchertseifer@ec.europa.eu [European Commission, Joint Research Centre, Karlsruhe (Germany)

    2017-07-01

    Full text: In various preclinical and clinical works the potential of the alpha emitters {sup 225}Ac and {sup 213}Bi as therapeutic radionuclides for application in targeted alpha therapy of cancer and infectious diseases was demonstrated. Both alpha emitters are available with high specific activity from established radionuclide generators. Their favorable chemical and physical properties have led to the conduction of a large number of preclinical studies and several clinical trials, demonstrating the feasibility, safety and therapeutic efficacy of targeted alpha therapy with {sup 225}Ac and {sup 213}Bi. This presentation will give an overview about the methods for the production of {sup 225}Ac and {sup 213}Bi, the {sup 225}Ac/{sup 213}Bi radionuclide generator systems, labelling of peptides and antibodies with {sup 225}Ac and {sup 213}Bi and relevant in vivo and in vitro works. (author)

  8. Radioisotopes for medical applications

    International Nuclear Information System (INIS)

    Carr, S.

    1998-01-01

    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

  9. Radioisotope method researches of pharmaceutical preparates

    International Nuclear Information System (INIS)

    Khujaev, S.; Sultanov, A.; Aliev, Kh.; Nazarov, E.A.

    2006-01-01

    Full text: The development of modern stage of nuclear medicine is characterized by the increasing role of methods using radionuclides. Radioactive nuclides used in nuclear medicine may be divided into 2 groups. Radionuclides used for diagnostic researches and radionuclides used for therapeutic purposes. These two directions are considered to be the main ones in usage of radionuclides in medicine. However there is one more direction in the research of new medical products where it is possible to use radionuclides to study their pharmacological kinetics. In these researches radionuclide is applied as a radioactive label at the stage of studying pharmacological kinetics of a new medical product. In Institute of Nuclear Physics AS RU the works are being carried out in the recent years focused on studying pharmacology of some new medical preparations, which are synthesized in Tashkent Pharmaceutical Institute. Syntheses these preparations are based on use microelements. Its compounds are possessed expressed biological activity and be of great importance in the pharmaceutical science of Uzbekistan. Introducing a radioisotope at the stage of synthesis carried out reception of labeled connections of all preparations. The output of the final product reached the yield of no less than 80 percent in all cases of synthesis. This work presents the results of research on synthesis and study of pharmacology of radioactively labeled preparations - Piracin, labeled by radioisotope Zn 6 9I; Cobavit, labeled by radioisotope Co 57; NI 101, labeled by radioisotope Co 57. Received radioisotope - labeled compounds of medical preparations were used in the study of their pharmacological kinetics. In all cases, preliminary irradiation of corresponding nuclear targets in the nuclear reactor and cyclotron, radiochemical procedures on separation, purification and concentration of radioactive isotopes, and reception of its radioactive solution for synthesis of labeled compounds of preparations

  10. Radiation protection at radioisotope processing facilities

    International Nuclear Information System (INIS)

    Hillier, L.R.; Decaire, R.

    2002-01-01

    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)

  11. Development and application of industrial radioisotope instruments in China

    International Nuclear Information System (INIS)

    Lu Yanxiao

    1994-09-01

    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.)

  12. Radioisotopes as Political Instruments, 1946–1953

    Science.gov (United States)

    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 purchase to civilian institutions. This program of the U.S. Atomic Energy Commission was meant to exemplify the peacetime dividends of atomic energy. The numerous requests from scientists outside the United States, however, sparked a political debate about whether the Commission should or even could export radioisotopes. This controversy manifested the tension in U.S. politics between scientific internationalism as a tool of diplomacy, associated with the aims of the Marshall Plan, and the desire to safeguard the country’s atomic monopoly at all costs, linked to American anti-Communism. This essay examines the various ways in which radioisotopes were used as political instruments—both by the U.S. federal government in world affairs, and by critics of the civilian control of atomic energy—in the early Cold War. PMID:20725612

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

    International Nuclear Information System (INIS)

    1963-01-01

    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

  14. Small radioisotope powered batteries

    International Nuclear Information System (INIS)

    Myatt, J.

    1975-06-01

    Various methods of converting the large amounts of energy stored in radioisotopes are described. These are based on:- (a) the Seebeck effect; (b) thermionic emission of electrons from a hot body; (c) the Stirling Cycle; and (d) radiovoltaic charge separation in 'p-n' junctions. Small generators in the range 0 to 100 W(e) developed using these effects are described and typical applications for each of these systems are given. These include data collection and transmission from remote sites, implantable medical devices, lighthouses, radio beacons, and space power supplies. (author)

  15. Radioisotopic Study of Methanol Transformation over H- and Fe-Beta Zeolites; Influence of Si/Al Ratio on Distribution of Products

    International Nuclear Information System (INIS)

    Sarkadi-Priboczki, E.; Kovacs, Z.; Kumar, N.; Murzin, D.Yu.

    2006-01-01

    Complete text of publication follows. The acid-basic properties of Beta zeolite can be modified by dealumination and/or ionexchange. The wide-pore H-Beta zeolite has strong Bronsted acid sites and other chemical environment which govern adsorption and conversion of methanol to dimethyl ether and hydrocarbons during catalysis [1-2]. Partly Fe-ion-exchanged Beta i.e. Fe-H-Beta zeolite keeps this behavior to a certain extent; however, the presence of Fe ions can modify the reaction pathway. In the present work, the methanol conversion was studied over H- and Fe-Beta zeolites at two different Si/Al ratios. 11 C-methanol was used to follow-up adsorption as well as desorption of methanol and its derivates. Therefore, a radioactivity detector was integrated to the gas chromatograph for exact identification of the labelled methanol and its derivates. H-Beta and Fe-Beta zeolites were applied at two different Si/Al ratios i.e. H-Beta(25) and H-Beta(300) and Fe-H-Beta(25) and Fe- H-Beta (300), respectively. A glass tube fixed-bed reactor was used as a closed static reactor. The 11 C-radioisotope (T 1/2 =20.4 min) was produced in 11 C-labelled carbon dioxide form by cyclotron. The 11 C-methanol tracer was produced by radiochemical process [3]. The mixture of 11 C-methanol and non-radioactive methanol was then introduced into zeolite by He gas flow. The volatile products of catalytic conversion of 11 C-methanol were analyzed by radio-gas chromatography (gas chromatograph with flame ionization detector (FID) coupled on-line with a radioactivity detector). The methanol conversion rate and product selectivities to dimethyl ether, hydrocarbons (methane, C 2 -C 6 olefins and paraffins), formaldehyde and carbon-oxides were measured and calculated over H- and Fe-Beta zeolites at two different Si/Al ratios at 250 and 350 deg C. Over H-Beta(25) C 2 -C 6 hydrocarbons (mostly as alkanes) with high conversion rate and some dimethyl ether were detected due to presence of strong Bronsted

  16. Safe Handling of Radioisotopes

    International Nuclear Information System (INIS)

    1958-01-01

    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.

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

    International Nuclear Information System (INIS)

    Burlison, J.S.; Laidler, R.I.

    1979-05-01

    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

  18. The Supply of Medical Radioisotopes. 2016 Medical Isotope Supply Review: 99Mo/99mTc Market Demand and Production Capacity Projection 2016-2021

    International Nuclear Information System (INIS)

    Charlton, Kevin; )

    2016-03-01

    Medical diagnostic imaging techniques using technetium-99m ( 99 mTc) account for approximately 80% of all nuclear medicine procedures, representing 30-40 million examinations Worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 ( 99 Mo) and only 6 hours for 99m Tc, and thus must be produced continuously - can lead to cancellations or delays in important medical testing services. Supply reliability has been challenged over the past decade due to unexpected shutdowns and extended refurbishment periods at some of the 99 Mo-producing research reactors and processing facilities. These shutdowns have at times created conditions for extended global supply shortages (e.g. 2009-2010). At the request of its member countries, the Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo supply situation periodically, to highlight periods of potential reduced supply and to underscore the case for implementing the HLG-MR policy approach in a timely and globally consistent manner. In 2012, the NEA released a 99 Mo supply and demand forecast up to 2030, identifying periods of potential low supply relative to demand. That 2012 forecast was updated with a report in 2014 that focused on the much shorter 2015-2020 period. That report was updated in 2015 with a report, '2015 Medical Isotope Supply Review: 99 Mo/ 99m Tc Market Demand and Production Capacity Projection 2015-2020' (NEA, 2015), which focused on the same period. This report updates the 2015 report, and focuses on the important 2016-2021 period. At the end of 2015, the OSIRIS reactor

  19. The Supply of Medical Radioisotopes. 2015 Medical Isotope Supply Review: 99Mo/99mTc Market Demand and Production Capacity Projection 2015-2020

    International Nuclear Information System (INIS)

    Charlton, Kevin; )

    2015-08-01

    Medical diagnostic imaging techniques using technetium-99m ( 99m Tc) account for approximately 80% of all nuclear medicine procedures, representing 30-40 million examinations Worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 ( 99 Mo) and only 6 hours for 99m Tc, and thus must be produced continuously - can lead to cancellations or delays in important medical testing services. Unfortunately, supply reliability has been challenged over the past decade due to unexpected shutdowns and extended refurbishment periods at some of the mostly ageing, 99 Mo-producing research reactors and processing facilities. These shutdowns have at times created conditions for extended global supply shortages (e.g. 2009-2010). At the request of its member countries, the Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo supply situation periodically, using the most up-to-date data available from supply chain participants, to highlight periods of potential reduced supply and to underscore the case for implementing the HLG-MR policy approach in a timely and globally consistent manner. In 2012, the NEA released a M o supply and demand forecast up to 2030, identifying periods of potential low supply relative to demand. That 2012 forecast was updated with a report 'Medical Isotope Supply in the Future: Production Capacity and Demand Forecast for the 99 Mo/ 99m Tc Market 2015-2020' (NEA, 2014) in 2014 that focused on the much shorter 2015-2020 period. This report updates the 2014 report, and continues to focus on the potentially critical 2015

  20. Support housing for radioisotope generation

    International Nuclear Information System (INIS)

    Fries, B.A.

    1976-01-01

    A support housing for on-site radioisotope generation is disclosed in which the formation of a short-lived daughter radioisotope from its longer-lived parent features countercurrent batch flow of the eluting reagent interior of the housing. 6 claims, 4 drawing figures

  1. Radioisotope Power System Pool Concept

    Science.gov (United States)

    Rusick, Jeffrey J.; Bolotin, Gary S.

    2015-01-01

    Advanced Radioisotope Power Systems (RPS) for NASA deep space science missions have historically used static thermoelectric-based designs because they are highly reliable, and their radioisotope heat sources can be passively cooled throughout the mission life cycle. Recently, a significant effort to develop a dynamic RPS, the Advanced Stirling Radioisotope Generator (ASRG), was conducted by NASA and the Department of Energy, because Stirling based designs offer energy conversion efficiencies four times higher than heritage thermoelectric designs; and the efficiency would proportionately reduce the amount of radioisotope fuel needed for the same power output. However, the long term reliability of a Stirling based design is a concern compared to thermoelectric designs, because for certain Stirling system architectures the radioisotope heat sources must be actively cooled via the dynamic operation of Stirling converters throughout the mission life cycle. To address this reliability concern, a new dynamic Stirling cycle RPS architecture is proposed called the RPS Pool Concept.

  2. The future of medical radioisotope supply

    International Nuclear Information System (INIS)

    Peykov, Pavel

    2014-01-01

    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 ( 99m Tc), and its parent isotope molybdenum-99 ( 99 Mo). 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 99 Mo 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)

  3. Cardiovascular: radioisotopic angiocardiography

    International Nuclear Information System (INIS)

    Kriss, J.P.

    1975-01-01

    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)

  4. Radioisotopes in sedimentology

    International Nuclear Information System (INIS)

    Courtois, G.

    1967-01-01

    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

  5. Radio-isotopic tracers

    International Nuclear Information System (INIS)

    Wolfangel, R.G.

    1976-01-01

    The invention concerns the dispersions that may be used for preparing radio-isotopic tracers, technetium labelled dispersions, processes for preparing these dispersions and their use as tracers. Technetium 99m sulphur colloids are utilized as scintillation tracers to give a picture of the reticulo-endothelial system, particularly the liver and spleen. A dispersion is provided which only requires the addition of a radioactive nuclide to form a radioactively labelled dispersion that can be injected as a tracer. It is formed of a colloid of tin sulphur dispersed in an aqueous buffer solution. Such a reagent has the advantage of being safe and reliable and is easier to use. The colloid can be prepared more quickly since additions of several different reagents are avoided. There is no need to heat up and no sulphuretted hydrogen, which is a toxic gas, is used [fr

  6. Generation of radioisotopes

    International Nuclear Information System (INIS)

    Panek-Finda, H.

    1984-01-01

    A method of producing radioisotopes for radiopharmaceutical applications is claimed. A physiological solution is used to elute a radioactive daughter isotope from a fission-produced parent isotope adsorbed on an adsorbent. The eluate containing the daughter isotope is purified with a cation-exchange material. In separate claims: the parent isotope is molybdenum-99; aluminium oxide which contains fully or partly hydrated manganese dioxide is used as the adsorbent for the parent isotope; a resin is used as the cation-exchange material; a strongly acid cation-exchange resin which has been neutralized is used as a resin; and a strongly acid cation-exchange resin which has been converted into the Na + , K + or NH 4 + form is used as a resin; an isotope generator system is also claimed

  7. Excitation functions of 3He- and α-particle induced nuclear reactions on natSb for production of medically relevant 123I and 124I radioisotopes

    International Nuclear Information System (INIS)

    Tarkanyi, F.; Takacs, S.; Kiraly, B.; Szelecsenyi, F.; Ando, L.; Bergman, J.; Heselius, S.-J.; Solin, O.; Hermanne, A.; Shubin, Yu.N.; Ignatyuk, A.V.

    2009-01-01

    Excitation functions were measured using the stacked foil irradiation technique from threshold energies to 28 MeV for 3 He- and to 21 MeV for α-particle induced nuclear reactions on natural antimony leading to the formation of 121,123,124 I radioisotopes. The measured excitation functions were compared with the contradicting results of the earlier investigations found in the literature and with the curves predicted by the ALICE-IPPE and EMPIRE-II codes. Integral yields were also calculated and compared with the experimental thick target yields reported in the literature.

  8. The application of spectrographic analysis to the radioisotope production control. II. Analysis of calcium-45, scandium-46, nickel-63, and copper-64 solutions

    International Nuclear Information System (INIS)

    Capdevila, C.; Roca, M.

    1972-01-01

    Semi-quantitative and quantitative determinations of both the radioactive and the target element in each radioisotope are described. The copper-spark technique was used except for Cu determinations, that need silver or.graphite electro des. Inter-element effects and their compensation through the use of Bi, 6a, In, Ho, Pd, TI and Y as reference elements was examined. For the determination of Ca in Ca-45 samples, Ba, La, Li and Sr were also tested. Good results are achieved with Li for Ca, Y for Sc,Ti and Ni, and either In or Y for Cu and Zn. (Author) 7 refs

  9. Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2

    Energy Technology Data Exchange (ETDEWEB)

    Abrahamson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States). Inhalation Toxicology Research Inst.; Gilbert, E.S. [Pacific Northwest Lab., Richland, WA (United States)

    1993-05-01

    The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled {open_quotes}Health Effects Models for Nuclear Power Plant Consequence Analysis{close_quotes}, NUREG/CR-4214, 1985 and revised further in the 1989 report NUREG/CR-4214, Rev. 1, Part 2. The health effects models presented in the 1989 NUREG/CR-4214 report were developed for exposure to low-linear energy transfer (LET) (beta and gamma) radiation based on the best scientific information available at that time. Since the 1989 report was published, two addenda to that report have been prepared to (1) incorporate other scientific information related to low-LET health effects models and (2) extend the models to consider the possible health consequences of the addition of alpha-emitting radionuclides to the exposure source term. The first addendum report, entitled {open_quotes}Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, Modifications of Models Resulting from Recent Reports on Health Effects of Ionizing Radiation, Low LET Radiation, Part 2: Scientific Bases for Health Effects Models,{close_quotes} was published in 1991 as NUREG/CR-4214, Rev. 1, Part 2, Addendum 1. This second addendum addresses the possibility that some fraction of the accident source term from an operating nuclear power plant comprises alpha-emitting radionuclides. Consideration of chronic high-LET exposure from alpha radiation as well as acute and chronic exposure to low-LET beta and gamma radiations is a reasonable extension of the health effects model.

  10. Radioisotope research and development at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Peterson, E.J.

    1993-01-01

    Throughout its fifty year history, Los Alamos National Laboratory has conducted research and development in the production, isolation, purification, and application of radioactive isotopes. Initially this work supported the weapons development mission of the Laboratory. Over the years the work has evolved to support basic and applied research in many diverse fields, including nuclear medicine, biomedical studies, materials science, environmental research and the physical sciences. In the early 1970s people in the Medical Radioisotope Research Program began irradiating targets at the Los Alamos Meson Physics Facility (LAMPF) to investigate the production and recovery of medically important radioisotopes. Since then spallation production using the high intensity beam at LAMPF has become a significant source of many important radioisotopes. Los Alamos posesses other facilities with isotope production capabilities. Examples are the Omega West Reactor (OWR) and the Van de Graaf Ion Beam Facility (IBF). Historically these facilities have had limited availability for radioisotope production, but recent developments portend a significant radioisotope production mission in the future

  11. Development of radioisotope preparation and application technology

    International Nuclear Information System (INIS)

    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 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

  12. 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.

  13. Radioisotope Power Systems Technology Development

    Data.gov (United States)

    National Aeronautics and Space Administration — The goal of the RPS's technology portfolio is to advance performance of radioisotope power systems through new and novel innovations being developed and transitioned...

  14. Radioisotope indicator, type BETA 2

    International Nuclear Information System (INIS)

    Duszanski, M.; Pankow, A.; Skwarczynski, B.

    1975-01-01

    The authors describe a radioisotope indicator, type BETA 2, constructed in the ZKMPW Works to be employed in mines for counting, checking, signalling the presence and positioning of cars, as well as monitoring the state of some other equipment. (author)

  15. Radioisotope Power Supply, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Hi-Z Technology has designed, built and tested a small thermoelectric module that is well suited to use the 1 watt radioisotope heater unit (RHU) as a heat source....

