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Sample records for accelerator radioisotope production

  1. Linear accelerator for radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-02-01

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

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

    International Nuclear Information System (INIS)

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

  3. Radioisotope production with electron accelerators

    International Nuclear Information System (INIS)

    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. Radioisotope production at JYFL Accelerator Laboratory in Finland

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-31

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

  5. The production of cyclotron radioisotopes and radiopharmaceuticals at the national accelerator centre in South Africa

    International Nuclear Information System (INIS)

    Accelerator radioisotopes have been manufactured in South Africa since 1965 with the 30 MeV cyclotron at the Council for Scientific and Industrial Research (CSIR) in Pretoria. After its closure in 1988, the radioisotope production programme was continued at the National Accelerator Centre (NAC) with the 200 MeV separated sector cyclotron (SCC) utilizing the 66 MeV proton beam, which is shared with the neutron therapy programme during part of the week. A variety of radiopharmaceuticals, such as 18F-FDG, 67Ga-citrate, a 67Ga-labelled resin. 111In-chloride, 111In-oxine and 111In-labelled resin. 123I-sodium iodide and 123I-labelled compounds, 201Tl-chloride, as well as the 81Rb/81mKr gas generator, are prepared for use in the nuclear medicine departments of 12 State hospitals and about 28 private nuclear medicine clinics in South Africa. A few longer-lived radioisotopes, such as 22Na, 55Fe and 139Ce, are also produced for research or industrial use. A research and development programme is running to develop new production procedures to produce radioisotopes and radiopharmaceuticals, or to improve existing production procedures. As part of a programme to utilize the beam time optimally, the production of some other radioisotopes is investigated. (author)

  6. Manual of radioisotope production

    International Nuclear Information System (INIS)

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

  7. 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)

  8. Production of 17F, 15O and other radioisotopes for PET using a 3 MV electrostatic tandem accelerator

    International Nuclear Information System (INIS)

    Target systems for the production of positron emitting radioisotopes used for medical research with positron emission tomography (PET) are under development for a 3 MV electrostatic tandem accelerator (NEC 9SDH-2). This machine is intended primarily for the continuous production of short lived tracers labeled with 15O (t1/2=122 s) or 17F (t1/2=65 s) for determining regional cerebral blood flow in humans. Simple gas, liquid, and solid target systems are presented for the production of [15O]H2O (yield at saturation 13 mCi/μA), [17F]F2 (22 mCi/μA), [17F] fluoride (aq.) (12 mCi/μA), [18F]fluoride (aq.) (21 mCi/μA), [13N] in graphite (25 mCi/μA), and [11C]CO2 (2.3 mCi/μA). Current limitations on single window targets for each production are discussed

  9. 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.

  10. 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?.

  11. High-intensity cyclotrons for radioisotope production and accelerator driven systems

    Science.gov (United States)

    Jongen, Y.; Vandeplassche, D.; Kleeven, W.; Beeckman, W.; Zaremba, S.; Lannoye, G.; Stichelbaut, F.

    2002-04-01

    IBA recently proposed a new method to extract high-intensity positive ion beams from a cyclotron based on the concept of auto-extraction. We review the design of a 14 MeV, multi-milliampere cyclotron using this new technology. IBA is also involved in the design of the accelerator system foreseen to drive the MYRRHA facility, a multipurpose neutron source developed jointly by SCK-CEN and IBA.

  12. High-intensity cyclotrons for radioisotope production and accelerator driven systems

    CERN Document Server

    Jongen, Y; Kleeven, W J; Beeckman, W; Zaremba, S; Lannoye, G; Stichelbaut, F

    2002-01-01

    IBA recently proposed a new method to extract high-intensity positive ion beams from a cyclotron based on the concept of auto-extraction. We review the design of a 14 MeV, multi-milliampere cyclotron using this new technology. IBA is also involved in the design of the accelerator system foreseen to drive the MYRRHA facility, a multipurpose neutron source developed jointly by SCK-CEN and IBA.

  13. INR capabilities for radioisotope production

    International Nuclear Information System (INIS)

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

  14. Production yield of produced radioisotopes from 100 MeV proton beam on lead target for shielding analysis of large accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Oranj, Leila Mokhtari; Oh, Joo Hee; Jung, Nam Suk; Bae, O Ryun; Lee, Hee Seock [Div. of Advanced Nuclear Engineering, POSTECH, Pohang (Korea, Republic of)

    2014-11-15

    In this work, the production yield of major shielding material, a lead, was investigated using 100 MeV protons of KOMAC accelerator facility. For the analysis of the experimental data, the activity has been calculated using the FLUKA Monte Carlo code and analytical methods. The cross section data and the stopping power in the irradiated assembly were calculated by TALYS and SRIM codes in the analytical method, respectively. Consequently, the experimental production yield of produced radioisotopes was compared with the data that are based on Monte Carlo calculations and analytical studies. In this research, the {sup nat}Pb(p, x) reaction was studied using experimental measurements, Monte Carlo simulations and analytical methods. Rereading to the experimental measurements, we demonstrate that both Monte Carlo simulation and analytical methods could be useful tools for the estimation of production yield of this reaction.

  15. Present status of OAP radioisotope production

    International Nuclear Information System (INIS)

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

  16. Particle-beam accelerators for radiotherapy and radioisotopes

    International Nuclear Information System (INIS)

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

  17. Construction Status of the Beamline for Radio-Isotope Production in the Korea Multi-purpose Accelerator Complex

    Energy Technology Data Exchange (ETDEWEB)

    Chung, B. H.; Yoon, S. P.; Seol, K. T.; Kim, H. S.; Kwon, H. J.; Cho, Y. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The 100-MeV beamline consist of 5 target room, a TR 103 as one of these is operating beamline, and a TR 101 as the other beamline is under construction as shown in Fig. 1. The TR 101 as beamline target room will be used for the high value-added medical isotope production and increased utilization of the proton accelerator. The optical system of the beamline consisted of dipole and quadrupole, and it included beam position monitor (BPM) and current transformer (CT) for beam diagnostics. The beamline was inserted into the carbon block and the aluminum collimator, the end of pipe as beam window was used for the aluminum to reduce the radioactive of materials. The target transfer equipment is being installed for RI production. The RI Beamline was aligned using the laser tracker, and vacuum leak was not detected by the helium leak detector. This facility is expected to the high value-added medical isotope production and increased utilization of the proton accelerator.

  18. 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.

  19. Radioisotope handling facilities and automation of radioisotope production

    International Nuclear Information System (INIS)

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

  20. Overview of radioisotope production and utilization

    International Nuclear Information System (INIS)

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

  1. 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.

  2. 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)

  3. Spallation production of neutron deficient radioisotopes in North America

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-10-01

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

  4. 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.

  5. Quality control of radioisotopic products

    International Nuclear Information System (INIS)

    Radiopharmaceutical quality control is a very comprehensive and responsible activity since it concerns products being used for the health care of patients. Quality control is practised by an analytical specialist in close cooperation with pharmacists who are responsible for routine quality assurance. There is also a good understanding with the production group to ensure high-quality products. Quality control also relies on the research and development group to investigate problems. Finally there is feedback from the user since he is also responsible for quality control in a limited way. The scope of quality control is comprehensive, e.g. physical inspection and chemical control of all inactive starting material including supervision of the various stages of production. The quality control of radioactive material includes nuclidic analysis, verification of radiochemical purity as well as regular stability checks. Biological controls comprise sterility tests both on final products and production environment; testing for toxicity, pyrogens and LD50 values. To test product efficacy it is imperative to rely on biodistribution. Rabbits are used for quality control screening in a qualitative static mode and the dissection of mice organs is carried out for time-consuming quantitative analyses. Since radiopharmaceuticals are being used in a dynamic mode by nuclear medicine, their quality control tests on animals should, for proper evaluation, be carried out by means of comparative studies with imported products and by using a high-resolution camera with computer facilities. The Group for Quality Control and Assurance is responsible for an extensive documentation system which ensures both good manufacturing practice and effective analytical tests. Through quality control the specialist is constantly striving for improvement to ensure a good product for the benefit of the patient

  6. 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)

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

    OpenAIRE

    Gizem Bakır; Saltuk Buğra Selçuklu; Hüseyin Yapıcı

    2016-01-01

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

  8. Self-reliance politics in radioisotopes production

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  11. Technical and economical availability of radioisotopes production in Brazil

    International Nuclear Information System (INIS)

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

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

    Indian Academy of Sciences (India)

    V Shivarudrappa; K V Vimalnath

    2005-07-01

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

  13. Development of stable isotope separation technology for radioisotope production

    International Nuclear Information System (INIS)

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

  14. Utilization of material testing reactor for radioisotope production

    International Nuclear Information System (INIS)

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

  15. A 5 MW TRIGA reactor design for radioisotope production

    International Nuclear Information System (INIS)

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

  16. 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...

  17. Shielding calculation of the radioisotope production channel at 'Tesla' cyclotron installation

    International Nuclear Information System (INIS)

    During construction of the 'Tesla' Accelerator Installation in the Vinca Institute, one of the important problems was shielding calculation for the Radioisotope production Channel. Calculations were made in three different methods: empirical, semiempirical and Monte Carlo method. The results have been compared and show good agreement. (author)

  18. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-10-01

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

  20. Wolf-Rayet stars and radioisotope production

    CERN Document Server

    Meynet, G

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-08-31

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

  3. KAERI charged particle cross section library for radioisotope production

    CERN Document Server

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

    2001-01-01

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

  4. Solid targets for production of radioisotopes with cyclotron

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  6. 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.

  7. Production capabilities in US nuclear reactors for medical radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-11-01

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

  8. Production of radioisotopes within a plasma focus device

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  10. Production, control and utilization of radioisotopes including radiopharmaceuticals

    International Nuclear Information System (INIS)

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

  11. 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)

  12. A benchmark study on uncertainty of ALICE ASH 1.0, TALYS 1.0 and MCNPX 2.6 codes to estimate production yield of accelerator-based radioisotopes

    Indian Academy of Sciences (India)

    Seyed Amirhossen Feghi; Zohreh Gholamzadeh; Zahra Alipoor; Akram Zali; Mahdi Joharifard; Morteza Aref; Claudio Tenreiro

    2013-07-01

    Radioisotopes find very important applications in various sectors of economic significance and their production is an important activity of many national programmes. Some deterministic codes such as ALICE ASH 1.0 and TALYS 1.0 are extensively used to calculate the yield of a radioisotope via numerical integral over the calculated cross-sections. MCNPX 2.6 stochastic code is more interesting among the other Monte Carlo-based computational codes for accessibility of different intranuclear cascade physical models to calculate the yield using experiment-based cross-sections. A benchmark study has been proposed to determine the codes' uncertainty in such calculations. 109Cd, 86Y and 85Sr production yields by proton irradiation of silver, rubidium chloride and strontium carbonate targets are studied. 109Cd, 86Y and 85Sr cross-sections are calculated using ALICE ASH 1.0 and TALYS 1.0 codes. The evaluated yields are compared with the experimental yields. The targets are modelled using MCNPX 2.6 code. The production yields are calculated using the available physical models of the code. The study shows acceptable relative discrepancies between theoretical and experimental results. Minimum relative discrepancy between experimental and theoretical yields is achievable using ISABEL intranuclear model in most of the targets simulated by MCNPX 2.6. The stochastic code utilization can be suggested for calculating 109Cd, 86Y and 85Sr production yields. It results in more valid data than TALYS 1.0 and ALICE ASH 1.0 in noticeably less average relative discrepancies.

  13. Radioisotope production at 14 MW TRIGA

    International Nuclear Information System (INIS)

    Few years after reactor first start-up it was developed a program for small-scale isotope production, as a complementary activity to the main activities at TRIGA reactor i.e. fuel and material testing in loops and capsules. We aimed to obtain radioactive material for industrial and medical use, of medium and high specific activity. In this paper, one is briefly described the irradiation conditions, irradiation devices, post-irradiation handling and the steps intended for improving the quality of this activity, referring particularly to some widely used isotopes as Ir-192, I-125, and Co-60 and to some radiopharmaceuticals (Mo-99 and I-131). One concludes by suggesting some ways to improve and enlarge isotope production at TRIGA: i. to optimize the channel filling with thinner iridium disks (0.25 mm) by re-spacing them; ii. to design and operate a better charging and discharging system of the ampoules irradiated in peripheral berylium channels; iii. to start fast neutron irradiations for getting medium half life isotopes such as P-32 and S-35; iv. to allocate a new high flux irradiation channel for cobalt, without interfering with the rest of the irradiations. (authors)

  14. Evaluation of medical isotope production with the accelerator production of tritium (APT) facility

    International Nuclear Information System (INIS)

    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

  15. Evaluation of medical isotope production with the accelerator production of tritium (APT) facility

    Energy Technology Data Exchange (ETDEWEB)

    Benjamin, R.W. [Westinghouse Savannah River Company, Aiken, SC (United States); Frey, G.D.; McLean, D.C., Jr; Spicer, K.M.; Davis, S.E.; Baron, S.; Frysinger, J.R. [Medical Univ. of South Carolina, Charleston, SC (United States); Blanpied, G.; Adcock, D. [South Carolina Univ., Columbia, SC (United States)

    1997-07-10

    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.

  16. 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.

  17. Charged particle cross-section database for medical radioisotope production: diagnostic radioisotopes and monitor reactions. Final report of a co-ordinated research project

    International Nuclear Information System (INIS)

    Medical applications of nuclear radiation are of considerable interest to the IAEA. Cyclotrons and accelerators, available in recent years in an increasing number of countries, are being used for the production of radioisotopes for both diagnostic and therapeutic purposes. The physical basis of this production is described through interaction of charged particles, such as protons, deuterons and alphas, with matter. These processes have to be well understood in order to produce radioisotopes in an efficient and clean manner. In addition to medical radioisotope production, reactions with low energy charged particles are of primary importance for two major applications. Techniques of ion beam analysis use many specific reactions to identify material properties, and in nuclear astrophysics there is interest in numerous reaction rates to understand nucleosynthesis in the Universe. A large number of medically oriented cyclotrons have been running in North America, western Europe and Japan for more than two decades. In recent years, 30-40 MeV cyclotrons and smaller cyclotrons (Ep < 20 MeV) have been installed in several countries. Although the production methods are well established, there are no evaluated and recommended nuclear data sets available. The need for standardization was thus imminent. This was pointed out at three IAEA meetings. Based on the recommendations made at these meetings, the IAEA decided to undertake and organize the Co-ordinated Research Project (CRP) on Development of Reference Charged Particle Cross-Section Database for Medical Radioisotope Production. The project was initiated in 1995. It focused on radioisotopes for diagnostic purposes and on the related beam monitor reactions in order to meet current needs. It constituted the first major international effort dedicated to standardization of nuclear data for radioisotope production. It covered the following areas: Compilation of data on the most important reactions for monitoring light ion

  18. Research reactor production of radioisotopes for medical use

    International Nuclear Information System (INIS)

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

  19. 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)

  20. Accelerators for energy production

    International Nuclear Information System (INIS)

    A tremendous progress of accelerators for these several decades, has been motivated mainly by the research on subnuclear physics. The culmination in high energy accelerators might be SSC, 20 TeV collider in USA, probably the ultimate accelerator being built with the conventional principle. The technology cultivated and integrated for the accelerator development, can now stably offer the high power beam which could be used for the energy problems. The Inertial Confinement Fusion (ICF) with high current, 10 kA and short pulse, 20 ns heavy ion beam (HIB) of mass number ∼200, would be the most promising application of accelerators for energy production. In this scenario, the fuel containing D-T mixture, will be compressed to the high temperature, ∼10 keV and to the high density state, ∼1000 times the solid density with the pressure of ablative plasma or thermal X ray produced by bombarding of high power HIB. The efficiency, beam power/electric power for accelerator, and the repetition rate of HIB accelerators could be most suitable for the energy production. In the present paper, the outline of HIB ICF (HIF) is presented emphasizing the key issues of high current heavy ion accelerator system. (author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    Clinical use of three short-lived radioisotopes: 15O, 13N and 11C 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 15O, 13N, 11C from the target bombardment with charged and accelerated particles was studied

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

    International Nuclear Information System (INIS)

    The dose transmission factor for normal concrete and the neutrons produced in the18O(p,n)18F and 13C(p,n)13N 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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

  9. 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)

  10. 78 FR 15009 - Consideration of Withdrawal From Commercial Production and Distribution of the Radioisotope...