  16. Medical application of radioisotopes

    International Nuclear Information System (INIS)

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

    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

  17. 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.

  18. Radioisotope applications on fluidized catalytic cracking units

    International Nuclear Information System (INIS)

    Charlton, J.S.

    1997-01-01

    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, 41 Ar, 79 Kr or 85 Kr. An appropriate tracer for the catalyst is produced by irradiating a catalyst sample in a nuclear reactor. The activation products, 140 La and 24 Na 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

  19. Bronchographic and radioisotopic studies of bronchial clearance

    International Nuclear Information System (INIS)

    Ducousso, R.; Girerd, E.; Nolibe, D.; Metivier, H.; Masse, R.

    1974-01-01

    Bronchograms were performed on monkeys and rats after insufflation of iodinated contrast powders. The clearance kinetics of the contrast media were followed radiographically and by radioisotopic whole body and excreta counting. Because of the product's solubility their elimination through the kidney is augmented with increasing deposition in the peripheral airways. Our attempts to slow down clearance by inducing experimental bronchitis or by previous inhalation of plutonium oxide were unsuccessful. Only insufflation of particles with wounding edges was followed by much longer retention than usual. As opposed to tantalum, the slight solubility of the product allows their elimination with time [fr

  20. Symposium on isotope production and applications

    International Nuclear Information System (INIS)

    1981-01-01

    This report contains the papers delivered at the symposium on isotope production and applications, held at Pelindaba, Pretoria, South Africa. The following topics were discussed: facilities for the production of radioisotopes at Pelindaba; the role of the chemist in the development and production of radioisotopic preparations; quality control of radioisotopic products; applications of radioisotopes in medicine; concepts and current status of nuclear imaging; industrial and research applications of radioisotopic tracers and radioisotopic radiation sources; radiation processing using intense radioisotopic radiation sources; a review of current and future radioisotope production activities at the Council for Scientific and Industrial Research

  1. An overview of computer models for pollutant transfer through the atmosphere, with special consideration for radioisotopes

    International Nuclear Information System (INIS)

    Zivanovic, M.; Djukanovic, J.; Davidovic, M.; Cekerevac, D.; Stankovic, S.

    2011-01-01

    Modern society is intrinsically connected with usage and production of radioisotopes, both for military and civilian applications. During the march of 2007, there were 443 active nuclear plants, unknown quantity of nuclear weapons and a huge number of industrial, medical and other facilities that possess and use radioisotopes for various purposes. With the widespread usage of radioisotopes, there comes a danger of accidental or planed release into the biosphere. This paper gives an overview of the models that can be used for prognosis or reconstruction of radioisotope transfer through the atmosphere in case of accidental or planned release [sr

  2. A new radioisotope facility for Thailand

    International Nuclear Information System (INIS)

    Horlock, K.

    1997-01-01

    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 m 2 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

  3. Radioisotopes for metastatic bone pain.

    Science.gov (United States)

    Roqué I Figuls, Marta; Martinez-Zapata, Maria José; Scott-Brown, Martin; Alonso-Coello, Pablo

    2011-07-06

    This is an update of the review published in Issue 4, 2003. Bone metastasis cause severe pain as well as pathological fractures, hypercalcaemia and spinal cord compression. Treatment strategies currently available to relieve pain from bone metastases include analgesia, radiotherapy, surgery, chemotherapy, hormone therapy, radioisotopes and bisphosphonates. To determine efficacy and safety of radioisotopes in patients with bone metastases to improve metastatic pain, decrease number of complications due to bone metastases and improve patient survival. We sought randomised controlled trials (RCTs) in MEDLINE, EMBASE, CENTRAL, and the PaPaS Trials Register up to October 2010. Studies selected had metastatic bone pain as a major outcome after treatment with a radioisotope, compared with placebo or another radioisotope. We assessed the risk of bias of included studies by their sequence generation, allocation concealment, blinding of study participants, researchers and outcome assessors, and incomplete outcome data. Two review authors extracted data. We performed statistical analysis as an "available case" analysis, and calculated global estimates of effect using a random-effects model. We also performed an intention-to-treat (ITT) sensitivity analysis. This update includes 15 studies (1146 analyzed participants): four (325 participants) already included and 11 new (821 participants). Only three studies had a low risk of bias. We observed a small benefit of radioisotopes for complete relief (risk ratio (RR) 2.10, 95% CI 1.32 to 3.35; Number needed to treat to benefit (NNT) = 5) and complete/partial relief (RR 1.72, 95% CI 1.13 to 2.63; NNT = 4) in the short and medium term (eight studies, 499 participants). There is no conclusive evidence to demonstrate that radioisotopes modify the use of analgesia with respect to placebo. Leucocytopenia and thrombocytopenia are secondary effects significantly associated with the administration of radioisotopes (RR 5.03; 95% CI 1.35 to

  4. Medical research with radioisotopes in Greece

    International Nuclear Information System (INIS)

    Belcher, E.H.

    1961-01-01

    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

  5. Uses of radioisotopes in Sudan

    International Nuclear Information System (INIS)

    Elradi, E. A. M.

    2013-07-01

    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)

  6. How to Handle Radioisotopes Safely.

    Science.gov (United States)

    Sulcoski, John W.

    This booklet is one in a series of instructional aids designed for use by elementary and secondary school science teachers. The various units and forms of radioactive materials used by teachers are first considered. Then, the quantities of radioisotopes that a person may possess without a license from the Atomic Energy Commission (AEC) are…

  7. Radioisotopes point the way ahead

    International Nuclear Information System (INIS)

    Evans, E.A.; Oldham, K.G.

    1988-01-01

    The use of radiochemicals as tracers in medicine is discussed, with particular reference to the choice of radioisotope to be used, its properties, quality control and its detection and measurement in tracer experiments. The development of autoradiography is discussed. (U.K.)

  8. Recent developments in radiation equipment and radioisotopes

    International Nuclear Information System (INIS)

    Beddoes, J.M.

    1978-09-01

    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)

  9. Radioisotope methodology course radioprotection aspects

    International Nuclear Information System (INIS)

    Bergoc, R.M.; Caro, R.A.; Menossi, C.A.

    1996-01-01

    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

  10. Radioisotopes for research on and control of mosquitos

    Science.gov (United States)

    Bruce-Chwatt, Leonard J.

    1956-01-01

    Practical applications of radioactive isotopes in medicine, science, and industry have multiplied enormously during the past five years. In this paper, the author attempts to gather what is known about the use of radioactive isotopes in the research on malaria control. The development of the uranium pile for large-scale production of radioisotopes and technical progress in the making of reliable electronic equipment have greatly contributed to the application of radioactive tracers in biological research. The present knowledge of radioisotopes in mosquito and in insecticide research is discussed. ImagesFIG. 1 PMID:13404435

  11. Radioisotope application to studies of copper electrolytic refining

    International Nuclear Information System (INIS)

    Shul'ts, U.; Lange, Kh.; Gajdel', B.

    1976-01-01

    Silver and selenium behaviour was studied using sup(110m)Ag and 75 Se radioisotopes in the copper electrolysis process. sup(110m)Ag and 75 Se distribution in the electrorefining products was also studied. It was found that Ag/Se mass ratio affected greatly the silver content in the copper cathode. It was found that the tracer technique made it possible to determine 0,1gSe/tCu and 1gAg/t Cu simultaneously and accurately with small material and time expenses. Using sup(110m)Ag radioisotope, the reduction in electrolyte silver content dependent on time may be determined quickly and accurately

  12. Realistic Specific Power Expectations for Advanced Radioisotope Power Systems

    Science.gov (United States)

    Mason, Lee S.

    2006-01-01

    Radioisotope Power Systems (RPS) are being considered for a wide range of future NASA space science and exploration missions. Generally, RPS offer the advantages of high reliability, long life, and predictable power production regardless of operating environment. Previous RPS, in the form of Radioisotope Thermoelectric Generators (RTG), have been used successfully on many NASA missions including Apollo, Viking, Voyager, and Galileo. NASA is currently evaluating design options for the next generation of RPS. Of particular interest is the use of advanced, higher efficiency power conversion to replace the previous thermoelectric devices. Higher efficiency reduces the quantity of radioisotope fuel and potentially improves the RPS specific power (watts per kilogram). Power conversion options include Segmented Thermoelectric (STE), Stirling, Brayton, and Thermophotovoltaic (TPV). This paper offers an analysis of the advanced 100 watt-class RPS options and provides credible projections for specific power. Based on the analysis presented, RPS specific power values greater than 10 W/kg appear unlikely.

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

    International Nuclear Information System (INIS)

    Simmons, J.L.

    1978-07-01

    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

  14. New data on cross-sections of deuteron induced nuclear reactions on gold up to 50 MeV and comparison of production routes of medically relevant Au and Hg radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Tárkányi, F. [Institute for Nuclear Research, Hungarian Academy of Sciences (ATOMKI), Debrecen (Hungary); Hermanne, A. [Cyclotron Laboratory, Vrije Universiteit Brussel (VUB), Brussels (Belgium); Ditrói, F., E-mail: ditroi@atomki.hu [Institute for Nuclear Research, Hungarian Academy of Sciences (ATOMKI), Debrecen (Hungary); Takács, S. [Institute for Nuclear Research, Hungarian Academy of Sciences (ATOMKI), Debrecen (Hungary); Adam Rebeles, R. [Cyclotron Laboratory, Vrije Universiteit Brussel (VUB), Brussels (Belgium); Ignatyuk, A.V. [Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation)

    2015-11-01

    Highlights: • Deuteron induced nuclear reactions on natural gold up to 50 MeV. • Stacked foil irradiation technique. • Comparison of results with the ALICE, EMPIRE and TENDL-2014 calculations. • Medical radioisotope production. - Abstract: Investigations of cross-sections of deuteron induced nuclear reactions on gold were extended up to 50 MeV by using the standard stacked foil irradiation technique and high resolution gamma-ray spectrometry. New cross-sections are reported for the {sup 197}Au(d,xn){sup 197m,197g,195m,195g,193m,193g}Hg and {sup 197}Au(d,x){sup 198m,198g,196m,196g,195,194}Au nuclear reactions. The application for production of the medically relevant isotopes {sup 198}Au and {sup 195m,195g,197m,197g}Hg is discussed, including the comparison with other charged particle induced production routes. The possible use of the {sup 197}Au(d,x){sup 197m,197g,195m,193m}Hg and {sup 196m,196g}Au reactions for monitoring deuteron beam parameters is also investigated.

  15. Development of nuclear theory and computer code for the evaluation of nuclear cross-sections relevant to beam monitoring used in medical radioisotope production and fusion technology. Final report for the period 15 December 1995 - 14 December 1997

    International Nuclear Information System (INIS)

    Gul, K.

    1998-06-01

    Nuclear reactions induced by light charged particles in copper are of importance as monitors in medical radioisotope production. Careful evaluations are needed for the excitation functions of activation reactions in copper with protons, 4-He and 3-He from the point of view of their use as beam flux monitors in the incident energy range below 30 MeV. The method used in the present work was based on theoretical calculations and comparison with experimental data. Calculations were performed using the Hauser-Feshbach statistical model and the preequilibrium hybrid model. To this end, the codes HFMOD and PREMOD developed at PINSTECH, Pakistan, were employed. Careful selection of optical model parameters, nuclear level densities as well as discrete levels was performed. Obtained were 10 excitation functions for production of radioactive isotopes on 63-Cu and 65-Cu with p, 4-He and 3-He: Protons in 3-25 MeV range, 63-Cu(p,n) 63-Zn, 63-Cu(p,2n) 62-Zn, 65-Cu(p,n) 65-Zn; Alphas in 8-27 MeV energy range, 63-Cu(a,n) 66-Ga, 63-Cu(a,2n) 65-Ga, 63-Cu(a,np) 65-Zn, 65-Cu(a,n) 68-Ga, 65-Cu(a,2n) 67-Ga; 3-He in 7-20 MeV range, 63-Cu(3He,n) 67-Ga, 65-Cu(3He,2n) 66-Ga. (author)

  16. 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.

  17. Physical aspects of radioisotope brachytherapy

    International Nuclear Information System (INIS)

    1967-01-01

    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

  18. Alpha-emitting radionuclides in cigarette tobacco

    International Nuclear Information System (INIS)

    Neton, James W.; Ibrahim, Shawki Amin

    1978-01-01

    As part of general studies of the concentration of 239/240 Pu, 238 Pu and 228,230,232 Th in the tissues of non-occupationally exposed individuals, it became evident that there was little or no information on their content in cigarette tobacco. To better understand this possible route of intake and its potential for lung exposure we have measured these nuclides in tobacco samples, from the U.S. Department of Agriculture (USDA), which have a well-known growing history, and in brand name cigarettes purchased commercially. The concentration of 239/240 Pu in both USDA and brand name tobacco has a range of 0.4-0.7 pCi/kg of tobacco while the 238 Pu concentration was ≤ 0.05 pCi/kg. The 228 Th concentration for USDA tobacco was 200 pCi/kg tobacco while the 232 Th was only 14 pCi/kg. The high 228/232 Th ratio may result from a lower uptake of 232 Th compared to that of 228 Ra. By comparing the concentration of these measured nuclides to other alpha emitters in tobacco that have been reported in the literature, i.e. 210 Po (400 pCi/kg) and 226 Ra (150 pCi/kg), it is apparent that 228 Th represents a significant fraction of the total alpha activity. It is also evident there is a much greater potential for exposure of the lung to radiation from 228 Th than from 239/240 Pu as a result of cigarette smoking. (author)

  19. Microbiological quality control practices at Australian Radioisotopes

    International Nuclear Information System (INIS)

    Saunders, M.

    1987-01-01

    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

  20. Accelerated Decay of Radioisotopes

    Science.gov (United States)

    2013-01-01

    controllable and varied to access reactions of interest (primarily (n,n’) inelastic scattering). Theory and analysis using Monte Carlo codes (MCNPX) is still...performance and p-7Li neutron production: The Mercury pulsed power generator was operated in positive polarity at 2/3 Marx charge. Positive polarity...was achieved by reversing the normal Marx charging polarity, which can be easily done at the lower 50 kV (out of 75 kV) charge. The ion diode produced

  1. Present status and prospect of radiation and radioisotopes in China

    International Nuclear Information System (INIS)

    Zhou, Yong-Tian

    1986-01-01

    Production and application of radioisotopes in China started almost thirty years ago. At present there are 20 units producing more than 700 radioisotope products. This report outlines the present status and prospect of radiation and radioisotopes in some major areas. Remarkable achievements have been made in agriculture using nuclear technology. More than 70 new varieties or strains of cultivated plants have been bred by inducing mutation through irradiation. A new variety of silkworm bred by irradiation has unique characteristics such as high and stable yield. Application of radioisotopes in medical research and clinical practice began in 1956 and radionuclides have been progressively used in diagnosis and treatment of diseases. The most common radionuclide used in therapy is iodine-131 for hyperthyroidism. Isotope-tracer technique and activation analysis play an important role in the study of traditional Chinese medicine. Isotope methods in China have been used in many industrial branches, such as textile, plastic and printing, but not very widely now. The nation has produced more than 2,000 sets of nuclear radiation measuring instruments, which become important parts of industrial automation control. The radiation processing research started in the end of 1950's. Food irradiation research has been going on in a good cooperation of different branches. Now China is planning to set up some plants to produce gamma irradiated disposal syringes and other medical devices. (Nogami, K.)

  2. Radioisotope evaluation in cardiology

    International Nuclear Information System (INIS)

    Massardo V, Teresa; Gonzalez E, Patricio; Canessa G, Jose

    2002-01-01

    The current applications of nuclear cardiology techniques are reviewed. Coronary artery disease is the most important and prevalent cardiovascular problem in most developed countries and also in Chile. Different approaches can be employed for its diagnosis and prognosis, as well as for risk stratification and preoperative evaluation. Myocardial infarction assessment and ischemia recognition with radionuclide perfusion images are also reviewed, including new protocols applying functional parameters addition. Viability detection after myocardial infarction or in patients with ischemic cardiomyopathy are discussed. Stress protocols with the use of exercise or pharmacological action for ischemia production, the diagnostic value of perfusion SPECT and the use of Thallium-201, Tc-99m-Sestamibi and metabolic images with Fluorine18-Fluordeoxyglucose are also mentioned (au)

  3. Ion exchange chromatography on a new form of tin dioxide for the isolation of strontium radioisotopes from fission products: an application to milk samples

    International Nuclear Information System (INIS)

    Stella, R.; Valentini, M.T.G.; Maggi, L.

    1990-01-01

    An amorphous, partially-reduced tin dioxide, having properties of an inorganic exchanger, was tested for application to fission product separations. Due to the good sorption of both strontium and barium the application of the exchanger to radiostrontium isolation from fission product mixtures is subjected to important restrictions. An application to 90 Sr determination in milk is proposed. (author)

  4. Radioisotopes in nuclear medicine

    International Nuclear Information System (INIS)

    Samuel, A.M.

    2002-01-01

    Full text: A number of advances in diverse fields of science and technology and the fruitful synchronization of many a new development to address the issues related to health care in terms of prognosis and diagnosis resulted in the availability of host of modern diagnostic tools in medicine. Nuclear medicine, a unique discipline in medicine is one such development, which during the last four decades has seen exponential growth. The unique contribution of this specialty is the ability to examine the dynamic state of every organ of the body with the help of radioactive tracers. This tracer application in nuclear medicine to monitor the biological molecules that participate in the dynamic state of body constituents has led to a whole new approach to biology and medicine. No other technique has the same level of sensitivity and specificity as obtained in radiotracer technique in the study of in-situ chemistry of body organs. As modem medicine becomes oriented towards molecules rather than organs, nuclear medicine will be in the forefront and will become an integral part of a curative process for regular and routine application. Advances in nuclear medicine will proceed along two principal lines: (i) the development of improved sensitive detectors of radiation, powerful and interpretable data processing, image analysis and display techniques, and (ii) the production of exotic and new but useful radiopharmaceuticals. All these aspects are dealt with in detail in this talk

  5. Research trends in radioisotopes: a scientometric analysis

    International Nuclear Information System (INIS)

    Sagar, Anil; Kademani, B.S.; Bhanumurthy, K.; Ramamoorthy, N.

    2014-01-01

    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)

  6. Medical radioisotopes for the next century

    International Nuclear Information System (INIS)

    Carr, S.W.