    Science.gov (United States)

    2013-03-08

    ... Consideration of Withdrawal From Commercial Production and Distribution of the Radioisotope Germanium-68 AGENCY... commercial production and distribution of germanium-68, based upon private industry expression of interest in... to refrain from competition with private industry in the commercial production and distribution...

  11. 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)

  12. Radioisotope production for using in nuclear medicine, in the IPEN-CNEN/SP - Brazil

    International Nuclear Information System (INIS)

    The importance of radioisotopes used in nuclear medicine is shown. The performance of the cyclotrons model CV-28 and studies about production of 123I are evaluated. The irradiation of mercury target as well as radioelements for using in nuclear medicine are studied. (M.J.C.)

  13. 77 FR 21592 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2012-04-10

    ... published in the Federal Register for comment on October 13, 2011 (76 FR 63668). This draft ISG provides... COMMISSION Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes..., ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format...

  14. 76 FR 63668 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2011-10-13

    ... COMMISSION Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes..., ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and... Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance...

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

    International Nuclear Information System (INIS)

    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)

  16. Radioisotope production in target fragmentation with high-energy heavy ions at HIMAC

    International Nuclear Information System (INIS)

    In order to improve utilisation of the multitracer method, two aspects of the method were pursued in this study. The production of radioisotopes from target fragmentation of 197Au nuclei was performed with high-energetic heavy ions of 12C (180, 290, 400 MeV/u) and 40Ar (290, 650 MeV/u) at HIMAC facilities. The yields of products were measured by using a thick-target-thick-catcher method and off-line gamma spectrometry with Ge semiconductor detectors. Besides, a special apparatus for practice of the radioisotope production was designed in application of the tracers for separation of the products from target material with high efficiency and the target material and shape for the design was investigated in a trial examination. (author)

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

    International Nuclear Information System (INIS)

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

  18. Nuclear reactors and production of medicinal radioisotopes : case of the CNSTN's subcritical assembly

    International Nuclear Information System (INIS)

    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 (utilizing the Cobalt-60 radioisotope) and medical imaging (utilizing the technetium-99 radioisotope). We propose to summarize, the basic information concerning the production of radioisotopes with research reactors, as well as information about the current project to implement a subcritical assembly-reactor in the National Centre of Nuclear Sciences and Technology (CNSTN). The CNSTN's subcritical assembly will serve as efficient tool for educating and training students and scientists. It would be then made available as a service to the community e.g. for industrial benefit and to academic organizations as an institutional benefit. The subcritical assembly is planned to be operational at the beginning of 2016 and will contribute for the initiation of the first steps (including the enacting of new legislation and the establishment of competent and independent nuclear safety regulator) needed for the development of the Tunisian nuclear power program and the related infrastructure, already considered. This project is carried out with the assistance and the support of the International Atomic Energy Agency. (Author)

  19. Application of Zn + p reactions for production of copper radioisotopes for medical studies

    Energy Technology Data Exchange (ETDEWEB)

    Szelecsenyi, F.; Kovacs, Z. [Institute of Nuclear Research of the Hungarian Academy of Sciences (ATOMKI), Debrecen (Hungary); Steyn, G.F.; Van der Walt, T.N.; Vermeulen, C.; Van der Meulen, N.P.; Dolley, S.G. [iThemba Laboratory for Accelerator Based Sciences (South Africa); Suzuki, K.; Mukai, K. [National Institute of Radiological Sciences, Chiba (Japan)

    2008-07-01

    The production possibility of four medically important copper radioisotopes via Zn + p reactions was studied up to 80 MeV. Based on experimentally evaluated excitation function curves of the {sup 64}Zn(p,x){sup 61}Cu, {sup nat}Zn(p,x){sup 62}Zn {yields} {sup 62}Cu; {sup 66}Zn(p,2pn){sup 64}Cu, {sup 68}Zn(p,x){sup 64}Cu and {sup 68}Zn(p,2p){sup 67}Cu reactions, production energy windows are recommended for the {sup 61}Cu, {sup 62}Cu, {sup 64}Cu and {sup 67}Cu isotopes. The available yields for these radioisotopes as well as the predicted yields of the major contaminants are also presented, it is concluded that the Zn + p route can produce sufficient activity of {sup 61,62,64,67}Cu (with low contamination level) to be considered for practical purposes.

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

    International Nuclear Information System (INIS)

    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

  1. 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.

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

    International Nuclear Information System (INIS)

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Basile, D.; Birattari, C.; Bonard, M.; Salomone, A. (Istituto Nazionale di Fisica Nucleare, Milan (Italy)); Goetz, L.; Sabbioni, E. (Commission of the European Communities, Ispra (Italy). Joint Research Centre)

    1981-06-01

    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 /sup 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).

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

    International Nuclear Information System (INIS)

    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 99mTC from the radioactive solution of Potassium molybdate (K299Mo04) is explained in detail. The specific activity of 99Mo obtained at a neutron flux of 2.5 x 1012 n/cm2, s ranges from 1.75 mCi99Mo/g MoO3 to 6.25 mCi 99Mo/g MoO3. However, the specific activity of 99Mo 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 99mTC 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)

  5. Short-Lived Radioisotope Production, Processing, Distribution and Applications in Korea

    International Nuclear Information System (INIS)

    The production, processing and distribution of short-lived radioisotopes by the Atomic Energy Research Institute of Korea are discussed. The radioisotopes concerned are Na24, Cu64, K42, Mo99, W187, colloidal Au198, Br82m and I128. The paper also deals with applications of these isotopes in various fields in Korea. The most important application is the use of Na24 for the detection of leaks in irrigation water storage containers. Since there are nearly 1500 such containers in South Korea, the detection of leaks is a nation-wide problem. Na24 is also applied to metabolic studies in hypertension and to the study of the mixing mechanism in miscible liquid-liquid phase systems. (author)

  6. 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.

  7. Chemical Process for Treatment of Tellurium and Chromium Liquid Waste from I-131 Radioisotope Production

    International Nuclear Information System (INIS)

    The I-131 radioisotope is used in nuclear medicine for diagnosis and therapy. The I-131 radioisotope is produced by wet distillation at Bandung Nuclear Research Center and generated about 4,875 Itr of liquid waste containing 2,532.8 ppm of tellurium and 1,451.8 ppm chromium at pH 1. Considering its negative impact to the environment caused by toxic behaviour of tellurium and chromium, it is necessary to treat chemically that's liquid waste. The research of chemical treatment of tellurium and chromium liquid waste from I-131 radioisotope production has been done. The steps of process are involved of neutralisation with NaOH, coagulation-flocculation process for step I using Ca(OH)2 coagulant for precipitation of sulphate, sulphite, oxalic, chrome Cr3+, and coagulation-flocculation process for step II using BaCI2 coagulant for precipitation of chrome Cr6+ and tellurium from the supernatant of coagulation in step I. The best result of experiment was achieved at 0.0161 ppm of chromium concentration on the supernatant from coagulation-flocculation of step I using 3.5 g Ca(OH)2 for 100 ml of liquid waste, and 0.95 ppm of tellurium concentration on the final supernatant from coagulation-flocculation by of step II using 0.7 g BaCI2 for supernatant from coagulation of step I. (author)

  8. Conceptual design of a new homogeneous reactor for medical radioisotope Mo-99/Tc-99m production

    Energy Technology Data Exchange (ETDEWEB)

    Liem, Peng Hong [Nippon Advanced Information Service (NAIS Co., Inc.) Scientific Computational Division, 416 Muramatsu, Tokaimura, Ibaraki (Japan); Tran, Hoai Nam [Chalmers University of Technology, Dept. of Applied Physics, Div. of Nuclear Engineering, SE-412 96 Gothenburg (Sweden); Sembiring, Tagor Malem [National Nuclear Energy Agency (BATAN), Center for Reactor Technology and Nuclear Safety, Kawasan Puspiptek, Serpong, Tangerang Selatan, Banten (Indonesia); Arbie, Bakri [PT MOTAB Technology, Kedoya Elok Plaza Blok DA 12, Jl. Panjang, Kebun Jeruk, Jakarta Barat (Indonesia)