    1999-01-01

    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

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

    International Nuclear Information System (INIS)

    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

  8. Radioisotopes labelled agrochemicals for fertiliser development

    International Nuclear Information System (INIS)

    Cherian, S.; Subramanian, T.K.; Aachari, P.S.; Murthy, T.S.

    1979-01-01

    Chemical fertilisers like superphosphate, urea, ammonium phosphate, etc., are extensively used in agriculture for improving yields of various crops. Agrochemicals labelled with radioisotopes help in evaluating the fertiliser uptake and the role of essential nutrients like phosphorus, nitrogen and calcium in different types of soils. Such studies help the industry considerably in preparing fertilisers suitable for various crops and soil conditions. Methods have been developed for the large scale preparation of labelled fertilisers like superphosphate- 32 P, nitric phosphate- 32 P with varying water solubilities. An account of the experimental investigations carried out and the finalised procedures for the preparation of labelled agrochemicals are given. The chemical methods developed would be suitable for production of fertilisers using raw materials indigenously available. (auth.)

  9. Applications of radioisotopes in industry and healthcare in Vietnam

    International Nuclear Information System (INIS)

    Dien, N.N.; Quang, N.H.

    1997-01-01

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

  10. Radioisotope programme in India: past, present and future

    International Nuclear Information System (INIS)

    Kohli, A.K.

    2012-01-01

    One of the major discoveries of the 20th century is the discovery of artificial radioactivity. This distinctive discovery in human history transformed atoms of one element to another. Until then, chemical reactions used to be concerned only with changes occurring outside the nucleus. The field of nuclear science came into existence with discovery of X-rays by Wilhelm Roentgen in 1895, radioactivity emitted by Uranium salt by Henri Becquerel in 1896 and pioneering work carried out by Madame Curie and Pierre Curie. India's atomic energy programme was envisaged, founded and developed by the great visionary Dr. Homi Jehangir Bhabha. Since then Department of Atomic Energy (DAE) of Government of India has been engaged in developing technologies for use of radiation in all possible fields for the benefit of society. The most common sources of radiation are radioisotopes. Radioisotopes are produced by nuclear reactors either by utilizing available excess neutrons for activation of stable elements or by separating useful fission products from the spent fuel. In India, the production of radioisotopes started with the commissioning of APSARA reactor in 1956. Initially, APSARA was operated at low power, and radioisotopes could be produced only on a small scale. All these operations had to be called out with remote handling or in the safe glove boxes keeping in view the radiation levels associated with the samples. In due course, the reactor reached full power and remotely operated processing equipment required for handling the radioisotopes were set up. Isotopes such as Iodine-131, Phosphorous-32, Gold-198 and Sodium-24 were produced and extracted in purified form in small quantities. These were given to KEM Hospital and Bombay Hospital at Mumbai, Vallabhbhai Patel Chest Institute and Safdarjung Hospital in Delhi, mainly for exploratory experiments

  11. Application of radiation and radioisotopes in life science

    International Nuclear Information System (INIS)

    Nakanishi, Tomoko M.

    2005-01-01

    Radiation and Radioisotopes have been played an important role in the wide range of life science, from the field study, such as fertilizer or pesticide development or production of new species, to gene engineering researches. Many mutants through radiation have been provided to the market and the usage of radioactive tracers was an effective tool to study plant physiology. It has been granted that the contribution of radioisotopes has been accelerated the development of the gene engineering technology, which is now overwhelming all the other usages of radiation or radioisotopes. However, because of the difficulty to get social acceptance for gene modified plants, the orientation of the life science is now changing towards, so called ''post genome era''. Therefore, from the point of radiation or radioisotope usage, new application methods are needed to develop new type of researches. We present how (1) neutron activation analysis, (2) neutron radiography and (3) positron emission tomography are promising to study living plant physiology. Some of these techniques are not necessarily new methods but with a little modification, they show new aspects of plant activity. (author)

  12. Transport of the radioisotopes iodine-131, cesium-134, and cesium-137 from the fallout following the accident at the Chernobyl nuclear reactor into cheesemaking products

    International Nuclear Information System (INIS)

    Assimakopoulos, P.A.; Ioannides, K.G.; Pak; Paradopoulou, C.V.

    1987-01-01

    The transport of radiation contamination from milk to products of the cheese making process has been studied. The concentration of radioactive iodine and cesium in samples of sheep milk and cheese (Gruyere) products was measured for 10 consecutive production d. Milk with concentration 100 Bq/L in each of the radionuclides 131 I, 134 Cs, and 137 Cs cheese with concentration 82.2 +/- 3.9 Bq/kg in iodine and an average of 42.3 +/- 2.3 Bq/kg in the cesium isotopes is produced. The corresponding concentrations in cream extracted from the same milk are 26.7 +/- 2.8 Bq/kg ( 131 I) and 18.6 +/- 1.9 Bq/kg ( 134 Cs, 137 Cs)

  13. The industrial application of radioisotopes

    International Nuclear Information System (INIS)

    Frevert, E.

    1991-01-01

    In this paper the two main fields of the industrial application of radioisotopes are introduced. In the field of process controlling device and control first about the transmission and the backscattering methods is reported. Then the x-ray fluorescence method and the moisture gauging with neutrons are mentioned. Also the measuring of depth of charge. In the field of tracer investigations about all kinds of flow and intermixture measurements is reported. And investigations of corrosion, wear and lubrication and precise location of nonmetallic pipe lines are mentioned. (Author)

  14. Artificial radioisotopes in hydrological investigation

    International Nuclear Information System (INIS)

    Plata-Bedmar, A.

    1988-01-01

    Radioisotope techniques have an important part in hydrological investigations. Sealed radiation sources have been used for measurements of sediments transported by river water, of thickness and density of sediment layers. X-ray fluorescence analysis and well-logging are widely applied in hydrological research. Tracer techniques have been useful in flow rate and river dynamics research, sediments tracing, irrigation and ground water problems, infiltration rate evaluation etc. The IAEA is supporting several projects involving the use of radioactive tracers in hydrological investigations p.e. in Guatemala, Romania, South East Asia, Brazil, Chile and Nicaragua

  15. Radioisotope studies on coconut nutrition

    International Nuclear Information System (INIS)

    Ray, P.K.

    1979-01-01

    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)

  16. List of ERDA radioisotope customers with summary of radioisotope shipments, FY-1974

    International Nuclear Information System (INIS)

    Simmons, J.L.; Mandell, S.

    1974-01-01

    The eleventh edition of the AEC 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 1974 commercial radioisotope production and distribution activities of USAEC 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. The information is divided into four sections. Section I is an alphabetical list of domestic and foreign customers and their addresses. Each customer has been designated a number according to its alphabetical position which provides a means of cross-referencing in the following sections. The isotopes purchased are listed after the address of the customer and the laboratory supplying each isotope is indicated by a letter set off by parentheses. Section II is an alphabetical list of isotopes, cross-referenced to customer numbers and again divided into the domestic and foreign categories. This section provides a quick idea of the amount of companies purchasing a particular isotope. If more information is needed, the reader can locate the customer by number and determine the laboratory supplying the isotope. The third section is an alphabetical list of states and countries, also cross-referenced to customer numbers, indicating geographical concentrations of isotope users. Section IV summarizes the FY 1974 radioisotope shipment activities of USAEC 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 (AEC facilities) categories, and the total figures for each isotope are also provided. (U.S.)

  17. The Supply of Medical Radioisotopes. Medical Isotope Supply in the Future: Production Capacity and Demand. Forecast for the 99Mo/99mTc Market, 2015-2020

    International Nuclear Information System (INIS)

    Peykov, Pavel; Cameron, Ron

    2014-04-01

    This document presents a forecast of 99 Mo/ 99m Tc production capacity and demand in 2015-2020, when two major irradiators - the OSIRIS and NRU reactors in France and Canada - are expected to exit the global supply chain and new alternative technology projects may be commissioned. The forecast does not attempt to predict shortages, but identify periods when there is an increased risk of disrupted supply, to inform policy makers and other stakeholders. (authors)

  18. Cross-sections for (p,x) reactions on natural chromium for the production of (52,52m,54)Mn radioisotopes.

    Science.gov (United States)

    Wooten, A Lake; Lewis, Benjamin C; Lapi, Suzanne E

    2015-02-01

    The production of positron-emitting isotopes of manganese is potentially important for developing contrast agents for dual-modality positron emission tomography and magnetic resonance (PET/MR) imaging, as well as for in vivo imaging of the biodistribution and toxicity of manganese. The decay properties of (52)Mn make it an excellent candidate for these applications, and it can easily be produced by bombardment of a chromium target with protons or deuterons from a low-energy biomedical cyclotron. Several parameters that are essential to this mode of production—target thickness, beam energy, beam current, and bombardment time—depend heavily on the availability of reliable, reproducible cross-section data. This work contributes to the routine production of (52g)Mn for biomedical research by contributing experimental cross-sections for natural chromium ((nat)Cr) targets for the (nat)Cr(p,x)(52g)Mn reaction, as well as for the production of the radiocontaminants (52m,54)Mn. Copyright © 2014. Published by Elsevier Ltd.

  19. Actual and future situations of the use of radioisotopes; Situacion actual y futura del empleo de radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Paredes G, L.C. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-07-01

    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)

  20. Development of Radioisotope Tracer Technology

    International Nuclear Information System (INIS)

    Jung, Sung Hee; Jin, Joon Ha; Kim, Jong Bum; Kim, Jin Seop; Kim, Jae Jo; Park, Soon Chul; Lim, Don Soon; Choi, Byung Jong; Jang, Dong Soon; Kim, Hye Sook

    2007-06-01

    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

  1. Power from Radioisotopes, Understanding the Atom Series.

    Science.gov (United States)

    Corliss, William R.; Mead, Robert L.

    This 1971 revision deals with radioisotopes and their use in power generators. Early developments and applications for the Systems for Nuclear Auxiliary Power (SNAP) and Radioisotope Thermoelectric Generators (RTGs) are reviewed. Present uses in space and on earth are included. Uses in space are as power sources in various satellites and space…

  2. Trends in the development of radioisotope batteries

    International Nuclear Information System (INIS)

    Goeldner, R.; Leonhardt, J.W.; Radmaneche, R.; Schlegel, H.

    1978-01-01

    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)

  3. Elementary concepts of the radioisotopes uses

    International Nuclear Information System (INIS)

    Pisarev, Mario A.

    2004-01-01

    Endocrinology has been one of the specialties earlier benefited for the radioisotopes uses in the diagnosis and treatment of different affections. These applications are based on the radioisotopes property of biochemical behaving as non- radioactive molecules, and at the same time, radiations emitting that can be detected by suitable means (diagnostic utility) or that have effects on biological systems (therapeutic action). (author) [es

  4. Studies on radioisotope mutagenesis in mammals

    International Nuclear Information System (INIS)

    Reddi, O.S.; Naidu, N.V.; Reddy, P.P.

    1974-01-01

    Studies on radioisotope mutagenesis are important from the point of view of the possible genetic hazards of their increasing use in medical and industrial applications and their concentration in man through environmental contamination. This paper reviews a series of studies undertaken on the genetic consequences of internal administation of certain selected radioisotopes, namely, 32 P, 131 I and 90 Sr in mammalian systems. (author)

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

    International Nuclear Information System (INIS)

    Lamar, D.A.

    1988-01-01

    Data were collected and compiled on radioisotopes produced and sold by Department of Energy (DOE) facilities, and on services rendered by DOE facilities. Compiled data were published and distributed in the document list of DOE Radioisotope Customers with Summary of Radioisotope Shipments, FY 1986, PNL-6361, October 1987. The DOE facilities that supplied information for the compilation were Argonne National Laboratory, Brookhaven National Laboratory, Hanford Engineering Development Laboratory, Idaho National Engineering Laboratory, Los Alamos National Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratory, Savannah River Plant, and UNC Nuclear Industries, Inc. (Hanford). The data provided were reported in several different ways: (1) a list of radioisotopes and services provided by each facility; (2) a list of radioisotope customers, the supplying DOE facility, and the radioisotope or service provided to each customer; and (3) a list of the quantity and value of each radioisotope or service sold by each DOE facility. The sales information covered foreign customers, domestic private customers, and domestic DOE customers

  6. Guidebook on radioisotope tracers in industry

    International Nuclear Information System (INIS)

    1990-01-01

    The idea of using tracers (chemical, dyes, etc.) in the investigation of complex physical phenomena has always attracted the attention of scientists and engineers. When radioactive isotopes became available it was immediately recognized that they offered an almost ideal solution to tracer selection. This book is devoted to reviewing the present status of the tracer method as such and to its applications to those branches of industry which have derived large benefits from the use of this modern technology. The main objectives of the IAEA's Industrial Applications and Chemistry Section is to help Member States in introducing to their own industries the different isotope and radiation techniques which have become available as a result of developments in the nuclear sciences. This section proposed the preparation of this guidebook, putting together various radiotracer methods and the experience obtained so far in their industrial use. Chapters 2 to 4 cover the general concept of tracers, technology and safety aspects, as well as data evaluation and interpretation. In chapter 5, therefore, general applications are discussed. In chapter 6, specialists in selected fields discuss their experience in radiotracer applications in various types of industrial activity. Most case studies are illustrated by at least one detailed example of an experiment carried out at an industrial installation. Current trends in the development of radiotracer methods are discussed in chapter 7, from both a theoretical and a practical viewpoint. Some possible new RTT applications in the future are also discussed here. Sealed radioactive sources are used almost as often as radioisotope tracers in industrial measurements. Annex I gives a short review of these techniques. Readers who are interested in the basic principles of radioisotope production will find the necessary information in Annex II. Annexes III, V and VI provide a demonstration of fundamental relations and properties; useful

  7. Study and development recuperation of Thallium-203 from bombarded targets of this metal in production of Thallium-201 via addition of Thallium-201 radioisotope as a tracer

    International Nuclear Information System (INIS)

    Shirazi, B.

    2006-01-01

    Thallium-203 is the main material for 201 TlCl 3 radiopharmaceutical. It is very important to recover the remaining enriched Thallium-203 in every stage of the process to be reused in the production loop. In this research, the recuperation of Thallium-203 was studied with Dowex 50 WΧ8 ion exchange resin and Thallium-201 as a tracer. The results based on filling of ( 1 8 X 1.5) cm columns with this resin showed that the best flow rate of eluent is 2 ml/min. Also the most suitable volumes are 200 mL (HNO 3 0.05 M), 400 mL (solution of Thallium-203), 100 mL (H 2 O), 500 mL (Citric acid), 100 mL (H 2 0), 100 mL (EDTA 0.5 M and pH∼12.5). 60 mL (H 2 0), respectively

  8. 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. http://www.sciencedirect.com/science/article/B6TVT-4C...

  9. Conceptual study of a compact accelerator-driven neutron source for radioisotope production, boron neutron capture therapy and fast neutron therapy

    CERN Document Server

    Angelone, M; Rollet, S

    2002-01-01

    The feasibility of a compact accelerator-driven device for the generation of neutron spectra suitable for isotope production by neutron capture, boron neutron capture therapy and fast neutron therapy, is analyzed by Monte Carlo simulations. The device is essentially an extension of the activator proposed by Rubbia left bracket CERN/LHC/97-04(EET) right bracket , in which fast neutrons are diffused and moderated within a properly sized lead block. It is shown that by suitable design of the lead block, as well as of additional elements of moderating and shielding materials, one can generate and exploit neutron fluxes with the spectral features required for the above applications. The linear dimensions of the diffusing-moderating device can be limited to about 1 m. A full-scale device for all the above applications would require a fast neutron source of about 10**1**4 s**-**1, which could be produced by a 1 mA, 30 MeV proton beam impinging on a Be target. The concept could be tested at the Frascati Neutron Gener...

  10. NASA's Radioisotope Power Systems - Plans

    Science.gov (United States)

    Hamley, John A.; Mccallum, Peter W.; Sandifer, Carl E., II; Sutliff, Thomas J.; Zakrajsek, June F.

    2015-01-01

    NASA's Radioisotope Power Systems (RPS) Program continues to plan and implement content to enable planetary exploration where such systems could be needed, and to prepare more advanced RPS technology for possible infusion into future power systems. The 2014-2015 period saw significant changes, and strong progress. Achievements of near-term objectives have enabled definition of a clear path forward in which payoffs from research investments and other sustaining efforts can be applied. The future implementation path is expected to yield a higher-performing thermoelectric generator design, a more isotope-fuel efficient system concept design, and a robust RPS infrastructure maintained effectively within both NASA and the Department of Energy. This paper describes recent work with an eye towards the future plans that result from these achievements.

  11. Radioisotope tracer applications in industry

    International Nuclear Information System (INIS)

    Rao, S.M.

    1987-01-01

    Radioisotope tracers have many advantages in industrial trouble-shooting and studies on process kinetics. The applications are mainly of two types: one leading to qualitative (Yes or No type) information and the other to quantitative characterisation of flow processes through mass balance considerations and flow models. ''Yes or No'' type methods are mainly used for leakage and blockage locations in pipelines and in other industrial systems and also for location of water seepage zones in oil wells. Flow measurements in pipelines and mercury inventory in electrolytic cells are good examples of tracer methods using the mass balance approach. Axial dispersion model and Tanks-in-Series model are the two basic flow models commonly used with tracer methods for the characterisation of kinetic processes. Examples include studies on flow processes in sugar crystallisers as well as in a precalcinator in a cement plant. (author). 18 figs

  12. 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.

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

    International Nuclear Information System (INIS)

    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

  14. Radioisotopic Studies of Brain Uptake

    International Nuclear Information System (INIS)

    Oldendorf, W. H.