    2014-09-30

    To partly solve the global and regional shortages of Mo-99 supply, a conceptual design of a nitrate-fuel-solution based homogeneous reactor dedicated for Mo-99/Tc-99m medical radioisotope production is proposed. The modified LEU Cintichem process for Mo-99 extraction which has been licensed and demonstrated commercially for decades by BATAN is taken into account as a key design consideration. The design characteristics and main parameters are identified and the advantageous aspects are shown by comparing with the BATAN's existing Mo-99 supply chain which uses a heterogeneous reactor (RSG GAS multipurpose reactor)

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

    International Nuclear Information System (INIS)

    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

  10. 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

  11. Production of Medical Radioisotopes with High Specific Activity in Photonuclear Reactions with $\\gamma$ Beams of High Intensity and Large Brilliance

    CERN Document Server

    Habs, D

    2010-01-01

    We study the production of radioisotopes for nuclear medicine in $(\\gamma,x{\\rm n}+y{\\rm p})$ photonuclear reactions or ($\\gamma,\\gamma'$) photoexcitation reactions with high flux [($10^{13}-10^{15}$)$\\gamma$/s], small diameter $\\sim (100 \\, \\mu$m$)^2$ and small band width ($\\Delta E/E \\approx 10^{-3}-10^{-4}$) $\\gamma$ beams produced by Compton back-scattering of laser light from relativistic brilliant electron beams. We compare them to (ion,$x$n$ + y$p) reactions with (ion=p,d,$\\alpha$) from particle accelerators like cyclotrons and (n,$\\gamma$) or (n,f) reactions from nuclear reactors. For photonuclear reactions with a narrow $\\gamma$ 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). $(\\gamma,\\gamma')$ isomer production via specially selected $\\gamma$ cascades allows to produce high specific activity in multiple excitations, where no back-pumping of the isomer to the ground st...

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

    International Nuclear Information System (INIS)

    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 203Pb radioisotope. However the targeted radionuclide therapy especially the α-emitting radioisotope therapy is also strongly interested to find an ideal tracer for the 213Bi and 212Pb therapy. Therefore the 203Pb is a potential radioisotope for this role due to its radiation behaviour and as heavy metal element. The 203Tl(p,n) 203Pb 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 carried out

  13. Supervision of I-125 Production at the Center of Radioisotope and Radiopharmaceutical

    International Nuclear Information System (INIS)

    The production of I-125 is one of the many research conducted at the Center for Radioisotope and Radiopharmaceutical. The supervision of I-125 production ia aimed in to managing an acceptance of external radiation doses of radiation by workers who engaged in the production of I-125 as dissolution and purification process of I-125 give a certain radiation exposure to the operator. According to the work instruction for preparation of I-125. The process has to closely monitored and supervised by Radiation Protection Officer (PPR). The production process of I-125 usually involves four radiation workers and one PPR. The acceptance of external radiation doses during the production process of I-125 was recorded was the PPR by using digital pen dose and radiation exposure rate was monitored by using survey meter. The acceptance of external radiation dose found was then compare the acceptance of external radiation dose from the TLD-badge reading and also to the dose limit value established by the monitoring board (BAPETEN). The acceptance of external radiation doses in the production of single batch of I-125 was found to be below the dose limit value (NBD) defined by BAPETEN. (author)

  14. Estimating individual exposure to 131I for radiation workers at radioisotope production using air sampling and smartphone techniques

    International Nuclear Information System (INIS)

    Indoor individual exposure at radioisotope production depends strongly on temporal concentration variation, contacting time and working location of radiation workers. To estimate personal exposure to indoor air polluted with 131I for the workers at radioisotope production, we had employed a low cost indoor model appropriate for their specific situation. In this model, time-microenvironment occupied by the workers was recorded by a smartphone sensitive motion software. Simultaneously, on the work days, indoor air in the three iodine production rooms was sampled by a portable air sampler coupled with activated carbon cartridges impregnated by TEDA. Then the low background gamma spectrometer was used to measure activity of the cartridges and the concentration of 131I in these rooms was calculated with the temporal resolution of one hour. By combining the hourly concentration with the high temporal resolution of activity patterns, we estimated the actual exposures for the group of workers producing radioisotopes in Nuclear Research Institute (Dalat) for the first four months of 2015. The highest daily average exposure was 410.2 Bq/m3 while the highest average exposure of the group was 147.2 Bq/m3. It showed an useful value for minimizing risks and estimating internal doses as well. This feasibility study may be applied for assessing personal exposure at radioisotope production, but also for many other indoor environments. (author)

  15. Radiochemical separation and quality assessment for the 68Zn target based 64Cu radioisotope production

    International Nuclear Information System (INIS)

    The radiochemical separation of the different radionuclides (64Cu, 67Cu, 67Ga, 66Ga, 56Ni, 57Ni, 55Co, 56Co, 57Co, 65Zn, 196Au ) induced in the Ni supported Cu substrate - 68Zn target system, which was bombarded with the 29.0 MeV proton beam, was performed by ion-exchange chromatography using successive isocratic and/or concentration gradient elution techniques. The overlapped gamma-ray spectrum analysis method was developed to assess the 67Ga and 67Cu content in the 64Cu product and even in the post-67Ga production 68Zn target solution without the support of radiochemical separation. This method was used for the assessment of 64+67Cu radioisotope separation from 67Ga , the quality control of 64Cu product and the determination of the 68Zn (p,2p)67Cu reaction yield. The improvement in the targetry and the optimization of proton beam energy for the 68Zn target based 64Cu and 67Ga production were proposed based on the stopping power and range of the incident proton and on the excitation functions, reaction yields and different radionuclides induced in the target system. (author)

  16. Feasibility Study on Simultaneous Multi-Radioisotope Production using Double Stacked Target in MC-50 Cyclotron

    International Nuclear Information System (INIS)

    This work was mainly focused on the feasibility of double target system for simultaneous two-radioisotope production. A simple double target was simulated for simultaneous production of 117mSn and 211At. To determine the optimum thickness of target layer, We demonstrated that the combination of double target system with a cyclotron capable of generating 47 MeV alpha particle provides simultaneous production of 117mSn and 211At. The radionuclides are often used in medicine for diagnosis, treatment and research. Alpha and beta(or electron) emitting radionuclides have become a promising method for the treatment of some tumors. 117mSn emits short-range electrons with a high linear energy transfer, and thus a high S value resulting in high quality therapeutic radiation. 211At has gained considerable interest for cancer treatment because its half-life of 7.2 hours matches better with the biological half-life of most carrier molecules. Moreover its decay scheme exhibits practically 100% yield for the emission of α-particles, with very low intensity gamma emissions

  17. 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

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

    International Nuclear Information System (INIS)

    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

  19. 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

  20. Cross sections for fuel depletion and radioisotope production calculations in TRIGA reactors

    International Nuclear Information System (INIS)

    For TRIGA Reactors, the fuel depletion and isotopic inventory calculations, depends on the computer code and in the cross sections of some important actinides used. Among these we have U-235, U-238, Pu-239, Pu-240 and Pu-241. We choose ORIGEN2, a code with a good reputation in this kind of calculations, we observed the cross sections for these actinides in the libraries that we have (PWR's and BWR), the fission cross section for U-235 was about 50 barns. We used a PWR library and our results were not satisfactory, specially for standard elements. We decided to calculate cross sections more suitable for our reactor, for that purpose we simulate the standard and FLIP TRIGA cells with the transport code WIMS. We used the fuel average flux and COLAPS (a home made program), to generate suitable cross sections for ORIGEN2, by collapsing the WIMS library cross sections of these nuclides. For the radioisotope production studies using the Central Thimble, we simulate the A and B rings and used the A average flux to collapse cross sections. For these studies, the required nuclides sometimes are not present in WIMS library, for them we are planning to process the ENDF/B data, with NJOY system, and include the cross sections to WIMS library or to collapse them using the appropriate average-flux and the program COLAPS. (author)

  1. Assessment of the radiological control at the IPEN radioisotope production facility

    Energy Technology Data Exchange (ETDEWEB)

    Carneiro, J.C.G.G.; Sanches, M.P.; Rodrigues, D.L.; Campos, D.; Nogueira, P.R.; Damatto, S.R.; Pecequilo, B.R.S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Nuclear and Energy Research Institute, IPEN/SP, Brazil and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in activated carbon cartridges and filter paper) at the workplace during radioisotope production were {sup 131}I, {sup 99m}Tc and {sup 99}Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m{sup 3} ), the activities concentrations also remained below the maximum admissible values, excepting to {sup 125}I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y{sup -1} , below the ICRP 103 recommended limit of 20 mSv.y{sup -1} for workers. (author)

  2. 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)

  3. Assessment of the radiological control at the IPEN radioisotope production facility

    International Nuclear Information System (INIS)

    The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Nuclear and Energy Research Institute, IPEN/SP, Brazil and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in activated carbon cartridges and filter paper) at the workplace during radioisotope production were 131I, 99mTc and 99Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m3 ), the activities concentrations also remained below the maximum admissible values, excepting to 125I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y-1 , below the ICRP 103 recommended limit of 20 mSv.y-1 for workers. (author)

  4. 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.

  5. Assessment of the radiological control at the IPEN radioisotope production facility

    International Nuclear Information System (INIS)

    The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Instituto de Pesquisas Energeticas e Nucleares, IPEN/SP, and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in charcoal and paper filters) at the workplace during radioisotope production were 131I, 99mTc and 99Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m3), the activities concentrations also remained below the maximum permissible values, excepting to 125I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y-1, below the ICRP 103 recommended limit of 20 mSv.y-1 for workers. (author)

  6. Operational readiness review plan for the radioisotope thermoelectric generator materials production tasks

    Energy Technology Data Exchange (ETDEWEB)

    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. 6 refs., 11 figs., 1 tab.

  7. Distribution of natural radioisotopes in industrial products of titanium production technological cycle

    International Nuclear Information System (INIS)

    Distribution of source and decay product nuclides in industrial products of industrial technology is studied to evaluate the radiation factor and examine the possibility of natural uranium and possibility of natural uranium and thorium group radionuclide concentration in separate products and wastes of processes related to ilmenite reprocessing and titanium tetrafluoride production. Determination of gamma-radiating radionuclides is performed by precision gamma spectrometry method, determination of thorium and polonium-210 isotopes - by alpha-spectrometry method using isotope dilution with the participation of polonium-210 and polonium-208. It is ascertained that during ilmenite melting the source radionuclides as well as radium isotopes transfer to a slag fraction, and lead-210 and polonium-210 isotopes get to a dust fraction. 5 refs., 4 tabs

  8. Project and implantation of automation in irradiation systems for solid, liquid and gaseous targets in cyclotrons aiming the production of radioisotopes

    CERN Document Server

    Araujo, S G D

    2001-01-01

    Nowadays, two cyclotron are being operated at IPEN-CNEN/SP: one model CV-28, capable of accelerating p, d sup 3 He sub 4 and alpha, with energies of 24, 14, 36 and 28 MeV, respectively, and beam currents up to 30 mu A; the other one, model Cyclone 30, accelerates protons with energy of 30 MeV and currents up to 350 mu A. Both have the objective of irradiating targets both for radioisotopes production for use in nuclear medicine, such as sup 6 sup 7 Ga, sup 2 sup 0 sup 1 Tl, sup 1 sup 2 sup 3 I, sup 1 sup 8 F and general research. The development of irradiating systems completely automatic was the objective of this work, always aiming to reduce the radiation exposition dose to the workers and to increase the reliability of use of these systems, because very high activities are expected in these processes. In the automation, a Programmable Logical Controller (PCL) was used connected to a feedback net, to manage all the variables involved in the irradiation processes. The program of the PCL was developed using S...

  9. Quarterly Technical Progress Report of Radioisotope Power System Materials Production and Technology Program tasks for April 2000 through June 2000

    Energy Technology Data Exchange (ETDEWEB)

    Moore, J.P.

    2000-10-23

    The Office of Space and Defense Power Systems (OSDPS) 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 (CVSs) and weld shields (WSs). This quarterly report has been divided into three sections to reflect program guidance from OSDPS for fiscal year (FY) 2000. The first section deals primarily with maintenance of the capability to produce flight quality carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, clad vent sets (CVSs), and weld shields (WSs). In all three cases, production maintenance is assured by the manufacture of limited quantities of flight quality (FQ) components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for two new RPS. The last section is dedicated to studies of the potential for the production of 238Pu at ORNL.

  10. 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.

  11. Production and Use of Short-Lived Radioisotopes from Reactors. Vol. II. Proceedings of a Seminar on the Practical Applications of Short-Lived Radioisotopes Produced in Small Research Reactors

    International Nuclear Information System (INIS)

    There are many radioisotope applications in which it is important that the radiation should rapidly fall to an insignificant level once the initial intense activity has served its purpose. Such applications include diagnostic tests in medicine, where it is essential to reduce the radiation dose to the patient to a minimum, non-destructive testing methods which must be applied without contaminating the material or product concerned, and repeated routine tests which are possible only if the residual activity from the previous test is negligible. All these applications call for radionuclides whose half- lives are measured in hours or even minutes. Similarly, in the new but increasingly important technique of activation analysis, whereby the quantities of elements present in a material can be determined by irradiating the material in a reactor and assaying the radionuclides produced, the latter are mainly short-lived and must be measured immediately. While the production of long-lived radionuclides can most economically be left to the large reactors at the main radioisotope centres, short-lived isotopes must be produced, or materials activation performed, in a reactor at or near the place of intended use or analysis; this, then, represents one of the most important uses for the large number of small reactors which have been installed in recent years, or will come into operation in the near future, in many parts of the world. Since in many countries the new problems of producing, separating and applying short-lived radioisotopes are being faced for the first time, the International Atomic Energy Agency believed it would be valuable to survey the state of the art by convening an international Seminar on Practical Applications of Short-lived Radioisotopes produced in Small Research Reactors at its Vienna headquarters in November, 1962. This Seminar provided an opportunity for the producers and users of short-lived radioisotopes from many countries to meet and discuss the

  12. Production and Use of Short-Lived Radioisotopes from Reactors Vol. I. Proceedings of a Seminar on the Practical Applications of Short-Lived Radioisotopes Produced in Small Research Reactors

    International Nuclear Information System (INIS)

    There are many radioisotope applications in which it is important that the radiation should rapidly fall to an insignificant level once the initial intense activity has served its purpose. Such applications include diagnostic tests in medicine, where it is essential to reduce the radiation dose to the patient to a minimum, non-destructive testing methods which must be applied without contaminating the material or product concerned, and repeated routine tests which are possible only if the residual activity from the previous test is negligible. All these applications call for radionuclides whose half- lives are measured in hours or even minutes. Similarly, in the new but increasingly important technique of activation analysis, whereby the quantities of elements present in a material can be determined by irradiating the material in a reactor and assaying the radionuclides produced, the latter are mainly short-lived and must be measured immediately. While the production of long-lived radionuclides can most economically be left to the large reactors at the main radioisotope centres, short-lived isotopes must be produced, or materials activation performed, in a reactor at or near the place of intended use or analysis; this, then, represents one of the most important uses for the large number of small reactors which have been installed in recent years, or will come into operation in the near future, in many parts of the world. Since in many countries the new problems of producing, separating and applying short-lived radioisotopes are being faced for the first time, the International Atomic Energy Agency believed it would be valuable to survey the state of the art by convening an international Seminar on Practical Applications of Short-lived Radioisotopes produced in Small Research Reactors at its Vienna headquarters in November, 1962. This Seminar provided an opportunity for the producers and users of short-lived radioisotopes from many countries to meet and discuss the

  13. Light Weight Radioisotope Heater Unit (LWRHU) production for the Galileo mission

    Science.gov (United States)

    Rinehart, Gary H.