    1970-01-01

    Measurements of the uptake of radioactive substances in the brain tissues after their administration by injection or inhalation provide an a traumatic approach to the study of blood flow and metabolic processes in the brain. This paper reviews the anatomical,physiological and physical problems arising in the measurement of radioactivity in the brain. The factors governing the passage of various classes of substances through the brain capillaries and their transport through the brain tissues are first considered. The physical problems arising in the measurement of radioactivity in the brain are then discussed. The main difficulties in such measurements is shown to arise from the contribution to the observed counting rate from radioactivity in the scalp and skull. This contribution can be minimized by the use of special collimators designed to view only a part of the brain but to include in their field of view a minimum of non-neural tissue. A further possibility arises with radioisotopes such as 113 In m which emit characteristic X radiation as well as y radiation since the contribution of the former to the total observed counting rate is almost entirely due to radioactivity in the superficial tissues whereas that of the latter is due to radioactivity in the superficial tissues and the brain. By recording the counting rates in appropriate channels of the photon spectrum it is thus possible to correct the results for radioactivity in the scalp and skull. With radioisotopes such as 75 Sc which emit two or more photons in cascade, coincidence counting techniques offer still a further possibility to minimize the contribution from radioactivity in the superficial tissues. Various potential applications of these techniques are described. (author)

  15. Review of Radioisotopes as Radiological Weapons

    Science.gov (United States)

    2016-06-01

    I N S T I T U T E F O R D E F E N S E A N A L Y S E S Review of Radioisotopes as Radiological Weapons Carl A. Curling Alex Lodge INSTITUTE FOR...E A N A L Y S E S IDA Document D-8048 Review of Radioisotopes as Radiological Weapons Carl A. Curling Alex Lodge This page is intentionally blank...representative of the highest typical activ- ity of that radioisotope , the amount of radioactive material found with that practice (Activ- ity of Practice

  16. 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.

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

    International Nuclear Information System (INIS)

    Bennett, N.; Chikshov, A.I.; Malykh, Y.A.

    1997-01-01

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

  18. 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.

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

    International Nuclear Information System (INIS)

    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

  20. Radioisotopes: problems of responsibility arising from medicine

    International Nuclear Information System (INIS)

    Dupon, Michel.

    1978-09-01

    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 [fr

  1. Milliwatt Radioisotope Stirling Convertor, Phase II

    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. Radioisotope applications in petroleum and gas industries

    International Nuclear Information System (INIS)

    Castagnet, A.C.; Agudo, E.G.; Duarte, U.

    1974-01-01

    The principal radioisotopic technique used for studying and /or controling the drilling, completion, treatment and oil well secondary recovery operations are described. In this cases the radioisotopes are employed almost exclusively as 'markers', in the form of localized and dispersed tracers. The growing acceptance of these techniques is essentially, a consequence of the confidence in the reliability of the data and conclusions derived from their application

  3. Radioisotope tracers in industrial flow studies

    International Nuclear Information System (INIS)

    Easey, J.F.

    1987-01-01

    The scope of radioisotope tracer work carried out by ANSTO has involved most sectors of Australian industry including iron and steel coal, chemical, petrochemical, natural gas, metallurgical, mineral, power generation, liquified air plant, as well as port authorities, water and sewerage instrumentalities, and environmental agencies. A major class of such studies concerns itself with flow and wear studies involving industrial equipment. Some examples are discussed which illustrate the utility of radioisotope tracer techniques in these applications

  4. Radioisotopes preparation with GA Siwabessy for application in health/medical

    International Nuclear Information System (INIS)

    Sunarhadijoso-Soenarjo

    2003-01-01

    The Center for Development of Radioisotopes and Radiopharmaceuticals (CDRR) has to improve its role and potency to comply domestic demand in radioisotope preparations. The radioisotopes are used as both primary radioisotopes and labeled compounds, especially for medical diagnosis and therapy as radiopharmaceutical preparations. The implementation of capability in production of radioisotopes and radiopharmaceuticals is fully affected by the readiness of operational function of supporting facilities in regard to maintain safety system, process and personnel as well. For those reasons, activities program has been carried out with the aims of : (a). To faithful capability in production of GA Siwabessy reactor based radioisotopes, labeled compounds and radiopharmaceutical kits, (b). To optimize normal operational function of supporting facilities and utilities, and (c). To perform invention and modification of heater and temperature control units on the air handling unit (AHU) system. Some kinds of radioactive products are dominant during the year of 2002, i.e. 153 SmCl 3 , Na 2 99 MoO 4 and Na 186 ReO 4 primary radioisotopes and 153 Sm-EDTMP labeled compound. The main utilization of the products is for research and development of processing technology and medical application as diagnostic or therapeutic agent. The operational function of supporting facilities and utilities was well performed meeting the requirement of the users. Some units of the systems partially showed degradation of working performance but it did not cause trouble in security and safety of the system, process and personnel. A heater device completed with control system has been installed as a modified part of AHU system and has been tested successfully. The operation of the heater device is significantly influential to the air temperature and humidity in working area. The required air condition, e.g. 22 - 25 o C of temperature and 40 - 50 % of humidity, can be complied on the blower motor

  5. 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)

  6. Early radioisotope uses in Mexico

    International Nuclear Information System (INIS)

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

    1991-10-01

    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)

  7. Development of radioisotope tracer technology

    International Nuclear Information System (INIS)

    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)

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

    Science.gov (United States)

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

    2016-01-01

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

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

    Science.gov (United States)

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

    2016-01-01

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

  10. Safety Analysis for a Radioisotope Stirling Generator

    International Nuclear Information System (INIS)

    William D. Richins; Jeffrey M. Lacy; Stephen R. Novascone; Barbara H. Dolphin

    2007-01-01

    The Idaho National Laboratory INL is conducting safety analyses of Radioisotope Stirling Generators for the Department of Energy (NE-50) to support the use of these devices as terrestrial power sources. 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. The subject generator is the product of a collaborative effort by Lockheed Martin, Infinia, and the Glenn Research Center. 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 storage and 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. The overall simulation results predicted by our software tools will be validated by impact testing. 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

  11. Analysis of status of radiation/radioisotopes utilization

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chan Hee; Lee, Seung Hyun; Kim, Na Kyung; Kim, Kon Wuk [Business Innovation Office, Korean Association for Radiation Application, Seoul (Korea, Republic of)

    2017-03-15

    The use of radiation and radioisotopes in Korea has been increasing each year, and its impact on economy and industry is expected to be increasing progressively following the development of industrial technology and the expansion of their usage. To establish and supporting policies for industries using radiation and radioisotopes, it is necessary to check the status of related industries accurately, as well as to gather data required to establish plans for industrial development by studying both revenues and economic scale (contributing to revenue). o analyze the status of utilization, surveys were carried out on 6,621 organizations engaged in nuclear operations handling radiation and radioisotopes pursuant to the Nuclear Safety Act as of end 2014, on 33,471 medical institutions using radiation generators for medical and diagnostic purposes pursuant to the Medical Service Act, and on 2,218 organizations using radiation generators for animal diagnostics pursuant to the Veterinary License Act. he overall status of the domestic radiation market including the number of user organizations, that of employees, and the size of distributions (imports, productions, and exports) with which the scale of domestic radiation market can be judged showed a growth trend compared to the previous year, though the number of employees for radiation operation in industrial sector, research sector, education sector, military sector, and power plants (nuclear power plants) and the size of imports was reduced somewhat. t is expected that data acquired through periodic surveys on the status of utilization would be utilized practically in establishing governmental policies related to the promotion of usage of radiation and radioisotopes, and also be utilized widely in cultivating and developing the industry efficiently to invigorate the related industries.

  12. Analysis of status of radiation/radioisotopes utilization

    International Nuclear Information System (INIS)

    Park, Chan Hee; Lee, Seung Hyun; Kim, Na Kyung; Kim, Kon Wuk

    2017-01-01

    The use of radiation and radioisotopes in Korea has been increasing each year, and its impact on economy and industry is expected to be increasing progressively following the development of industrial technology and the expansion of their usage. To establish and supporting policies for industries using radiation and radioisotopes, it is necessary to check the status of related industries accurately, as well as to gather data required to establish plans for industrial development by studying both revenues and economic scale (contributing to revenue). o analyze the status of utilization, surveys were carried out on 6,621 organizations engaged in nuclear operations handling radiation and radioisotopes pursuant to the Nuclear Safety Act as of end 2014, on 33,471 medical institutions using radiation generators for medical and diagnostic purposes pursuant to the Medical Service Act, and on 2,218 organizations using radiation generators for animal diagnostics pursuant to the Veterinary License Act. he overall status of the domestic radiation market including the number of user organizations, that of employees, and the size of distributions (imports, productions, and exports) with which the scale of domestic radiation market can be judged showed a growth trend compared to the previous year, though the number of employees for radiation operation in industrial sector, research sector, education sector, military sector, and power plants (nuclear power plants) and the size of imports was reduced somewhat. t is expected that data acquired through periodic surveys on the status of utilization would be utilized practically in establishing governmental policies related to the promotion of usage of radiation and radioisotopes, and also be utilized widely in cultivating and developing the industry efficiently to invigorate the related industries

  13. Project and supply agreement. The text of the agreement of 15 January 1993 between the International Atomic Energy Agency and the Government of the Republic of Indonesia and the Government of the United States of America concerning the transfer of enriched uranium for the fabrication of targets for the production of radioisotopes for medical purposes

    International Nuclear Information System (INIS)

    1994-08-01

    The text of the Project and Supply Agreement, which was approved by the Agency's Board of Governors on 4 December 1992 and concluded on 15 January 1993 between the Agency and the Governments of the Republic of Indonesia and the United States of America for the transfer of enriched uranium for the fabrication of targets for the production of radioisotopes for medical purposes is reproduced herein for the information of all Members. The agreement entered into force on 15 January 1993, pursuant to Article XII.1

  14. Short-lived cyclotron-produced radioisotopes: Medi-Physics, Inc.'s commitment

    International Nuclear Information System (INIS)

    Kramer, H.H.

    1985-01-01

    Medi-Physics, Inc., is a major US supplier of short-lived cyclotron-produced radioisotopes for radiopharmaceuticals, as well as routinely producing and distributing the greatest number of 123 I radiopharmaceuticals. The present commercial production capacity for 123 I is more than ten times the theoretical need for existing procedures and is more than adequate for the research and development of new radiopharmaceuticals. However, production capacity is only one component of many that are required to supply a radioisotope for human use. These components are summarized in this paper

  15. NASA's Radioisotope Power Systems Program Status

    Science.gov (United States)

    Dudzinski, Leonard A.; Hamley, John A.; McCallum, Peter W.; Sutliff, Thomas J.; Zakrajsek, June F.

    2013-01-01

    NASA's Radioisotope Power Systems (RPS) Program began formal implementation in December 2010. The RPS Program's goal is to make available RPS for the exploration of the solar system in environments where conventional solar or chemical power generation is impractical or impossible to meet mission needs. To meet this goal, the RPS Program manages investments in RPS system development and RPS technologies. The current keystone of the RPS Program is the development of the Advanced Stirling Radioisotope Generator (ASRG). This generator will be about four times more efficient than the more traditional thermoelectric generators, while providing a similar amount of power. This paper provides the status of the RPS Program and its related projects. Opportunities for RPS generator development and targeted research into RPS component performance enhancements, as well as constraints dealing with the supply of radioisotope fuel, are also discussed in the context of the next ten years of planetary science mission plans.

  16. The Current Utilization and Future Demand of Radiopharmaceutical and Radioisotopes in Malaysia

    International Nuclear Information System (INIS)

    Ibrahim Ijang; Zakaria Ibrahim; Bohari Yaacob

    2013-01-01

    Radioisotope and pharmaceutical kits play an important role in nuclear medicine for non-invasive diagnosis and treatment of various cancers and cardiovascular disease. Our aim was to survey the current utilization and future demand of radiopharmaceuticals and radioisotopes in Malaysia. The survey methodology technique was done using questionnaire administration modes. The survey was done for four month duration from government hospitals that have nuclear medicine department. The most frequent pharmaceutical kits used in hospitals were Methylene Diphosphonic acid (MDP) for bone imaging and Diethylene Triamine Pantacetic acid (DTPA). Similarly radioisotopes widely used were Tc-99m and Iodine 131.Therefore if produced of Tc-99m by Nuclear Malaysia can improved in term of high quality products, Nuclear Malaysia could be the sole supplier of this product to hospitals in Malaysia. Similarly pharmaceutical kits especially MDP and DTPA, Nuclear Malaysia has the expertise and knowledge to supply these kits to the hospital. (author)

  17. Application of radioisotopes in the field of nuclear medicine

    International Nuclear Information System (INIS)

    Nayak, D.; Lahiri, S.

    1999-01-01

    A comprehensive review has been made to discuss the role of various radionuclides of lanthanide series elements in the field of nuclear medicine. The role of several pharmaceuticals labeled with radiolanthanides and used for investigative purposes like measurement of cerebral blood flow, bone density measurement, bone marrow imaging, etc., have been described. The role of lanthanide radionuclides in radiation synovectomy, radioimmunotherapy, etc., have also been discussed. Methods of preparation of some representative radiopharmaceuticals like 153 Sm-EDTMP, 153 Sm-HYP, have been presented. An outline on the production of carrier free radioisotopes of lanthanide series elements has been given. (author)

  18. Industrial application of radioisotopes in South Africa: a bibliographic review

    International Nuclear Information System (INIS)

    De Jesus, A.S.M.; Smith, S.W.; Van As, D.; De Wet, W.J.

    1985-01-01

    Since 1963 considerable strides have been made concerning the application of nuclear radiation, in most cases provided by radioisotopic sources, in the South African industry. South Africa has moved from a phase where the emphasis was on experimenting and learning to a phase where the technologies developed over the years are being put to work in a productive manner by exploiting them, largely complementary to other non-nuclear technologies. Classification in terms of application areas includes subjects such as process control, elemental analysis, industrial processes, mining exploration and prospecting, environmental applications and radiation processing

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-09-01

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

  20. Radioisotopes in non-destructive testing

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1976-12-01

    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)

  1. Industrial applications of radioisotope techniques in Poland

    International Nuclear Information System (INIS)

    Michalik, J.St.

    1985-01-01

    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)

  2. Radioisotopes present in building materials of workplaces

    Science.gov (United States)

    Del Claro, F.; Paschuk, S. A.; Corrêa, J. N.; Denyak, V.; Kappke, J.; Perna, A. F. N.; Martins, M. R.; Santos, T. O.; Rocha, Z.; Schelin, H. R.

    2017-11-01

    The isotope 222Rn is responsible for approximately half of the effective annual dose received by the world population. The decay products of 222Rn interacting with the cells of biological tissue of lungs have very high probability to induce cancer. The present survey was focused in the evaluation of activity concentration of 222Rn and other radioisotopes related to the building materials at workplaces at Curitiba - Paraná State. For this purpose, the instant radon detector AlphaGUARD (Saphymo GmbH) was used to measure the average concentrations of 222Rn in building materials, which were also submitted to gamma spectrometry analysis for qualitative and quantitative evaluation of the radionuclides present in samples of sand, mortar, blue crushed stone (Gneissic rock), red crushed stone (Granite), concrete and red bricks. The main radionuclides evaluated by gamma spectrometry in building material samples were 238U/226Ra, 232Th and 40K. These measurements were performed at the Laboratory of Applied Nuclear Physics of the Federal University of Technology - Paraná in collaboration with the Center of Nuclear Technology Development (CDTN - CNEN). The results of the survey present the concentration values of 222Rn related to construction materials in a range from 427±40.52 Bq/m³ to 2053±90.06 Bq/m³. The results of gamma spectroscopy analysis show that specific activity values for the mentioned isotopes are similar to the results indicated by the literature. Nevertheless, the present survey is showing the need of further studies and indicates that building materials can contribute significantly to indoor concentration of 222Rn.

  3. WITHDRAWN: Radioisotopes for metastatic bone pain.

    Science.gov (United States)

    Roqué I Figuls, Marta; Martinez-Zapata, Maria José; Scott-Brown, Martin; Alonso-Coello, Pablo

    2017-03-23

    This is an update of the review published in Issue 4, 2003. Bone metastasis cause severe pain as well as pathological fractures, hypercalcaemia and spinal cord compression. Treatment strategies currently available to relieve pain from bone metastases include analgesia, radiotherapy, surgery, chemotherapy, hormone therapy, radioisotopes and bisphosphonates. To determine efficacy and safety of radioisotopes in patients with bone metastases to improve metastatic pain, decrease number of complications due to bone metastases and improve patient survival. We sought randomised controlled trials (RCTs) in MEDLINE, EMBASE, CENTRAL, and the PaPaS Trials Register up to October 2010. Studies selected had metastatic bone pain as a major outcome after treatment with a radioisotope, compared with placebo or another radioisotope. We assessed the risk of bias of included studies by their sequence generation, allocation concealment, blinding of study participants, researchers and outcome assessors, and incomplete outcome data. Two review authors extracted data. We performed statistical analysis as an "available case" analysis, and calculated global estimates of effect using a random-effects model. We also performed an intention-to-treat (ITT) sensitivity analysis. This update includes 15 studies (1146 analyzed participants): four (325 participants) already included and 11 new (821 participants). Only three studies had a low risk of bias. We observed a small benefit of radioisotopes for complete relief (risk ratio (RR) 2.10, 95% CI 1.32 to 3.35; Number needed to treat to benefit (NNT) = 5) and complete/partial relief (RR 1.72, 95% CI 1.13 to 2.63; NNT = 4) in the short and medium term (eight studies, 499 participants). There is no conclusive evidence to demonstrate that radioisotopes modify the use of analgesia with respect to placebo. Leucocytopenia and thrombocytopenia are secondary effects significantly associated with the administration of radioisotopes (RR 5.03; 95% CI 1.35 to

  4. Utilization of radioisotopes in France, present and future

    International Nuclear Information System (INIS)

    Gauvenet, A.J.

    1976-01-01

    France is one of the countries having used radioisotopes very early. The first research reactor went critical in 1948, and has been used right from the start mainly to produce the radioisotopes for research and medicine. The growth in production was extremely fast, and the net receipts (excluding tax) amounted to F.52.3 million during 1974, of which F.20.9 million from export. The increase as compared with 1973 is 33%. The research and production facilities, which are concerned with medical applications, are in full expansion, Finally, the increasing use of trans-uranic elements, particularly of Pu-238 pacemakers, is noted. The uses of Cm-244 and Cf-252 are also growing. The problem at user level that undoubtedly requires the greatest attention is the regulations. The regulations on radioelements in France are reviewed in details on the following matters; poisonous substances, radioactive transport, waste, license for using artificial radioactive substances, etc. As the conclusion, the extremely ripid growth in the use of radioisotopes - mainly artificial ones - brought about the problems of adaptation with respect to the control and training regulations. One of the problems is obviously due to the fact that the personnel using such substances does not possess the specialization, training and managerial staff which marks the nuclear industry proper. It is therefore of prime significance to give unfailing attention to this use which is becoming the matter of major importance in France. The stress now placed on everything that concerns radiation has the great interest of forcing renewed awareness, thereby avoiding the degradation that the routine might bring. (Kobatake, H.)