    The Light Weight Radioisotope Heater Unit (LWRHU) is a (Pu-238)O2-fueled heat source designed to provide a thermal watt of power for space missions. The LWRHU will be used to maintain the temperature of various components on the spacecraft at the required level. The heat source consists of a (Pu-238)O2-fuel pellet, a Pt-30 pct Rh capsule, a pyrolytic graphite insulator, and a woven graphite aeroshell assembly. Los Alamos National Laboratory has fabricated 134 heater units which will be used on the Galileo mission.

  14. Production, Characterization, and Acceleration of Optical Microbunches

    Energy Technology Data Exchange (ETDEWEB)

    Sears, Christopher M.S. [Stanford Univ., CA (United States)

    2008-06-20

    Optical microbunches with a spacing of 800 nm have been produced for laser acceleration research. The microbunches are produced using a inverse Free-Electron-Laser (IFEL) followed by a dispersive chicane. The microbunched electron beam is characterized by coherent optical transition radiation (COTR) with good agreement to the analytic theory for bunch formation. In a second experiment the bunches are accelerated in a second stage to achieve for the first time direct net acceleration of electrons traveling in a vacuum with visible light. This dissertation presents the theory of microbunch formation and characterization of the microbunches. It also presents the design of the experimental hardware from magnetostatic and particle tracking simulations, to fabrication and measurement of the undulator and chicane magnets. Finally, the dissertation discusses three experiments aimed at demonstrating the IFEL interaction, microbunch production, and the net acceleration of the microbunched beam. At the close of the dissertation, a separate but related research effort on the tight focusing of electrons for coupling into optical scale, Photonic Bandgap, structures is presented. This includes the design and fabrication of a strong focusing permanent magnet quadrupole triplet and an outline of an initial experiment using the triplet to observe wakefields generated by an electron beam passing through an optical scale accelerator.

  15. Production of medical radioisotope 153Sm in the Tehran Research Reactor (TRR) through theoretical calculations and practical tests

    International Nuclear Information System (INIS)

    Highlights: ► Production of 153Sm isotope by neutron activation in a nuclear reactor was studied. ► Optimal parameters for weight and irradiation time were found. ► This study led to an empirical correction factor (kf). ► Kf enhanced the production procedure of the 153Sm radioisotope. ► The results led to nearly 60% decrease in the amount of material used in the production process. - Abstract: The feasibility of producing 2000–3000 mCi 153Sm by irradiation of 152Sm in 5 MW TRR was studied via TRR core simulation. In this study the cross-section of 152Sm (n,γ) 153Sm reaction from ENDF/B library was used. The effective activation cross section for production of 153Sm is obtained using the neutron spectra in different irradiation channel of the core. The activity of the simulated samples is calculated using the obtained fluxes and cross sections. Then samples were prepared and irradiated under different conditions and fluxes. The final production’s specific activity was measured by the standard dose calibrator ISOMED 1010. By comparison of the theoretical calculations and actual measurements, an empirical correction factor (Kf) was obtained, which is helpful in production procedure of the 153Sm radioisotope. The optimal weight of the samples and irradiation time was studied according to the flux calculations based on the location of the sample and saturated activity calculation. In order to test the proposed conditions, samples were prepared and were irradiated under the proposed conditions. According to the compared results with the initial irradiation condition, the new proposed sample which weighed 4 mg of Sm2O3 is acceptable for the labeling, therefore this study led to nearly 60% decrease in the amount of material used in the production process

  16. The IEA-R1 research reactor: 50 years of operating experience and utilization for research, teaching and radioisotopes production

    International Nuclear Information System (INIS)

    This paper describes almost 50 years of operating experience and utilization of the IEA-R1 research reactor for research, teaching and radioisotopes production. The current and future program of upgrading the reactor is also described. IEA-R1 research reactor at the Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, Brazil is the largest power research reactor in Brazil, with a maximum power rating of 5 MWth. It is being used for basic and applied research in the nuclear and neutron related sciences, for the production of radioisotopes for medical and industrial applications, and for providing services of neutron activation analysis, real time neutron radiography, and neutron transmutation doping of silicon. IEA-R1 is a swimming pool reactor, with light water as the coolant and moderator, and graphite and beryllium as reflectors. The reactor was commissioned on September 16, 1957 and achieved its first criticality. It is currently operating at 3.5 MWth with a 64-hour cycle per week. In the early sixties, IPEN produced 131I, 32P, 198Au, 24Na, 35S, 51Cr and labeled compounds for medical use. In the year 1980, production of 99mTc generator kits from the fission 99Mo imported from Canada was started. This production is continuously increasing, with the current rate of about 16,000 Ci of 99mTC per year. The 99mTc generator kits, with activities varying from 250 mCi to 2,000 mCi, are distributed to more than 260 hospitals and clinics in Brazil. Several radiopharmaceutical products based on 131I , 32P, 51Cr and 153Sm are also produced. During the past several years, a concerted effort has been made in order to upgrade the reactor power to 5 MWth through refurbishment and modernization programs. One of the reasons for this decision was to produce 99Mo at IPEN. The reactor cycle will be gradually increased to 120 hours per week continuous operation. It is anticipated that these programs will assure the safe and sustainable operation of the IEA-R1 reactor for

  17. Radioisotope Power Sources

    International Nuclear Information System (INIS)

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

  18. Optimization of physical and technical parameters relevant to the production and separation of 123 I radioisotope using low energy cyclotrons

    International Nuclear Information System (INIS)

    Radioisotopes of iodine are very frequently used in nuclear medicine. They have been used as scanning agents or for radiotherapy in liver, pancreas, kidneys and thyroid tumors. 131I (T1/2 = 8.03 d) and 125I (T1/2 59.4 d) are extensively used, the former in therapy and the latter for in-vitro testes. In recent years, 124I (T1/2 = 4.18 d) and 120I (T1/2 = 81 min) found some applications in Positron Emission Tomography (PET). 123I (T1/2 =13.2 h) is utilized in diagnostic studies using Single Photon Emission Computed Tomography (SPECT). One of the suitable reactions for production of 123I from Te targets using low energy cyclotrons is the 123Te(p,n)123I reaction. In this work the excitation functions for production of iodine radioisotopes including 123I have been measured using natTe. The cross section values of natTe(p,x n)120g,121,123,124,125,126,128,130I reactions have been determined from their respective threshold energy up to 14.5 MeV. The conventional stacked-foil technique was used and the samples were prepared by an electrodeposition method. In order to validate the data, nuclear model calculations were performed using the code ALICE-IPPE which is based on the preequilibrium-evaporation model. All of the measured excitation curves were compared with those obtained by nuclear model calculation as well as the available data in the literature. From the experimental results the theoretical yields for all of the investigated radionuclides were calculated and plotted as a function of proton energy. The production yield and impurity levels were estimated in the recommended energy ranges. The thick target yields have been determined theoretically from the excitation function curves and measured experimentally by irradiated thick Te target and the results were compared.For production of 123I radionuclide, TeO2 target was prepared on platinum substrate for irradiation. Dry distillation method was used in the separation process. The parameters affecting of the target

  19. Automated production of copper radioisotopes and preparation of high specific activity [64Cu]Cu-ATSM for PET studies

    International Nuclear Information System (INIS)

    60Cu and 64Cu are useful radioisotopes for positron emission tomography (PET) radiopharmaceuticals and may be used for the preparation of promising agents for diagnosis and radiotherapy. In this study, the production and purification of 60/64Cu starting from 60/64Ni using a new automated system, namely Alceo, is described. A dynamic process for electrodeposition and dissolution of 60/64Ni/60/64Cu was developed. Preliminary production yields of 60Cu and 64Cu were 400 and 300 mCi, respectively. 64Cu was used to radiolabel the hypoxia detection tracer ATSM with a specific activity of 2.2±1.3 Ci/μmol.