  5. Radioisotopes and ionizing radiations in biological research

    International Nuclear Information System (INIS)

    1984-01-01

    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 [fr

  6. Radioisotope techniques used in breast cancer

    International Nuclear Information System (INIS)

    Auyong Tingkun

    2001-01-01

    Breast cancer is one of the commonest cancer in women. Treatment and prognosis of breast cancer depend very much on accurate diagnosis, staging and follow-up of patients. Recently, there are several radioisotope techniques developed and have great impact on management of breast cancer. These include scintimammography, sentinel lymph node detection and positron emission tomography. This article is to review these important techniques

  7. Radioisotopes and food preservation against insects

    International Nuclear Information System (INIS)

    Hachem Ahmad, M.S.

    1998-01-01

    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

  8. ILLUSTRATIONS OF RADIOISOTOPES--DEFINITIONS AND APPLICATIONS.

    Science.gov (United States)

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

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

  9. Radioisotopes in management of metastatic prostate cancer.

    Science.gov (United States)

    Raval, Amar; Dan, Tu D; Williams, Noelle L; Pridjian, Andrew; Den, Robert B

    2016-01-01

    Metastatic prostate cancer continues to be a leading cause of morbidity and mortality in men with prostate cancer. Over the last decade, the treatment landscape for patients with castrate-resistant disease has drastically changed, with several novel agents demonstrating an improvement in overall survival in large, multi-institutional randomized trials. Traditional treatment with radioisotopes has largely been in the palliative setting. However, the first in class radiopharmaceutical radium-223 has emerged as the only bone-directed treatment option demonstrating an improvement in overall survival. Medline publications from 1990 to 2016 were searched and reviewed to assess the use of currently approved radioisotopes in the management of prostate cancer including emerging data regarding integration with novel systemic therapies. New positron emission tomography-based radiotracers for advanced molecular imaging of prostate cancer were also queried. Radioisotopes play a crucial role in the diagnosis and treatment of prostate cancer in the definitive and metastatic setting. Molecular imaging of prostate cancer and theranostics are currently being investigated in the clinical arena. The use of modern radioisotopes in selected patients with mCRPC is associated with improvements in overall survival, pain control, and quality of life.

  10. Fuel selection for radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Menezes, A.

    1988-06-01

    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) [pt

  11. Application of artificial radioisotopes in hydrological studies

    International Nuclear Information System (INIS)

    Jacob, Noble; Shivanna, K.

    2009-01-01

    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)

  12. The industrial application of radioisotopes in Australia

    International Nuclear Information System (INIS)

    Easey, J.F.

    1987-01-01

    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. Reflections on the juridical implications of the medical use of radiations and radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Campos, Ana Celia P.P. [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Faculdade de Direito]. E-mails: anaceu2000@yahoo.com.br; Cuperschmid, Ethel Mizrahy [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Centro de Memoria da Medicina - CEMMOR]. E-mail: ethel.mizrahy@yahoo.com; Campos, Tarcisio P. Ribeiro de [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Programa de Pos-graduacao em Ciencias e Tecnicas Nucleares]. E-mail: campos@nuclear.ufmg.br

    2007-07-01

    The pacific use of radiation and radioisotopes for the society presents radiological risks, due its capacity to produce damage to environmental and human being, contrasting with its high economic and social benefits. In the face of the risk, juridical system leans over to reach the required regulations that implies in the balance between human and environmental security and the expected improvements of the medical nuclear techniques. The Brazilian Constitution of 1988 tries to provide the normalization for the application of the nuclear energy and its radioisotopes. However, target as a strategically technology and due to its expansion, its regulations still deserves analyses and reflections. The present paper starts from the Constitution presenting the references about the theme and analyzing it. It is addressed the principle of the objective civil responsibility making analyses on the use of radiations and radioisotope on the medicine. It addresses the role of federal autonomy related to the 'MCT - Ministerio de Ciencia e Tecnologia' with its accumulative functions in society, such as scientific and technologic development, education, and its own focalization. The recent opening of the monopoly for the production of radioisotopes for very short half-lives is also discussed. It makes a comparison between juridical aspects of Brazil with international system. The present article contributes to open same topics of discussions on the Brazilian juridical aspects involving radiations and radioisotopes application on medicine. (author)

  14. Contributions and Future of Radioisotopes in Medical, Industrial and Space Applications

    Science.gov (United States)

    Tingey, G. L.; Dix, G. P.; Wahlquist, E. J.

    1990-11-01

    There are 333 isotopes that have a half-life between 1 day and 100,000 years that have a wide variety of applications including public health, medicine,industrial technology, food technology and packaging, agriculture, energy supply, and national security. This paper provides an overview of some of the most extensive applications of radioisotopes including some observations of future uses. Examples are discussed that indicate that the use of radioisotopes is almost unlimited and will continue to grow. There is a growing need for future applications development and production. 12 refs., 1 tab. (BM)

  15. Contributions and future of radioisotopes in medical, industrial, and space applications

    Science.gov (United States)

    Tingey, G. L.; Dix, G. P.; Wahlquist, E. J.

    1990-11-01

    There are 333 isotopes that have a half-life between 1 day and 100,000 years that have a wide variety of applications including public health, medicine, industrial technology, food technology and packaging, agriculture, energy supply, and national security. This paper provides an overview of some of the most extensive applications of radioisotopes including some observations of future uses. Examples are discussed that indicate that the use of radioisotopes is almost unlimited and will continue to grow. There is a growing need for future applications development and production.

  16. Contributions and future of radioisotopes in medical, industrial and space applications

    International Nuclear Information System (INIS)

    Tingey, G.L.; Dix, G.P.; Wahlquist, E.J.

    1990-11-01

    There are 333 isotopes that have a half-life between 1 day and 100,000 years that have a wide variety of applications including public health, medicine,industrial technology, food technology and packaging, agriculture, energy supply, and national security. This paper provides an overview of some of the most extensive applications of radioisotopes including some observations of future uses. Examples are discussed that indicate that the use of radioisotopes is almost unlimited and will continue to grow. There is a growing need for future applications development and production. 12 refs., 1 tab. (BM)

  17. Analyses and quantitative determination of the strontium radioisotopes 89 and 90 in milk powder

    International Nuclear Information System (INIS)

    Jeanmaire, L.; Michon, G.

    1959-01-01

    The authors describe a procedure for the determination of the strontium radioisotopes 89 and 90. The concentration of strontium is made possible by the insolubility of its nitrate salt in strong nitric acid which allows the removal of greatest part of calcium. The purification is performed on a cation exchange column. The amount of radioisotope 90 is determined by means of its daughter product yttrium 90 necessary calibrations and computations are treated in special paragraphs. With regard to the reproducibility of the measurements, the fluctuations are less than 20 per cent. This seems satisfaction for such a technique which have great sensibility while being long and necessitative great carefulness. (author) [fr

  18. Facilities for Research and Development of Medical Radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

    2003-03-15

    This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value.

  19. Novel Radioisotope Applications in Industry Promoted by the IAEA

    International Nuclear Information System (INIS)

    Thereska, J.

    2001-01-01

    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 world-wide 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)

  20. Radioisotopes in Hydrology. Proceedings of a Symposium

    International Nuclear Information System (INIS)

    1963-01-01

    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

  1. The radioisotope complex project "RIC-80" at the Petersburg Nuclear Physics Institute

    Science.gov (United States)

    Panteleev, V. N.; Barzakh, A. E.; Batist, L. Kh.; Fedorov, D. V.; Ivanov, V. S.; Moroz, F. V.; Molkanov, P. L.; Orlov, S. Yu.; Volkov, Yu. M.

    2015-12-01

    The high current cyclotron C-80 capable of producing 40-80 MeV proton beams with a current of up to 200 μA has been constructed at Petersburg Nuclear Physics Institute. One of the main goals of the C-80 is the production of a wide spectrum of medical radionuclides for diagnostics and therapy. The project development of the radioisotope complex RIC-80 (radioisotopes at the cyclotron C-80) at the beam of C-80 has been completed. The RIC-80 complex is briefly discussed in this paper. The combination of the mass-separator with the target-ion source device, available at one of the new target stations for on-line or semi on-line production of a high purity separated radioisotopes, is explored in greater detail. The results of target and ion source tests for a mass-separator method for the production of high purity radioisotopes 82Sr and 223,224Ra are also presented.

  2. The radioisotope complex project “RIC-80” at the Petersburg Nuclear Physics Institute

    Energy Technology Data Exchange (ETDEWEB)

    Panteleev, V. N., E-mail: vnp@pnpi.spb.ru; Barzakh, A. E.; Batist, L. Kh.; Fedorov, D. V.; Ivanov, V. S.; Moroz, F. V.; Molkanov, P. L.; Orlov, S. Yu.; Volkov, Yu. M. [NRC “Kurchatov Institute” PNPI, 188300 Gatchina (Russian Federation)

    2015-12-15

    The high current cyclotron C-80 capable of producing 40-80 MeV proton beams with a current of up to 200 μA has been constructed at Petersburg Nuclear Physics Institute. One of the main goals of the C-80 is the production of a wide spectrum of medical radionuclides for diagnostics and therapy. The project development of the radioisotope complex RIC-80 (radioisotopes at the cyclotron C-80) at the beam of C-80 has been completed. The RIC-80 complex is briefly discussed in this paper. The combination of the mass-separator with the target-ion source device, available at one of the new target stations for on-line or semi on-line production of a high purity separated radioisotopes, is explored in greater detail. The results of target and ion source tests for a mass-separator method for the production of high purity radioisotopes {sup 82}Sr and {sup 223,224}Ra are also presented.

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

    International Nuclear Information System (INIS)

    Zhang Jiahua

    1987-01-01

    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

  4. The supply of medical radioisotopes - The Path to Reliability

    International Nuclear Information System (INIS)

    2011-01-01

    The reliable supply of molybdenum-99 ( 99 Mo) and its decay product, technetium-99m ( 99m Tc), is a vital component of modern medical diagnostic practices. Disruptions in the supply chain of these radioisotopes can delay or prevent important medical testing services. Unfortunately, supply reliability has declined over the past decade, due to unexpected or extended shutdowns at the few ageing, 99 Mo-producing, research reactors and processing facilities. These shutdowns have recently created global supply shortages. This report provides the findings and analysis of two years of extensive examination of the 99 Mo/ 99m Tc supply chain by the OECD/NEA High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR). It puts forth a comprehensive policy approach that would help ensure long-term supply security of 99 Mo/ 99m Tc, detailing the essential steps to be taken by governments, industry and the health community to address the vulnerabilities of the supply chain, including its economic structure. (authors)

  5. Application state of radioisotopes for medical use

    International Nuclear Information System (INIS)

    Nakajima, Tomoyoshi

    1979-01-01

    Application of unsealed radioisotopes as radiopharmaceuticals has been increasing year by year with the development of nuclear medicine. As for the radioisotopes for in vivo use which are internally administered and are detected by external scanning, the consumption of Tc-99 m drugs has increased rapidly. The sales of radiopharmaceuticals for in vivo use including 131 I, etc. amounted to four billion Yen in 1977. The consumption of the isotopes used in vitro for radioimmunoassay has made more rapid increase, and the sales of radiopharmaceuticals for in vitro use amounted to seven billion Yen in 1977. Radiopharmaceuticals have been used in 1,134 institutes all over Japan in 1978. 534 among them have applied radiopharmaceuticals to both in vivo and in vitro uses. Radioactive wastes have been increasing with the application of these unsealed radiopharmaceuticals, and their disposal method should be examined as there is a limit in their storage. (Kobatake, H.)

  6. Radioisotope thermionic converters for space applications

    International Nuclear Information System (INIS)

    Miskolczy, G.; Lieb, D.P.

    1990-01-01

    The recent history of radioisotope thermionics is reviewed, with emphasis on the U.S. programs, and the prospects for the future are assessed. In radioisotope thermionic converters the emitter heat is generated by the decay of a radioactive isotope. The thermionic converter emitter is mounted directly on a capsule containing the isotope. The rest of the capsule is generally insulated to reduce thermal loss. The development of isotope-fueled thermionic power systems for space application has been pursued since the late 1950's. The U.S. effort was concentrated on modular systems with alpha emitters as the isotope heat source. In the SNAP-13 program, the heat sources were Cerium isotopes and each module produced about 100 watts. The converters were planar diodes and the capsule was insulated with multi-foil insulation

  7. Advanced Stirling Radioisotope Generator Life Certification Plan

    Science.gov (United States)

    Rusick, Jeffrey J.; Zampino, Edward J.

    2013-01-01

    An Advanced Stirling Radioisotope Generator (ASRG) power supply is being developed by the Department of Energy (DOE) in partnership with NASA for potential future deep space science missions. Unlike previous radioisotope power supplies for space exploration, such as the passive MMRTG used recently on the Mars Curiosity rover, the ASRG is an active dynamic power supply with moving Stirling engine mechanical components. Due to the long life requirement of 17 years and the dynamic nature of the Stirling engine, the ASRG project faced some unique challenges trying to establish full confidence that the power supply will function reliably over the mission life. These unique challenges resulted in the development of an overall life certification plan that emphasizes long-term Stirling engine test and inspection when analysis is not practical. The ASRG life certification plan developed is described.

  8. Radioisotopes technology used to probe process problems

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    With the move to a greater degree of sophistication in industrial processes has come a need for improved measurement control methods as well as for efficient techniques for investigating process problems. Radioisotope-based technology, because of its unique benefits, is playing an increasing role in assisting mining and industry to satisfy the critical needs for efficiency in investigating process problems. More than twenty years of experience in the application of radioisotope and radiation techniques to the practical problems of industry has resulted in the Atomic Energy Corporation of South Africa having accumulated both extensive expertise and the facilities to carry out wide-ranging investigations, and to provide a large variety of cost effective services. Some of these are described. 2 figs., 2 ills

  9. Studies on computer analysis for radioisotope images

    International Nuclear Information System (INIS)

    Takizawa, Masaomi

    1977-01-01

    A hybrid type image file and processing system are devised by the author to file and the radioisotope image processing with analog display. This system has some functions as follows; Ten thousand images can be stored in 60 feets length video-tape-recorder (VTR) tape. Maximum of an image on the VTR tape is within 15 sec. An image display enabled by the analog memory, which has brightness more than 15 gray levels. By using the analog memories, effective image processing can be done by the small computer. Many signal sources can be inputted into the hybrid system. This system can be applied many fields to both routine works and multi-purpose radioisotope image processing. (auth.)

  10. Development of radioisotope labeled polymeric carriers

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-04-01

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

  11. Radioisotopes for nuclear medicine: the future

    International Nuclear Information System (INIS)

    Carr, S.W.

    1998-01-01

    Full text: Nuclear medicine occupies an important niche in the spectrum of medical capability. Since its initial application on a routine basis over 30 years ago its importance has continued to grow. For example, it is expected that over 430,000 Australians will have a nuclear medicine procedure in 1998. Current procedures using nuclear medicine are mainly concerned with diagnosis of oncology, cardiology and neurology. The main radioisotope used in nuclear medicine is Tc 99m, which is produced by a 'so called' Mo-Tc 99m generator. Other isotopes which currently find routine use are Ga-67, Th-201 and I-131. The selective uptakes by particular organs or structures is facilitated by the use of 'cold kits' which after the chemistry of the radioisotope many of the recent advances have been concerned with increasing the selectivity for a particular organ structure. Several of these new agents show increased selectivity using antibody a peptide recognition units

  12. Utilization of radioisotopes in the agriculture

    International Nuclear Information System (INIS)

    Cerri, C.C.

    1987-01-01

    Some aspects of radioisotopes utilization in the agriculture, such as, the use of gamma radiation for genetic improvement of plants; the use of C 14 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.) [pt

  13. Visualization of Radioisotope Detectability Over Time.

    Energy Technology Data Exchange (ETDEWEB)

    Huynh, Brady [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-02-01

    A radioactive isotope is an atom that has an unstable nucleus. The isotope can undergo radioactive decay, the process in which excessive nuclear energy is emitted from the nucleus in many different forms, such as gamma radiation, alpha particles, or beta particles. The important thing to note is that these emissions act as a signature for the isotope. Each radioisotope has a particular emission spectrum, emitting radiation at different energies and at different rates.

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

    International Nuclear Information System (INIS)

    Hardy, C.J.

    1987-01-01

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

  15. Steps of radioisotope separation in Japan

    International Nuclear Information System (INIS)

    Nakane, Ryohei; Kitamoto, Asashi; Shimizu, Masami

    1998-03-01

    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.)

  16. Medical Radioisotope Scanning. Proceedings of a Seminar

    International Nuclear Information System (INIS)

    1959-01-01

    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.

  17. Nuclear energy in the service of biomedicine: the U.S. Atomic Energy Commission's radioisotope program, 1946-1950.

    Science.gov (United States)

    Creager, Angela N H

    2006-01-01

    The widespread adoption of radioisotopes as tools in biomedical research and therapy became one of the major consequences of the "physicists' war" for postwar life science. Scientists in the Manhattan Project, as part of their efforts to advocate for civilian uses of atomic energy after the war, proposed using infrastructure from the wartime bomb project to develop a government-run radioisotope distribution program. After the Atomic Energy Bill was passed and before the Atomic Energy Commission (AEC) was formally established, the Manhattan Project began shipping isotopes from Oak Ridge. Scientists and physicians put these reactor-produced isotopes to many of the same uses that had been pioneered with cyclotron-generated radioisotopes in the 1930s and early 1940s. The majority of early AEC shipments were radioiodine and radiophosphorus, employed to evaluate thyroid function, diagnose medical disorders, and irradiate tumors. Both researchers and politicians lauded radioisotopes publicly for their potential in curing diseases, particularly cancer. However, isotopes proved less successful than anticipated in treating cancer and more successful in medical diagnostics. On the research side, reactor-generated radioisotopes equipped biologists with new tools to trace molecular transformations from metabolic pathways to ecosystems. The U.S. government's production and promotion of isotopes stimulated their consumption by scientists and physicians (both domestic and abroad), such that in the postwar period isotopes became routine elements of laboratory and clinical use. In the early postwar years, radioisotopes signified the government's commitment to harness the atom for peace, particularly through contributions to biology, medicine, and agriculture.