  20. Automated production of copper radioisotopes and preparation of high specific activity [{sup 64}Cu]Cu-ATSM for PET studies

    Energy Technology Data Exchange (ETDEWEB)

    Matarrese, Mario [Institute of Molecular Bioimaging and Physiology-CNR, University of Milano-Bicocca, San Raffaele Scientific Institute, Via Olgettina 60, 20132 Milano (Italy); Technological Oncologyc Laboratory (LaTO), Contrada Pietrapollastra Pisciotto, 90015 Cefalu (Italy)], E-mail: matarrese.mario@hsr.it; Bedeschi, Paolo [Comecer S.p.A., Via Emilia Ponente 390, 48014 Castelbolognese (Italy); Scardaoni, Roberto [Technological Oncologyc Laboratory (LaTO), Contrada Pietrapollastra Pisciotto, 90015 Cefalu (Italy); Sudati, Francesco; Savi, Annarita; Pepe, Annalisa; Masiello, Valeria; Todde, Sergio; Gianolli, Luigi; Messa, Cristina; Fazio, Ferruccio [Institute of Molecular Bioimaging and Physiology-CNR, University of Milano-Bicocca, San Raffaele Scientific Institute, Via Olgettina 60, 20132 Milano (Italy)

    2010-01-15

    {sup 60}Cu and {sup 64}Cu are useful radioisotopes for positron emission tomography (PET) radiopharmaceuticals and may be used for the preparation of promising agents for diagnosis and radiotherapy. In this study, the production and purification of {sup 60/64}Cu starting from {sup 60/64}Ni using a new automated system, namely Alceo, is described. A dynamic process for electrodeposition and dissolution of {sup 60/64}Ni/{sup 60/64}Cu was developed. Preliminary production yields of {sup 60}Cu and {sup 64}Cu were 400 and 300 mCi, respectively. {sup 64}Cu was used to radiolabel the hypoxia detection tracer ATSM with a specific activity of 2.2{+-}1.3 Ci/{mu}mol.

  1. Analysis of metal radioisotope impurities generated in [{sup 18}O]H{sub 2}O during the cyclotron production of fluorine-18

    Energy Technology Data Exchange (ETDEWEB)

    Gillies, J.M. [Cancer Research-UK/UMIST Radiochemical Targeting and Imaging Group, Christie Hospital NHS Trust, Paterson Institute for Cancer Research, Wilmslow Road, Manchester, M20 4BX (United Kingdom)]. E-mail: jgillies@picr.man.ac.uk; Najim, N. [Cancer Research-UK/UMIST Radiochemical Targeting and Imaging Group, Christie Hospital NHS Trust, Paterson Institute for Cancer Research, Wilmslow Road, Manchester, M20 4BX (United Kingdom); School of Chemical Engineering and Analytical Sciences, University of Manchester, P.O. Box 88, Manchester, M60 1QD (United Kingdom); Zweit, J. [Cancer Research-UK/UMIST Radiochemical Targeting and Imaging Group, Christie Hospital NHS Trust, Paterson Institute for Cancer Research, Wilmslow Road, Manchester, M20 4BX (United Kingdom); School of Chemical Engineering and Analytical Sciences, University of Manchester, P.O. Box 88, Manchester, M60 1QD (United Kingdom)

    2006-04-15

    We show the separation of metal radioistope impurities using capillary electrophoresis (CE). The methodology used is an improvement of existent protocols for separation of stable metal ions. Production of fluorine-18 using [{sup 18}O]H{sub 2}O-enriched water encased in a titanium target body results in the production of several metal radioisotope impurities. Optimisation of the conditions for CE separation of the metal radioisotope impurities incorporated the use of 6 mM 18-Crown-6 in combination with 12 mM glycolic acid as complexing agents within the running buffer (10 mM pyridine, pH 4.0). Using this optimised procedure, we were able to separate and detect a number of metal radioisotopes, including chromium, cobalt, manganese, vanadium and berillium, within the fM concentration range.

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  5. Annual Technical Progress Report of Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2006 Through September 30, 2007

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2008-04-01

    The Office of Radioisotope 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. 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 Radioisotope Power Systems for fiscal year (FY) 2007. 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 radioisotope power systems.

  6. Research trends in radioisotopes: a scientometric analysis

    International Nuclear Information System (INIS)

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

  7. 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.

  8. Excitation functions of reactions of production of radioisotopes 201Tl, 201Pb, 201Bi (experimental and theoretical data)

    International Nuclear Information System (INIS)

    The results of calculations of charged particle induced reactions for the production of neutron deficient radioisotopes 201Tl, 201Pb, 201Bi and concomitant ones are discussed. The excitation functions for reactions 202Hg(p,xn), 197Au(a,xn), 203,205Tl(p,xn), 203,205Tl(d,xn), 203,205Tl(p,pxn), 204Pb(p,xn), 204Pb(p,p3n), 206Pb(p,6n), 206Pb(p,p5n), 207Pb(p,7n), 207Pb(p,p6n), 208Pb(p,xn) and 208Pb(p,p7n) are calculated on the base of statistical model in energy range up to 80 MeV. For the most reactions producing 201Tl the data on the calculated and practical yields under optimum conditions are given and the main admixture levels are pointed out. 30 refs., 9 figs

  9. Internal individual dose monitoring and estimation of dose equivalent from workers of the development and production of radioisotopes in CIAE

    International Nuclear Information System (INIS)

    The results of internal individual dose monitoring from workers of the development and production of radioisotopes in CIAE (1995-2000) are presented. The annual average committed effective dose is 1.8 x 10-2 - 8.0 x 10-1 mSv and the collective committed effective dose is 2.9 x 10-3 - 9.8 x 10-2 man·Sv in 1995-2000. The collective committed effective dose is 1.6 x 10-1 man·Sv and the annual average committed effective dose is 1.8 x 10-1 mSv for the 873 persons from 1995-2000

  10. 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.

    2009-12-20

    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.

  11. 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.

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

    International Nuclear Information System (INIS)

    The reliable supply of molybdenum-99 (99Mo) and its decay product, technetium-99m (99mTc), is a vital component of modern medical diagnostic practices. At present, most of the global production of 99Mo is from highly enriched uranium (HEU) targets. However, all major 99Mo-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 99Mo/99mTc and the long-term supply reliability of these medical isotopes. This study provides the findings and analysis from an extensive examination of the 99Mo/99mTc 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 99Mo production on the global 99Mo/99mTc 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 99Mo/99mTc

  13. Radioisotope analyzer of barium

    International Nuclear Information System (INIS)

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

  14. Manual for reactor produced radioisotopes

    International Nuclear Information System (INIS)

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

  15. 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.

  16. The progress of radioisotope technology and application in China

    Institute of Scientific and Technical Information of China (English)

    Zhang Jinrong; Luo Zhifu

    2008-01-01

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

  17. Improvements for the iodine-123 production at the JYFL-accelerator

    Science.gov (United States)

    Virtanen, A.; Liukkonen, E.; Heikkinen, P.; Kumpulainen, J.

    1999-06-01

    High intensity proton beams are needed in the Jyväskylä accelerator for radioisotope production. At present the extraction efficiency of 30-70 MeV proton beams is 50-70%. This limits the maximum extracted beam current to about 30 μA. In order to minimize activation of the cyclotron and to allow for higher intensities we have studied the possibility of H- acceleration with stripping extraction. It was found that beam losses due to residual gas at a normal pressure in the cyclotron do not exceed a few percent as well as the beam losses due to electromagnetic dissociation of H- ions accelerated up to 75 MeV are lower than 2%. The beam optics calculations show that proton beam can be extracted with an efficiency of 100% and matched with the existing beam line. The plans to develop the production of the 123I radiopharmaceutical raw material includes a new 124Xe gas target system. Its advantages are the increase of the yield due to the lowered proton energy and the purity of the reaction product.

  18. Study of components and statistical reaction mechanism in simulation of nuclear process for optimized production of 64Cu and 67Ga medical radioisotopes using TALYS, EMPIRE and LISE++ nuclear reaction and evaporation codes

    International Nuclear Information System (INIS)

    Production of medical radioisotopes is one of the most important tasks in the field of nuclear technology. These radioactive isotopes are mainly produced through variety nuclear process. In this research, excitation functions and nuclear reaction mechanisms are studied for simulation of production of these radioisotopes in the TALYS, EMPIRE and LISE++ reaction codes, then parameters and different models of nuclear level density as one of the most important components in statistical reaction models are adjusted for optimum production of desired radioactive yields

  19. Frontiers in radioisotope application

    International Nuclear Information System (INIS)

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

  20. Semi-Annual Technical Progress Report of the Radioisotope Power System Materials Production and Technology Program Tasks for September 2000 through March 2001

    Energy Technology Data Exchange (ETDEWEB)

    Moore, J.P.