  18. Advanced Stirling Convertor Development for NASA Radioisotope Power Systems

    Science.gov (United States)

    Wong, Wayne A.; Wilson, Scott D.; Collins, Josh

    2015-01-01

    Sunpower Inc.'s Advanced Stirling Convertor (ASC) initiated development under contract to the NASA Glenn Research Center and after a series of successful demonstrations, the ASC began transitioning from a technology development project to a flight development project. The ASC has very high power conversion efficiency making it attractive for future Radioisotope Power Systems (RPS) in order to make best use of the low plutonium-238 fuel inventory in the United States. In recent years, the ASC became part of the NASA and Department of Energy (DOE) Advanced Stirling Radioisotope Generator (ASRG) Integrated Project. Sunpower held two parallel contracts to produce ASCs, one with the DOE and Lockheed Martin to produce the ASC-F flight convertors, and one with NASA Glenn for the production of ASC-E3 engineering units, the initial units of which served as production pathfinders. The integrated ASC technical team successfully overcame various technical challenges that led to the completion and delivery of the first two pairs of flightlike ASC-E3 by 2013. However, in late fall 2013, the DOE initiated termination of the Lockheed Martin ASRG flight development contract driven primarily by budget constraints. NASA continues to recognize the importance of high-efficiency ASC power conversion for RPS and continues investment in the technology including the continuation of ASC-E3 production at Sunpower and the assembly of the ASRG Engineering Unit #2. This paper provides a summary of ASC technical accomplishments, overview of tests at Glenn, plans for continued ASC production at Sunpower, and status of Stirling technology development.

  19. The Radioisotope Industry - Canadian Experience

    International Nuclear Information System (INIS)

    Evans, D. J. R.

    1987-01-01

    Canada is the world's largest producer, while the Canadian share of total cyclotron isotope production is very much smaller. This is a direct reflection of the country's nuclear history. The NRC reactor, which went critical in 1947, was at that time the world's highest flux nuclear reactor. NRC, which followed in 1956, gave access to even higher fluxes and irradiation volumes. Isotope production in Canada began almost coincidentally with the start-up of NRC and I-131 was exported to the United Stated in 1948, followed by C-14 before 1950. The above specific isotope applications, together with the earlier commentary on the overall Canadian historical experience clearly indicates the value of an indigenous isotope industry in Canada's case. It should be noted, of course, that the Canadian domestic applications base also involves all the other technological areas covered by other speakers at this Conference. While Canada is unique in that domestic self-sufficiency has led to an even more important export industry, there is no doubt that the development of domestic self-reliance in the isotope applications area is in its own right a valuable off-shoot of any country's nuclear R and D and power programs

  20. Establishment of regulation for managing the spent radioisotopes

    International Nuclear Information System (INIS)

    Li, K.K.

    1995-01-01

    Along with the increasing finding of the radiation contaminated residential buildings and roads in Taiwan, the appropriate management of the radioisotopes became popular issues recently among the public. This paper described the current situation and inventory of the radioisotopes with traceable records. The author addressed the importance of integrating various regulations to manage the radioisotope during its entire life cycle. A new fee-collecting system was also proposed to implement the generator-pays principle

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

    International Nuclear Information System (INIS)

    1983-04-01

    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)

  2. Efficient, Long-Lived Radioisotope Power Generator, Phase I

    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...

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

    International Nuclear Information System (INIS)

    1984-01-01

    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.)

  4. Vitrified chemically bonded phosphate ceramics for immobilization of radioisotopes

    Science.gov (United States)

    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. Production of Actinium-225 via High Energy Proton Induced Spallation of Thorium-232

    Energy Technology Data Exchange (ETDEWEB)

    Harvey, James T.; Nolen, Jerry; Vandergrift, George; Gomes, Itacil; Kroc, Tom; Horwitz, Phil; McAlister, Dan; Bowers, Del; Sullivan, Vivian; Greene, John

    2011-12-30

    The science of cancer research is currently expanding its use of alpha particle emitting radioisotopes. Coupled with the discovery and proliferation of molecular species that seek out and attach to tumors, new therapy and diagnostics are being developed to enhance the treatment of cancer and other diseases. This latest technology is commonly referred to as Alpha Immunotherapy (AIT). Actinium-225/Bismuth-213 is a parent/daughter alpha-emitting radioisotope pair that is highly sought after because of the potential for treating numerous diseases and its ability to be chemically compatible with many known and widely used carrier molecules (such as monoclonal antibodies and proteins/peptides). Unfortunately, the worldwide supply of actinium-225 is limited to about 1,000mCi annually and most of that is currently spoken for, thus limiting the ability of this radioisotope pair to enter into research and subsequently clinical trials. The route proposed herein utilizes high energy protons to produce actinium-225 via spallation of a thorium-232 target. As part of previous R and D efforts carried out at Argonne National Laboratory recently in support of the proposed US FRIB facility, it was shown that a very effective production mechanism for actinium-225 is spallation of thorium-232 by high energy proton beams. The base-line simulation for the production rate of actinium-225 by this reaction mechanism is 8E12 atoms per second at 200 MeV proton beam energy with 50 g/cm2 thorium target and 100 kW beam power. An irradiation of one actinium-225 half-life (10 days) produces {approx}100 Ci of actinium-225. For a given beam current the reaction cross section increases slightly with energy to about 400 MeV and then decreases slightly for beam energies in the several GeV regime. The object of this effort is to refine the simulations at proton beam energies of 400 MeV and above up to about 8 GeV. Once completed, the simulations will be experimentally verified using 400 MeV and 8 Ge

  6. Radioisotope Thermoelectric Generator Transport Trailer System

    International Nuclear Information System (INIS)

    Ard, K.E.; King, D.A.; Leigh, H.; Satoh, J.A.

    1994-01-01

    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. 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)

  8. Digital radioisotope moisture-density meter

    International Nuclear Information System (INIS)

    Bychvarov, N.; Vankov, I.; Dimitrov, L.

    1982-01-01

    The primary information from the detectors of a combined radioisotope moisture-density meter is obtained as pulses, their counting rate being functionally dependent on the humidity per unit volume and the wet density. However, most practical cases demand information on the moisture per unit weight and the mass density of the dry skeleton. The paper describes how the proposed electronic circuit processes the input primary information to obtain the moisture in weight % and the mass density of the dry skeleton in g/cm 3 . (authors)

  9. Preliminary estimation of the dose rates of the operation room of the RPR radioisotope cell

    International Nuclear Information System (INIS)

    Rocha, A.C.S.; Silva, J.J.G.; Pina, J.L.S. de; Fajardo, P.W.

    1986-07-01

    During the preliminary studies, about the installations layout of a radioisotope production reactor, the possibility of construction of a radioisotope cell at the reactor building has been investigated. The decisions about that construction has considered mainly the level of the radiation dose over the cell operator. The dose rate has been calculated based on: neutron flux and gamma radiation from fission products and activation materials inside the reactor; volatile fission products such as noble gases and iodides; tritium form ternary fission. The objective was calculate the radiation dose over the cell operator during a journey of 8 hours of work per day. For those calculations some data have been obtained from the Angra-3 reactor. (author)

  10. Report of Radioisotope Inspection Technical Committee

    International Nuclear Information System (INIS)

    Otani, H.

    1980-01-01

    For the purpose of unifying the method of performance test for the routine management of the performance of RI equipments, the check-up of performance at the time of purchasing the equipments or research works, the Committee has continued the investigation on the method of performance test on RI equipments. Now, the definite plans have been decided regarding the method of performance test on radioisotope monitoring instruments and the measuring instruments for RI samples, therefore they are reported hereinafter. As for the radioisotope monitoring instruments, Curie meter, area monitor, water monitor, gas monitor and hand, foot and cloth monitor were taken up, and the items of inspection, the purposes, the testing methods, the expression of measured results and their evaluation were discussed. The accuracy of measurement of absolute radio-activity is important in Curie meter, the stability of continuous monitoring is important in general monitors, and the limit of measurement is important in the hand, foot and cloth monitor. As for the measuring instruments for radioactive materials, the efficiency of counting, linearity and stability were taken up as the items of performance test, and other matters to which attention should be paid were added. These were described, dividing into well type scintillation counter and liquid scintillation counter. (Kako, I.)

  11. Drying equipment for radioisotope-treated animals

    International Nuclear Information System (INIS)

    Fujikake, Toshio; Ohmori, Akira; Takada, Yukio; Nakano, Shozoh; Tamai, Shinsuke.

    1978-01-01

    The animal experiments using radioisotopes have been carried out over wide fields, accordingly, the number of radioisotope-contaminated animal cadavers has been increasing rapidly. It was decided that each establishment employing radioiosotopes dries those cadavers to such state as to be able to burn up with the device in Japan Atomic Energy Research Institute. The animal waste-drying device meeting the above mentioned purpose was developed by the joint work of Fuji Electric General Devices Co. and Fuji Electric Co. It is known as the micro-wave drying device for animals (its nickname is Microdry). This device dehydrates at high speed by micro-wave drying method. By using along with a moisture detector, it gives the drying state as requested regardless of the water content of each animal. The animal wastes after perfect dehydration are reduced to the weight of about one-third, and the dried animal cadavers can be preserved for a long time at room temperature because of the sterilizing effect of the micro-wave heating. This device is noted for its excellent safeness, simple operation, and low treatment cost. It is anticipated that it can be further applied to other fields such as excreta, breeding materials, etc. (Kobatake, H.)

  12. Safe Handling of Radioisotopes. Medical Addendum

    International Nuclear Information System (INIS)

    Hercik, F.; Jammet, H.

    1960-01-01

    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.

  13. Safe Handling of Radioisotopes. Health Physics Addendum

    International Nuclear Information System (INIS)

    Appleton, G.J.; Krishnamoorthy, P.N.

    1960-01-01

    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.

  14. The use of radioisotope tracers in the metallurgical industries

    International Nuclear Information System (INIS)

    Easey, J.F.

    1987-01-01

    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)

  15. RADIOISOTOPE EXPERIMENTS IN HIGH SCHOOL BIOLOGY, AN ANNOTATED SELECTED BIBLIOGRAPHY.

    Science.gov (United States)

    HURLBURT, EVELYN M.

    SELECTED REFERENCES ON THE USE OF RADIOISOTOPES IN BIOLOGY ARE CONTAINED IN THIS ANNOTATED BIBLIOGRAPHY FOR SECONDARY SCHOOL STUDENTS. MATERIALS INCLUDED WERE PUBLISHED AFTER 1960 AND DEAL WITH THE PROPERTIES OF RADIATION, SIMPLE RADIATION DETECTION PROCEDURES, AND TECHNIQUES FOR USING RADIOISOTOPES EXPERIMENTALLY. THE REFERENCES ARE LISTED IN…

  16. Application of radioisotope technique for investigation of pumps seals

    International Nuclear Information System (INIS)

    Antoszewski, B.; Zorawska, A.

    1988-01-01

    Radioisotope method of measuring the wear of rings of the face mechanical seals, bush in soft seals, and leakage in double mechanical seals is described. The examples are given. It is found that radioisotope technique can be used for investigation of the seals. (author)

  17. Applying advanced digital signal processing techniques in industrial radioisotopes applications

    International Nuclear Information System (INIS)

    Mahmoud, H.K.A.E.

    2012-01-01

    Radioisotopes can be used to obtain signals or images in order to recognize the information inside the industrial systems. The main problems of using these techniques are the difficulty of identification of the obtained signals or images and the requirement of skilled experts for the interpretation process of the output data of these applications. Now, the interpretation of the output data from these applications is performed mainly manually, depending heavily on the skills and the experience of trained operators. This process is time consuming and the results typically suffer from inconsistency and errors. The objective of the thesis is to apply the advanced digital signal processing techniques for improving the treatment and the interpretation of the output data from the different Industrial Radioisotopes Applications (IRA). This thesis focuses on two IRA; the Residence Time Distribution (RTD) measurement and the defect inspection of welded pipes using a gamma source (gamma radiography). In RTD measurement application, this thesis presents methods for signal pre-processing and modeling of the RTD signals. Simulation results have been presented for two case studies. The first case study is a laboratory experiment for measuring the RTD in a water flow rig. The second case study is an experiment for measuring the RTD in a phosphate production unit. The thesis proposes an approach for RTD signal identification in the presence of noise. In this approach, after signal processing, the Mel Frequency Cepstral Coefficients (MFCCs) and polynomial coefficients are extracted from the processed signal or from one of its transforms. The Discrete Wavelet Transform (DWT), Discrete Cosine Transform (DCT), and Discrete Sine Transform (DST) have been tested and compared for efficient feature extraction. Neural networks have been used for matching of the extracted features. Furthermore, the Power Density Spectrum (PDS) of the RTD signal has been also used instead of the discrete

  18. Assessment of radioisotope heaters for remote terrestrial applications

    International Nuclear Information System (INIS)

    Uherka, K.L.

    1987-05-01

    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

  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)

    1981-01-01

    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 A 1 and A 2 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 cm 2 for the radioisotopes emitting alpha-ray, and 1/10,000 micro-curie per cm 2 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 A 2 value for BM type transported goods and 1/1,000 of A 2 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. Gas chemical investigation of hafnium and zirconium complexes with hexafluoroacetylacetone using preseparated short-lived radioisotopes

    OpenAIRE

    Düllmann, Ch. E.; Gregorich, K. E.; Pang, G. K.; Dragojevic, I.; Eichler, Robert; Folden III, C.M.; Garcia, M. A.; Gates, J. M.; Hoffman, D.C.; Nelson, S. L.; Sudowe, Ralf; Nitsche, Heino

    2017-01-01

    Volatile metal complexes of the group 4 elements Zr and Hf with hexafluoroacetylacetonate (hfa) have been studied using short-lived radioisotopes of the metals. The new technique of physical preseparation has been employed where reaction products from heavy-ion induced fusion reactions are isolated in a physical recoil separator - the Berkeley Gas-filled Separator in our work - and made available for chemistry experiments. Formation and decomposition of M(hfa)4 (M=Zr, Hf) has been observed an...

  2. Radioisotopes for the treatment of cancer

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1983-01-01

    Radiotherapy can be, in some favourable cases, entirely successful in the treatment of cancer. One method of treatment - teletherapy - is to implant a compact source of radiation on or within the tumour. Artificial radioisotopes are used as sources of radiation for this purpose. Several sources may be combined so that the resultant radiation field is matched to the shape and size of the tumour. An important example of such treatment is the radiotherapy of cancer of uterus cervix, which commonly occurs in young women. Recently, a loading technique has been developed which gives the therapist very little exposure to radiation. The feasibility of this technique in developing countries is being jointly studied by IAEA and WHO

  3. 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.

  4. Induced radioisotopes in a linac treatment hall.

    Science.gov (United States)

    Vega-Carrillo, Héctor René; de Leon-Martinez, Héctor Asael; Rivera-Perez, Esteban; Luis Benites-Rengifo, Jorge; Gallego, Eduardo; Lorente, Alfredo

    2015-08-01

    When linacs operate above 8MV 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. Copyright © 2015 Elsevier Ltd. All rights reserved.

  5. Development of leakage monitoring system using radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. C.; Lee, D. S. [Seoil College, Seoul (Korea); Cho, Y. S. [Konyang University, Nonsan (Korea); Shin, S. K. [Sungkyunkwan Univ., Seoul (Korea)

    2000-04-01

    This study is to development the potable neutron back-scattering gauge for leakage and detecting liquid interface of an oil and liquid tank, using a radioisotopes. For this purpose, small sized, light weight potable gauge is to be designed as to develope neutron shielding mechanism, low power supply circuit, high voltage circuit, measurement circuit, and operating handle etc. The user will be able to set the duration of the time interval, the scale, the high voltage, the threshold, the channel window, the selection whether the data storage or not, the selection whether the scale, high voltage, threshold and window fix or not at any time. The counted pulse will be displayed with the numerical value and the line bar. The gauge will be able to connect to an IBM compatible PC via a serial port, power will be supplied by internal battery. 9 refs., 28 figs., 10 tabs. (Author)

  6. Radioisotope heaters for spacecraft life support systems

    International Nuclear Information System (INIS)

    Shivers, R.W.; Murray, R.W.

    1974-01-01

    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.)

  7. Radioisotope scanning in inflammatory muscle disease

    Energy Technology Data Exchange (ETDEWEB)

    Brown, M.B.; Swift, T.R.; Spies, S.M.

    1976-06-01

    Fourteen whole-body rectilinear bone scans using technetium 99m-polyphosphate were done in nine patients with well-documented inflammatory myopathy (either polymyositis or dermatomyositis). In all nine patients the scans showed evidence of increased muscle labeling. Muscle uptake was markedly increased in one patient, moderately increased in two patients, and minimally increased in six patients. The degree of muscle labeling correlated with the severity of the muscle weakness at the time the scan was done. In four patients, who received high-dose corticosteroid treatment, muscle uptake was decreased following therapy. These findings suggest that radioisotope scanning may be useful in the diagnosis and management of patients with inflammatory muscle diseases.

  8. Radioisotopes for Therapy and Development of Therapeutic Radiopharmaceuticals

    International Nuclear Information System (INIS)

    Mikolajczak, R.

    2009-01-01

    In recent years there has been a rapid expansion in the use of radionuclides for therapeutic purposes. The potential usefulness of a particular radioisotope depends on many factors: physical data (half-life, energy of beta-particles, gamma ray emissions), production method including separation, labeling and targeting properties of a radionuclide carrier molecule. Depending on the production mode, the radioisotope can be obtained in the pure form (without any carrier) or in the form of the mixture of isotopes, containing also the stable forms. The specific activity is than defined as radioactivity of a certain radioisotope in this mixture. Several beta-emitting radionuclides for targeted radionuclide therapy can be produced in the nuclear reactors, including generator systems, and the list of other potentially useful isotopes is not yet closed. Among the radionuclides used for cancer therapy, 131 I, 90 Y, 188 Re, 166 Ho and 153 Sm have found applications in a number of clinical procedures and have been used for cancer therapy, bone pain palliation, radiosynovectomy, intravascular radiation therapy and other disorders. Extensive research in the field of radiopharmaceuticals and nuclear medicine practices have lead to the identification of other radionuclides including 177 Lu, 161 Tb, 67 Cu, 47 Sc with promising radionuclide physical and chemical properties, which still need to be explored. The latter two are of interest due to their positron emitting 'twins' i.e. 64 Cu and 44 Sc, which can be used for diagnostic imaging and therapy follow up using the same carrier molecules. On the other hand various techniques have been developed in order to improve the therapeutic effect such as the isotope cocktail approach, loco-regional administration, pre-targeting or combination with chemotherapy, providing new therapy options. The most popular in last years were carrier-free 90 Y and 177L u as well as carrier-added 177 Lu used for labeling of peptides specific to somatostatin

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

    International Nuclear Information System (INIS)

    Ramamoorthy, N.; Haji-Saeid, M.

    2004-01-01

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

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

    International Nuclear Information System (INIS)

    Ramamoorthy, N.; Haji-Saeid, M.

    2004-01-01

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

  11. Utilization of radioisotopes and irradiation in crop protection research

    International Nuclear Information System (INIS)

    Ong, S.H.

    1981-01-01

    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)

  12. Life atomic a history of radioisotopes in science and medicine

    CERN Document Server

    Creager, Angela N H

    2013-01-01

    After World War II, the US Atomic Energy Commission (AEC) began mass-producing radioisotopes, sending out nearly 64,000 shipments of radioactive materials to scientists and physicians by 1955. Even as the atomic bomb became the focus of Cold War anxiety, radioisotopes represented the government's efforts to harness the power of the atom for peace-advancing medicine, domestic energy, and foreign relations.             In Life Atomic, Angela N. H. Creager tells the story of how these radioisotopes, which were simultaneously scientific tools and political icons, transformed biomedicine and ecolog

  13. NASA Glenn Research Center Support of the Advanced Stirling Radioisotope Generator Project

    Science.gov (United States)

    Wilson, Scott D.; Wong, Wayne A.

    2015-01-01

    A high-efficiency radioisotope power system was being developed for long-duration NASA space science missions. The U.S. Department of Energy (DOE) managed a flight contract with Lockheed Martin Space Systems Company to build Advanced Stirling Radioisotope Generators (ASRGs), with support from NASA Glenn Research Center. DOE initiated termination of that contract in late 2013, primarily due to budget constraints. Sunpower, Inc., held two parallel contracts to produce Advanced Stirling Convertors (ASCs), one with Lockheed Martin to produce ASC-F flight units, and one with Glenn for the production of ASC-E3 engineering unit "pathfinders" that are built to the flight design. In support of those contracts, Glenn provided testing, materials expertise, Government-furnished equipment, inspection capabilities, and related data products to Lockheed Martin and Sunpower. The technical support included material evaluations, component tests, convertor characterization, and technology transfer. Material evaluations and component tests were performed on various ASC components in order to assess potential life-limiting mechanisms and provide data for reliability models. Convertor level tests were conducted to characterize performance under operating conditions that are representative of various mission conditions. Despite termination of the ASRG flight development contract, NASA continues to recognize the importance of high-efficiency ASC power conversion for Radioisotope Power Systems (RPS) and continues investment in the technology, including the continuation of the ASC-E3 contract. This paper describes key Government support for the ASRG project and future tests to be used to provide data for ongoing reliability assessments.

  14. Radioisotope Power Systems Reference Book for Mission Designers and Planners

    Science.gov (United States)

    Lee, Young; Bairstow, Brian

    2015-01-01

    The RPS Program's Program Planning and Assessment (PPA) Office commissioned the Mission Analysis team to develop the Radioisotope Power Systems (RPS) Reference Book for Mission Planners and Designers to define a baseline of RPS technology capabilities with specific emphasis on performance parameters and technology readiness. The main objective of this book is to provide RPS technology information that could be utilized by future mission concept studies and concurrent engineering practices. A progress summary from the major branches of RPS technology research provides mission analysis teams with a vital tool for assessing the RPS trade space, and provides concurrent engineering centers with a consistent set of guidelines for RPS performance characteristics. This book will be iterated when substantial new information becomes available to ensure continued relevance, serving as one of the cornerstone products of the RPS PPA Office. This book updates the original 2011 internal document, using data from the relevant publicly released RPS technology references and consultations with RPS technologists. Each performance parameter and RPS product subsection has been reviewed and cleared by at least one subject matter representative. A virtual workshop was held to reach consensus on the scope and contents of the book, and the definitions and assumptions that should be used. The subject matter experts then reviewed and updated the appropriate sections of the book. The RPS Mission Analysis Team then performed further updates and crosschecked the book for consistency. Finally, a second virtual workshop was held to ensure all subject matter experts and stakeholders concurred on the contents.

  15. Experimental studies of the medical radioisotopes production in neutron spectra generated by 660 MeV protons and 1-8 GeV deuterons in massive uranium target

    Science.gov (United States)

    Zhadan, A.; Sotnikov, V.; Adam, J.; Solnyshkin, A.; Tyutyunnikov, S.; Voronko, V.; Zhivkov, P.; Zavorka, L.

    2017-06-01

    The possibility of medical radionuclide 64,67Cu production in spallation neutron spectrum induced by proton and deuteron beams has been studied. Experiments were performed on a massive natural uranium target at the accelerators Phasotron and Nuclotron JINR, Dubna. The main disadvantage of this method is a high 64Cu/67Cu ratio in the final product at EOB. Significantly reduce 64Cu/67Cu ratio is only possible if you use zinc target enriched with 68Zn or 67Zn. The MCNPX simulation of 67,64Cu production and definition of the theoretical limit of the specific activity of 67,64Cu by irradiation of natural zinc and zinc enriched by the 68 isotope were performed. The neutron flux density shouldnot be less than 5.1013 n/cm2/s if we want to obtain high specific activity (>200 GBq/mg) of 67Cu.

  16. Advanced Radiative Emitters for Radioisotope Thermophotovoltaic Power Systems, Phase I

    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 performance,...

  17. Advanced Radiative Emitters for Radioisotope Thermophotovoltaic Power Systems, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Radioisotope Power Systems (RPS) are critical for future space and planetary exploration missions. Small improvements in the RPS performance, weight, size, and/or...

  18. Thermal Model Predictions of Advanced Stirling Radioisotope Generator Performance

    Science.gov (United States)

    Wang, Xiao-Yen J.; Fabanich, William Anthony; Schmitz, Paul C.

    2014-01-01

    This presentation describes the capabilities of three-dimensional thermal power model of advanced stirling radioisotope generator (ASRG). The performance of the ASRG is presented for different scenario, such as Venus flyby with or without the auxiliary cooling system.

  19. Variable Conductance Heat Pipes for Radioisotope Stirling Systems, Phase I

    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...

  20. Short course on the use of radioisotopes in agriculture

    International Nuclear Information System (INIS)

    1981-01-01

    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

  1. Organic synthesis with short-lived positron-emitting radioisotopes

    International Nuclear Information System (INIS)

    Pike, V.W.

    1988-01-01

    Chemistry with short-lived positron-emitting radioisotopes of the non-metals, principally 11 C, 13 N and 18 F, has burgeoned over the last decade. This has been almost entirely because of the emergence of positron emission tomography (PET) as a powerful non-invasive technique for investigating pathophysiology in living man. PET is essentially an external technique for the rapid serial reconstruction of the spatial distribution of any positron-emitting radioisotope that has been administered in vivo. Such a distribution is primarily governed by the chemical form in which the positron-emitting radioisotope is incorporated, and importantly for clinical research, is often perturbed by physical, biological or clinical factors. Judicious choice of the chemical form enables specific biological information to be obtained. For example, the labelling of glucose with a positron-emitting radioisotope could be expected to provide a radiopharmaceutical for the study of glucose utilisation in both health and disease. (author)

  2. Radioisotope Applications and the Evolution of the Techniques

    International Nuclear Information System (INIS)

    Rueda, C.

    2006-01-01

    A time of commemoration like the present is ideal for making and analysis of radioisotope applications and the evolution which the techniques employed in their use have undergone over the last 25 years. This article analyses the different practices using radioisotopes highlighting those which re no longer used, those that have been progressively abandoned and those which have been emerging during these past few years. The article also indicates when-ever possible the reason for the change and their associated advantages. (Author)

  3. Evaluation of processing methods for static radioisotope scan images

    International Nuclear Information System (INIS)

    Oakberg, J.A.

    1976-12-01

    Radioisotope scanning in the field of nuclear medicine provides a method for the mapping of a radioactive drug in the human body to produce maps (images) which prove useful in detecting abnormalities in vital organs. At best, radioisotope scanning methods produce images with poor counting statistics. One solution to improving the body scan images is using dedicated small computers with appropriate software to process the scan data. Eleven methods for processing image data are compared

  4. Strategy for securing the national supply of radioisotopes

    International Nuclear Information System (INIS)

    Wang Yongxian

    2013-01-01

    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 99m Tc and the most of medical radioisotopes of clinical importance. Results: The quality of 99m Tc produced by cyclotron, such as nuclide purity, specific activity and nonradioisotope impurities, has reached and/or exceeded that eluted from 99 Mo/ 99m Tc 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)

  5. Country report: Serbia. Development, Preparing and Quality Assurance of Radiopharmaceuticals Based on 188Re and 90Y for Radionuclide Therapy: The Possibilities for their Production in Laboratory for Radioisotopes, Ins «Vinča»

    International Nuclear Information System (INIS)

    Djokić, Divna

    2010-01-01

    The main object of the research planed for this project was to optimize the procedures for the 90 Y and 188 Re labelling of different compounds as well as their in vitro and in vivo evaluation. The work has been involved setting up the facilities, standardization of preparing protocols, and improving existing quality assurance/quality control (QA/QC) procedures in order to supply reliable products to the national nuclear medicine community

  6. 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.

  7. Treatment of animal wastes contaminated with radioisotopes

    International Nuclear Information System (INIS)

    Morikawa, Naotake

    1979-01-01

    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.)

  8. Safe Handling of Radioisotopes. 1973 Edition

    International Nuclear Information System (INIS)

    1973-01-01

    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.

  9. Versatile PC-logger for radioisotope measurements

    International Nuclear Information System (INIS)

    Furman, L.; Petryka, L.; Przewlocki, K.; Stegowski, Z.; Wierzbicki, A.

    1998-01-01

    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)

  10. Radioisotope-powered cardiac pacemaker program. Clinical studies of the nuclear pacemaker model NU-5. Final report

    International Nuclear Information System (INIS)

    1980-06-01

    Beginning in February, 1970, the Nuclear Materials and Equipment Corporation (NUMEC) undertook a program to design, develop and manufacture a radioisotope powered cardiac pacemaker system. The scope of technical work was specified to be: establish system, component, and process cost reduction goals using the prototype Radioisotope Powered Cardiac Pacemaker (RCP) design and develop production techniques to achieve these cost reduction objectives; fabricate radioisotope powered fueled prototype cardiac pacemakers (RCP's) on a pilot production basis; conduct liaison with a Government-designated fueling facility for purposes of defining fueling requirements, fabrication and encapsulation procedures, safety design criteria and quality control and inspection requirements; develop and implement Quality Assurance and Reliability Programs; conduct performance, acceptance, lifetime and reliability tests of fueled RCP's in the laboratory; conduct liaison with the National Institutes of Health and with Government specified medical research institutions selected for the purpose of undertaking clinical evaluation of the RCP in humans; monitor and evaluate, on a continuing basis, all test data; and perform necessary safety analyses and tests. Pacemaker designs were developed and quality assurance and manufacturing procedures established. Prototype pacemakers were fabricated. A total of 126 radioisotope powered units were implanted and have been followed clinically for approximately seven years. Four (4) of these units have failed. Eighty-three (83) units remain implanted and satisfactorily operational. An overall failure rate of less than the target 0.15% per month has been achieved

  11. First ECR-Ionized Noble Gas Radioisotopes at ISOLDE

    CERN Document Server

    Wenander, F; Gaubert, G; Jardin, P; Lettry, Jacques

    2004-01-01

    The production of light noble gas radioisotopes with high ionization potentials has been hampered by modest ionization efficiencies for standard plasma ion-sources. However, the decay losses are minimal as the lingering time of light noble gases within plasma ion-sources is negligible when compared to its diffusion out of the target material. Previous singly charged ECRIS have shown a higher efficiency but also a lingering time of the order of 1 s and a total weight that prevents remote handling by the ISOLDE robot. The compact MINIMONO efficiently addressed the lingering time and weight issues. In addition, the MINIMONO maintained the high off-line ionization efficiency for light noble gases. This paper describes a standard ISOLDE target unit equipped with a MINIMONO ion-source and the first tests. The ion-source has been tested off-line and equipped with a CaO target for on-line tests. Valuable information was gained about high current (100-500 muA) transport through the ISOLDE mass separators designed for ...

  12. Properties of radioisotope sources and design of irradiation facilities

    International Nuclear Information System (INIS)

    Kasamatsu, Tomomichi

    1976-01-01

    Radioisotope sources for industrial use are described, and irradiation facilities are also explained. The materials considered for radiation sources are Co-60, Cs-137, Sr-90, Kr-85, fission products and spent fuel. The dose rate distribution of radiation sources is important for the design of irradiation facilities. The sources must be placed into lead containers and installed in shielded rooms. It is easy to construct the facility for the source of a small amount. The facility and equipments for the source of a large amount must be designed carefully according to the purpose. Examples are illustrated. The cost for irradiation is also an important factor to be considered for industrial use. The amount of required dose, the sizes of apparatuses and containers, the amount of gamma-ray sources and so on are considered in the estimation. The regulation standard for radiation safety is determined by a law. The radiation sources should be sealed completely. Radiation shielding from the sealed sources, the principles of handling the sources, the facilities for handling the sealed sources, the management of the sealed sources and the health check-up of workmen are prescribed. (Kato, T.)

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

    International Nuclear Information System (INIS)

    Tozuka, Zenzaburo; Doi, Masahiro; Miyazawa, Eiji; Kawakami, Takeo

    1998-01-01

    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, 14 C, 3 H, 125 I and 35 S 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.)

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

    Science.gov (United States)

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

    1999-01-01

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

  15. Radioisotopic splenoportography in patients with portal hypertension

    International Nuclear Information System (INIS)

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

    1989-01-01

    Radio-isotopic splenoportography was performed by injecting 99m TcO 4 - 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)

  16. Utilization of radioisotopes in medical field

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, Yasuhito [National Inst. of Radiological Sciences, Chiba (Japan)

    2000-03-01

    The establishment and advance of nuclear medicine was briefly described here and the present situations and recent topics on clinical nuclear medicine were summarized as well as its prospects for the future. A labeling method to monitor dynamic changes of living substances using radioisotope (RI) was established by Hevesy using radionuclides. The radiotracing method has been applied to chemical field. The numbers of yearly application in 1982, 1987, 1992 and 1997 were reported in respects of in vivo assays (scintigram, SPECT, PET), the treatments with unsealed RI, PET and in vitro examination (RIA, IRMA). The data show that the application of in vivo examination greatly increased for the last 5 years. Bone scintigram was most frequent (26.9%) followed by myocardial scintigram (19.6%). On the other hand, application of in vitro radioassay is gradually decreasing now after the peak in 1992 (241,000 cases per day). The determination of blood concentrations of various tumor markers such as CEA, CA19-9, CA15-3 ar3, etc. became able using radioimmunodetection (RID). Positron emission computed tomography (PET) is valuable for detection of malignant tumor especially for postoperative recurrence or metastasis, evaluation of myocardial viability and identification of epileptic focus. PET using {sup 15}O labeled H{sub 2}O is thought useful for the study on higher functions of human brain such as language, thinking, and prognostic evaluation of damages in the brain. Nuclear medicinal examination, which has been used for diagnosis would be utilized for designing of clinical therapy and evaluation of its effects and prognosis. (M.N.)

  17. Daily intakes of naturally occurring radioisotopes in typical Korean foods.

    Science.gov (United States)

    Choi, Min-Seok; Lin, Xiu-Jing; Lee, Sun Ah; Kim, Wan; Kang, Hee-Dong; Doh, Sih-Hong; Kim, Do-Sung; Lee, Dong-Myung

    2008-08-01

    The concentrations of naturally occurring radioisotopes ((232)Th, (228)Th, (230)Th, (228)Ra, (226)Ra, and (40)K) in typical Korean foods were evaluated. The daily intakes of these radioisotopes were calculated by comparing concentrations in typical Korean foods and the daily consumption rates of these foods. Daily intakes were as follows: (232)Th, 0.00-0.23; (228)Th, 0.00-2.04; (230)Th, 0.00-0.26; (228)Ra, 0.02-2.73; (226)Ra, 0.01-4.37 mBq/day; and (40)K, 0.01-5.71 Bq/day. The total daily intake of the naturally occurring radioisotopes measured in this study from food was 39.46 Bq/day. The total annual internal dose resulting from ingestion of radioisotopes in food was 109.83 muSv/y, and the radioisotope with the highest daily intake was (40)K. These values were same level compiled in other countries.

  18. NASA Radioisotope Power System Program - Technology and Flight Systems

    Science.gov (United States)

    Sutliff, Thomas J.; Dudzinski, Leonard A.

    2009-01-01

    NASA sometimes conducts robotic science missions to solar system destinations for which the most appropriate power source is derived from thermal-to-electrical energy conversion of nuclear decay of radioactive isotopes. Typically the use of a radioisotope power system (RPS) has been limited to medium and large-scale missions, with 26 U,S, missions having used radioisotope power since 1961. A research portfolio of ten selected technologies selected in 2003 has progressed to a point of maturity, such that one particular technology may he considered for future mission use: the Advanced Stirling Converter. The Advanced Stirling Radioisotope Generator is a new power system in development based on this Stirling cycle dynamic power conversion technology. This system may be made available for smaller, Discovery-class NASA science missions. To assess possible uses of this new capability, NASA solicited and funded nine study teams to investigate unique opportunities for exploration of potential destinations for small Discovery-class missions. The influence of the results of these studies and the ongoing development of the Advanced Stirling Radioisotope Generator system are discussed in the context of an integrated Radioisotope Power System program. Discussion of other and future technology investments and program opportunities are provided.

  19. Daily intakes of naturally occurring radioisotopes in typical Korean foods

    International Nuclear Information System (INIS)

    Choi, Min-Seok; Lin Xiujing; Lee, Sun Ah; Kim, Wan; Kang, Hee-Dong; Doh, Sih-Hong; Kim, Do-Sung; Lee, Dong-Myung

    2008-01-01

    The concentrations of naturally occurring radioisotopes ( 232 Th, 228 Th, 230 Th, 228 Ra, 226 Ra, and 40 K) in typical Korean foods were evaluated. The daily intakes of these radioisotopes were calculated by comparing concentrations in typical Korean foods and the daily consumption rates of these foods. Daily intakes were as follows: 232 Th, 0.00-0.23; 228 Th, 0.00-2.04; 230 Th, 0.00-0.26; 228 Ra, 0.02-2.73; 226 Ra, 0.01-4.37 mBq/day; and 40 K, 0.01-5.71 Bq/day. The total daily intake of the naturally occurring radioisotopes measured in this study from food was 39.46 Bq/day. The total annual internal dose resulting from ingestion of radioisotopes in food was 109.83 μSv/y, and the radioisotope with the highest daily intake was 40 K. These values were same level compiled in other countries

  20. Radioisotope Therapy of Japan: Future Perspective and Recommendations.

    Science.gov (United States)

    Higashi, Tatsuya; Ikebuchi, Shuji; Uchiyama, Mayuki; Oriuchi, Noboru; Kinuya, Seigo; Hosono, Makoto

    2016-01-01

    In Japan, because of the rapid increase in the number of thyroid cancer patients and the recent severe shortage of radioisotope therapy wards, the prolonged waiting time for the admission to the radioisotope therapy wards has become a social problem. This situation is against one of the main purposes of the Cancer Control Promotion Plan of our nation, which is advocating an equal accessibility of medical care for the Japanese citizens. In 2015, diet discussions about the problems of radioisotope therapy took place and the prime minister stated that the promotion of radioisotope therapy is one of the most important issues in Japan, therefore further promotion of research and development is anticipated in this field. In this article, we have summarized the problems during radioisotope therapy, and have added our recommendations in the social and medical realizable countermeasures in future, according to the deep considerations of medical economy in Japan, an assumption of disease prevalence of thyroid cancer in the future, and the situations of foreign countries.

  1. Current status and future prospect of medical radioisotope application in Taiwan

    International Nuclear Information System (INIS)

    Chen, J. T.; Wang, Y. L.; Lin, W. J.

    2006-01-01

    Full text: The development of radiopharmaceuticals are catalogued as SPECT, PET and labeled therapeutic drugs. INER has almost caught up with the pace of world trend. INER's new innovative research and development of radioisotopes and radiopharmaceuticals have made a great progress. INER horizontally integrate from the cyclotron's high efficient ion source and high power RF techniques to animal PET and animal PET-CT techniques. INER have been developing cyclotron radioisotopes producing techniques since 1993. INER's EBCO TR-30/15 cyclotron with four beamlines and one Nordion's gas target system, and two solid target systems can provide up to 3 0 M eV proton beams. Radioisotopes 123 I, 11 In, 124 I etc. are produced by these targets and some self designed target systems, 18 F fluoride is produced by the new designed water target system and delivered to more than 1 50 f t distance long to several hot cells providing radiofluorination syntheses. 1I is produced as NH 4 I23 and Na 123 I for radioiodination labeling to clinical study. Therapeutic radioisotopes are produced in high grade quality, and provided for labeling monoclonal antibody. Vertically integrate from diagnosis to therapeutical radiopharmaceuticals. Those include the positron and gamma emitting radiopharmaceuticals such as 99 mTc-MAG 3, 9( Tc-TRODAT, 18 F-FDG, 123 I-ADAM etc., and alpha or beta emitting therapeutic radiochemicals 188 Re-Liposome and 225 Ac-DOTA-CEA etc. labeling techniques. Radioisotopes technique plays the core role for PET scanner, diagnosis and therapeutic radiopharmaceutical development. 99 mTc-MAG 3a nd 18 F-FDG etc. have been commercialized by INER. As mentioned previously, INER has acquired the first radiopharmaceutical drug licenses for 18 F-FDG, 111 In-Pentetreotide and Trodat-1 in Taiwan. TRODAT-1 is the first licensed dopamine transporter in the world. It can be possibly delivered to every hospital all over the world. Parkinson disease can be easily diagnosed by identifying the

  2. Radioisotopic synoviorthesis. Overall performance in our centre

    International Nuclear Information System (INIS)

    Ruiz Hernandez, D.M.; Castillo Berrio, C.; Nogueiras Alonso, J.; Rivas Dominguez, O.; Serena Puig, A.; Martinez Bernardez, S.; Loira Bamio, F.; Campos Villarino, L.; Guitian Iglesias, R.; Lopez Lopez, A.

    2015-01-01

    Full text of publication follows. Aim: assessing the use of Radioisotopic Synoviorthesis (RS) in our hospital; its therapeutic efficacy, complication rate and patient satisfaction with this procedure. Materials and methods: retrospective search of the RS performed in our center from 2005 to 2012. Review of medical records (written and electronic items). Patient satisfaction survey by phone. Method: rheumatologist prescription. Informed consent. Pregnancy test if appropriate. Intra-articular administration of 185 MBq of 90 Yttrium-colloidal and 40 mg of triamcinolone. Compressive bandage and relative rest during 48 hours. Control image at 72 hours p.i.. (Bremsstrahlung). Treatment response assessed by: pain and/or joint effusion recurrence or not, its magnitude and frequency; need for fluid drainage; infiltrations and amount of analgesics for clinical control. Initial date of response and duration thereof. Results: 42 cases were reviewed in total (Knee RS), excluding 13: 5 contraindication (Baker cyst), 1 by insufficient joint fluid, 1 performed with 186Renio, by meniscus rupture in 1 and in 5 by insufficient monitoring. Of the 29 cases finally analyzed, 25 had good response at the initial evaluation (2 months). The following-up at 18 months was only possible in 26 patients; of them just 18 persisted with positive outcome. In 4 cases there were never improved. There were slight migration to regional nodes in three patients, but without regional swelling nor other adverse effects. There were no cases of radio-necrosis or transient increase of synovitis. Overall assessment of the procedure by the patients was satisfactory in most cases. Conclusion: the RS in synovitis associated with chronic inflammatory arthropathy of diverse etiology produces very good short-term therapeutic results in most patients and in a lesser, but significant, percentage of cases a durable response even at two years post treatment. In some patients it could be a definitive solution. The RS is

  3. A facility to remotely assemble radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Engstrom, J.W.; Goldmann, L.H.; Truitt, R.W.

    1992-07-01

    Radioisotope Thermoelectric Generators (RTGs) are electrical power sources that use heat from decaying radioisotopes to directly generate electrical power. The RTG assembly process is performed in an inert atmosphere inside a large glovebox, which is surrounded by radiation shielding to reduce exposure to neutron and gamma radiation from the radioisotope heat source. In the past, allowable dose rate limits have allowed direct, manual assembly methods; however, current dose rate limits require a thicker radiation shielding that makes direct, manual assembly infeasible. To minimize RTG assembly process modifications, telerobotic systems are being investigated to perform remote assembly tasks. Telerobotic systems duplicate human arm motion and incorporate force feedback sensitivity to handle objects and tools in a human-like manner. A telerobotic system with two arms and a three-dimensional (3-D) vision system can be used to perform remote RTG assembly tasks inside gloveboxes and cells using unmodified, normal hand tools

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

    International Nuclear Information System (INIS)

    Shypailo, R.J.; Ellis, K.J.

    2001-01-01

    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 40 K 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. 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.

  6. Determination of the radiological impact of radioisotope waste disposal

    International Nuclear Information System (INIS)

    1986-09-01

    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

  7. The application of radioisotopes in the Argentine technology

    International Nuclear Information System (INIS)

    Baro, G.B.; Lazor, C.J.

    1976-10-01

    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) [es

  8. The application of spectrographic analysis to the radioisotope production control

    International Nuclear Information System (INIS)

    Capdevila, C.; Roca, M.

    1972-01-01

    The copper spark technique has been employed for both semi-quantitative and quantitative determinations of twelve usual impurities in the p.p.m. range, in Solutions of Mn-54, Fe-55, Fe-59 and Cr-51. The effect of the HCl concentration has previously been investigated: for the majority of elements the line intensities attain a maximum at 0.3 N HCl. To compensate for the influence of the concentration of the radioactive element, as well as of Na in the Cr-51 samples, Bi, 6a, In, Mo, Pd, TI and Y have been tested. Finally, the quantitative determination of each radioelement has been performed using the above-mentioned elements as internal standards, Ga and Ko giving the best results. (Author) 2 refs

  9. Use of copper radioisotopes in investigating disorders of copper metabolism

    International Nuclear Information System (INIS)

    Camakaris, J.; Voskoboinik, I.; Brooks, H.; Greenough, M.; Smith, S.; Mercer, J.

    1998-01-01

    Full text: Copper is an essential trace element for life as a number of vital enzymes require it. Copper deficiency can lead to neurological disorders, osteoporosis and weakening of arteries. However Cu is also highly toxic and homeostatic mechanisms have evolved to maintain Cu at levels which satisfy requirements but do not cause toxicity. Toxicity is mediated by the oxidative capacity of Cu and its ability to generate toxic free radicals. There are several acquired and inherited diseases due to either Cu toxicity or Cu deficiency. The study of these diseases facilitates identification of genes and proteins involved in copper homeostasis, and this in turn will provide rational therapeutic approaches. Our studies have focused on Menkes disease in humans which is an inherited and usually lethal copper deficiency. Using copper radioisotopes 64 Cu (t 1/2 = 12.8 hr) and 67 Cu (t 1/2 = 61 hr) we have studied the protein which is mutated in Menkes disease. This is a transmembrane copper pump which is responsible for absorption of copper into the body and also functions to pump out excess Cu from cells when Cu is elevated. It is therefore a vital component of normal Cu homeostasis. We have provided the first biochemical evidence that the Menkes protein functions as a P-type ATPase Cu pump (Voskoboinik et al., FEBS Letters, in press) and these data will be discussed. The assay involved pumping of radiocopper into purified membrane vesicles. Furthermore we have transfected normal and mutant Menkes genes into cells and are carrying out structure-function studies. We are also studying the role of amyloid precursor protein (APP) as a Cu transport protein in order to determine how Cu regulates this protein and its cleavage products. These studies will provide vital information on the relationship between Cu and APP and processes which lead to Alzheimers disease

  10. Small Radioisotope Power System Testing at NASA Glenn Research Center

    Science.gov (United States)

    Dugala, Gina; Bell, Mark; Oriti, Salvatore; Fraeman, Martin; Frankford, David; Duven, Dennis

    2013-01-01

    In April 2009, NASA Glenn Research Center (GRC) formed an integrated product team (IPT) to develop a Small Radioisotope Power System (SRPS) utilizing a single Advanced Stirling Convertor (ASC) with passive balancer. A single ASC produces approximately 80 We making this system advantageous for small distributed lunar science stations. The IPT consists of Sunpower, Inc., to provide the single ASC with a passive balancer, The Johns Hopkins University Applied Physics Laboratory (JHUAPL) to design an engineering model Single Convertor Controller (SCC) for an ASC with a passive balancer, and NASA GRC to provide technical support to these tasks and to develop a simulated lunar lander test stand. The single ASC with a passive balancer, simulated lunar lander test stand, and SCC were delivered to GRC and were tested as a system. The testing sequence at GRC included SCC fault tolerance, integration, electromagnetic interference (EMI), vibration, and extended operation testing. The SCC fault tolerance test characterized the SCCs ability to handle various fault conditions, including high or low bus power consumption, total open load or short circuit, and replacing a failed SCC card while the backup maintains control of the ASC. The integrated test characterized the behavior of the system across a range of operating conditions, including variations in cold-end temperature and piston amplitude, including the emitted vibration to both the sensors on the lunar lander and the lunar surface. The EMI test characterized the AC and DC magnetic and electric fields emitted by the SCC and single ASC. The vibration test confirms the SCCs ability to control the single ASC during launch. The extended operation test allows data to be collected over a period of thousands of hours to obtain long term performance data of the ASC with a passive balancer and the SCC. This paper will discuss the results of each of these tests.

  11. Review of Dangerous Radioisotopes: What is Available in Practice, What Should We be Concerned About?

    Science.gov (United States)

    2015-06-01

    I N S T I T U T E F O R D E F E N S E A N A L Y S E S Review of Dangerous Radioisotopes : What is Available in Practice, What Should... Radioisotopes : What is Available in Practice, What Should We be Concerned About? Carl A. Curling, Sc.D. Alex Lodge IDA I Financial... radioisotopes of interest from within the full spectrum of radiological threats. Thirty one radioisotopes were evaluated for their credibility as

  12. Evaluation of medical isotope production with the accelerator production of tritium (APT) facility

    International Nuclear Information System (INIS)

    Benjamin, R.W.; Frey, G.D.; McLean, D.C., Jr; Spicer, K.M.; Davis, S.E.; Baron, S.; Frysinger, J.R.; Blanpied, G.; Adcock, D.

    1997-01-01

    The accelerator production of tritium (APT) facility, with its high beam current and high beam energy, would be an ideal supplier of radioisotopes for medical research, imaging, and therapy. By-product radioisotopes will be produced in the APT window and target cooling systems and in the tungsten target through spallation, neutron, and proton interactions. High intensity proton fluxes are potentially available at three different energies for the production of proton- rich radioisotopes. Isotope production targets can be inserted into the blanket for production of neutron-rich isotopes. Currently, the major production sources of radioisotopes are either aging or abroad, or both. The use of radionuclides in nuclear medicine is growing and changing, both in terms of the number of nuclear medicine procedures being performed and in the rapidly expanding range of procedures and radioisotopes used. A large and varied demand is forecast, and the APT would be an ideal facility to satisfy that demand

  13. New methods for radio-isotope investigation in cardiology

    International Nuclear Information System (INIS)

    Usdin, J.-P.; Meignan, M.

    1979-01-01

    Radio-isotopes can play an important part in non invasive evaluation of the cardio-vascular system. Thallium 201 myocardial scintiscan associated to exercise ECG is an excellent examination in the evaluation of coronary insufficiency. Labelled Albumin angioscintiscan studies ventricular function and certain congenital heart diseases without any danger to the patient [fr

  14. Clinical evaluation of Proscillaridin-A with radioisotopes

    International Nuclear Information System (INIS)

    Franco, P.D.A.; Cordovil, I.L.; Rocha, A.F.G.

    1976-01-01

    Thirty patients with cardiac insufficiency were evaluated under the use of Proscillaridin-A. The analysis was based on classic clinical parameters and 11 patients through the circulation time with the radioisotopic technique. The results obtained are analysed and discussed about the absence of side effects, considering as well the therapeutic use of the drug [pt

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

    International Nuclear Information System (INIS)

    Wang Tieshan; Zhang Baoguo

    1996-01-01

    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

  16. Anthropogenic radioisotopes to estimate rates of soil redistribution by wind

    Science.gov (United States)

    Erosion of soil by wind and water is a degrading process that affects millions of hectares worldwide. Atmospheric testing of nuclear weapons and the resulting fallout of anthropogenic radioisotopes, particularly Cesium 137, has made possible the estimation of mean soil redistribution rates. The pe...

  17. A Concept for a Radioisotope Powered Lunar CubeSat

    Science.gov (United States)

    Cataldo, R. L.

    2016-11-01

    Presented is a concept for a small lander or cubesat lunar mission that would benefit from a low-power milli-watt radioisotope power source (RPS). A RPS would provide long-lived electrical and thermal power enabling a long-lived lunar mission.

  18. Are radioisotope shortages a thing of the past?

    International Nuclear Information System (INIS)

    Peykov, Pavel; Cameron, Ron

    2014-01-01

    Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of 99 Mo/ 99m Tc supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo/ 99m Tc supply situation periodically, using the most up-to-date data from supply chain participants, to highlight periods of reduced supply and underscore the case for implementing the HLG-MR policy approach in a timely and globally-consistent manner. In 2012, the NEA released a 99 Mo supply and demand update for the period up to 2030 (A Supply and Demand Update of the Molybdenum-99 Market, OECD/NEA, 2012), identifying periods of low supply relative to demand. This paper presents the preliminary results from an updated 99 Mo supply and demand forecast, focusing on the potentially critical 2015-2020 period, when two major 99 Mo producers (the NRU reactor in Canada and the OSIRIS reactor in France) are scheduled to cease 99 Mo irradiations. On the demand side, the NEA had previously released a study with the results from a global survey of future demand for 99 Mo/ 99m Tc (OECD-NEA, 2011), devising a scenario based on a data assessment by an expert advisory group. In the current analysis, the expected demand growth rate and total demand have been modified, based on the latest information from supply chain participants. On the supply side, the NEA has updated the list of current and planned new 99 Mo/ 99m Tc irradiation and processing projects. The modelling results incorporate revisions to production start/end dates, potential additional projects, and impacts of converting to the use of low-enriched uranium (LEU) targets on 99 Mo/ 99m Tc capacity and production. The supply forecast horizon (2015 to 2020) has been chosen to reflect upcoming, important changes in global production capacity - the planned shutdowns in Canada and France, and the expected

  19. Control of radioisotopes and radiation sources in Indonesia

    International Nuclear Information System (INIS)

    Ridwan, M.

    2001-01-01

    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

  20. The practical model of electron emission in the radioisotope battery by fast ions

    International Nuclear Information System (INIS)

    Erokhine, N.S.; Balebanov, V.M.

    2003-01-01

    Under the theoretical analysis of secondary-emission radioisotope source of current the estimate of energy spectrum F(E) of secondary electrons with energy E emitted from films is the important problem. This characteristic knowledge allows, in particular, studying the volt-ampere function, the dependence of electric power deposited in the load on the system parameters and so on. Since the rigorous calculations of energy spectrum F(E) are the complicated enough and labour-intensive there is necessity to elaborate the practical model which allows by the simple computer routine on the basis of generalized data (both experimental measurements and theoretical calculations) on the stopping powers and mean free path of suprathermal electrons to perform reliable express-estimates of the energy spectrum F(E) and the volt-ampere function I(V) for the concrete materials of battery emitter films. This paper devoted to description of of the practical model to calculate electron emission characteristics under the passage of fast ion fluxes from the radioisotope source through the battery emitter. The analytical approximations for the stopping power of emitter materials, the electron inelastic mean free path, the ion production of fast electrons and the probability for them to arrive the film surface are taken into account. In the cases of copper and gold films, the secondary electron escaping depth, the position of energy spectrum peak are considered in the dependence on surface potential barrier magnitude U. According to our calculations the energy spectrum peak shifted to higher electron energy under the U growth. The model described may be used for express estimates and computer simulations of fast alpha-particles and suprathermal electrons interactions with the solid state plasma of battery emitter films, to study the electron emission layer characteristics including the secondary electron escaping depth, to find the optimum conditions for excitation of nonequilibrium