    2001-05-22

    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) and weld shields (WS). 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) 2001. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, CVS, and WS. 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.

  1. 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.

  2. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Tasks for October 1, 2003 through September 30, 2004

    Energy Technology Data Exchange (ETDEWEB)

    None listed

    2005-06-01

    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 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 Space and Defense Power Systems for fiscal year (FY) 2004. Production and production maintenance activities for flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

  3. 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.

  4. 78 FR 1848 - Plutonium-238 Production for Radioisotope Power Systems for National Aeronautics and Space...

    Science.gov (United States)

    2013-01-09

    ... foreseeable future in the NI PEIS (DOE/EIS-0310), which was issued on December 15, 2000 (65 FR 78484). The NI... production capabilities. The NI PEIS ROD was published on January 26, 2001 (66 FR 7877). In the ROD, DOE had... determined that no additional NEPA documentation was necessary and amended its ROD (69 FR 50180, August...

  5. Radioisotope Power Supply Project

    Data.gov (United States)

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

  6. Radiation safety aspects of production of commercial levels of medical radioisotopes

    Science.gov (United States)

    Boothe, T. E.; McLeod, T. F.; Fernandez-Rubio, F.

    1993-06-01

    The first step toward efficient radiation safety in a facility that intends to produce commercial levels of radionuclides is to nticipate the scope of the facility during the design stages of the physical plant and during formulation of operating procedures. The design and operation must include flexibility to accommodate changing needs of production and research and development while providing radiation safety. A recently proposed licensing guide from the Bureau of Radiation Control, Texas Department of Health, while providing for safe operation, would severely limit flexibility and development. For example, engineering controls and procedures should be specified for generic systems as opposed to each specific radionuclide and by-products. Operator training is critical for reduced exposure and should be addressed, but requiring prior training for all operators is not reasonably achievable and would result in loss of proprietary information. Procedures to reduce exposure should include experimentally determined "cooldown" times, "problem indexes" for specific jobs related to particular cyclotrons, and proper management and administrative structures.

  7. ANNUAL TECHNICAL PROGRESS REPORT OF RADIOISOTOPE POWER SYSTEM MATERIALS PRODUCTION AND TECHNOLOGY PROGRAM TASKS FOR OCTOBER 1, 2004, THROUGH SEPTEMBER 30, 2005

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-09-30

    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. 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 Space and Defense Power Systems for fiscal year (FY) 2005. 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 radioisotope power systems.

  8. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Tasks for October 1, 2004 through September 30, 2005

    Energy Technology Data Exchange (ETDEWEB)

    None listed

    2006-08-03

    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. 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 Space and Defense Power Systems for fiscal year (FY) 2005. 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 radioisotope power systems.

  9. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for October 1, 2004 Through September 30, 2005

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2006-06-01

    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 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 Space and Defense Power Systems for fiscal year (FY) 2005. 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 radioisotope power systems.

  10. 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.

  11. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technical Program Tasks for October 1, 2005 through September 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    None

    2007-04-02

    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. 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 Space and Defense Power Systems for fiscal year (FY) 2006. 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 radioisotope power systems.

  12. ANNUAL TECHNICAL PROGRESS REPORT OF RADIOISOTOPE POWER SYSTEM MATERIALS PRODUCTION AND TECHNOLOGY PROGRAM TASKS FOR OCTOBER 1, 2005 THROUGH SEPTEMBER 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2007-04-01

    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 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 Space and Defense Power Systems for fiscal year (FY) 2006. 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 radioisotope power systems.

  13. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Programs Tasks for October 1, 2005, through September 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    None

    2006-09-30

    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. 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 Space and Defense Power Systems for fiscal year (FY) 2006. 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 radioisotope power systems.

  14. Safety test of transport packages for radioisotopes

    International Nuclear Information System (INIS)

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

  15. Calculation of excitation functions of proton, alpha and deuteron induced reactions for production of medical radioisotopes {sup 122–125}I

    Energy Technology Data Exchange (ETDEWEB)

    Artun, Ozan, E-mail: ozanartun@yahoo.com; Aytekin, Hüseyin, E-mail: huseyinaytekin@gmail.com

    2015-02-15

    In this work, the excitation functions for production of medical radioisotopes {sup 122–125}I with proton, alpha, and deuteron induced reactions were calculated by two different level density models. For the nuclear model calculations, the Talys 1.6 code were used, which is the latest version of Talys code series. Calculations of excitation functions for production of the {sup 122–125}I isotopes were carried out by using the generalized superfluid model (GSM) and Fermi-gas model (FGM). The results have shown that generalized superfluid model is more successful than Fermi-gas model in explaining the experimental results.

  16. Power from Radioisotopes (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Corliss, William R; Mead, Robert L

    1971-01-01

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

  17. Consumer Promotions and the Acceleration of Product Purchases

    OpenAIRE

    Scott A. Neslin; Caroline Henderson; John Quelch

    1985-01-01

    One potential consequence of consumer promotions is the acceleration of consumer category purchases. Purchase acceleration can assume two forms: purchasing of a larger quantity or shortening of interpurchase time. This research presents an analytical framework for measuring purchase acceleration, and applies that framework to the analysis of two product classes. The effects of coupons, manufacturer and retailer advertising, and price cuts are examined. Different market segments and loyalty gr...

  18. 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)

    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)

  19. 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.

  20. Vanguard industrial linear accelerator rapid product development

    Science.gov (United States)

    Harroun, Jim

    1994-07-01

    Siemens' ability to take the VanguardTM Industrial Linear Accelerator from the development stage to the market place in less than two years is described. Emphasis is on the development process, from the business plan through the shipment of the first commercial sale. Included are discussions on the evolution of the marketing specifications, with emphasis on imaging system requirements, as well as flexibility for expansion into other markets. Requirements used to create the engineering specifications, how they were incorporated into the design, and lessons learned from the demonstration system are covered. Some real-life examples of unanticipated problems are presented, as well as how they were resolved, including some discussion of the special problems encountered in developing a user interface and a training program for an international customer.

  1. The radioisotopes and radiations program

    International Nuclear Information System (INIS)

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

  2. Economical Radioisotope Power Project

    Data.gov (United States)

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

  3. Studies on application of radiation and radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-05-01

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

  4. Studies on application of radiation and radioisotopes

    International Nuclear Information System (INIS)

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

  5. Agricultural application of radioisotopes

    International Nuclear Information System (INIS)

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

  6. Production of an accelerated oxygen-14 beam

    CERN Document Server

    Powell, J; Cerny, J

    2003-01-01

    BEARS is an ongoing project to provide a light-ion radioactive-beam capability at the 88-Inch Cyclotron at LBNL. Light radioactive isotopes are produced at a 10 MeV proton medical cyclotron, transported 350 m via a high-speed gas transport capillary, cryogenically separated, and injected into the 88-Inch Cyclotron's ion source. The first radioactive beam successfully accelerated was carbon-11 and beams of intensity more than 10 sup 8 ions/s have been utilized for experiments. Development of oxygen-14 as the second BEARS beam presented considerable technical challenges, both due to its short half-life of 71 s and the radiation chemistry of oxygen in the target. The usual techniques developed for medical uses of oxygen-15 involve the addition of significant amounts of carrier oxygen, something that would overload the ion source. As a solution, oxygen-14 is produced as water in a carrier-free form, and is chemically converted in two steps to carbon dioxide, a form readily usable by the BEARS. This system has bee...

  7. Radioisotope x-ray analysis

    International Nuclear Information System (INIS)

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

  8. 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.

  9. 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.

  10. Radioisotopes as Political Instruments, 1946–1953

    OpenAIRE

    Creager, Angela N. H.

    2009-01-01

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

  11. Geometric Product Formula for Charged Accelerating Black Hole

    CERN Document Server

    Pradhan, Parthapratim

    2016-01-01

    We evaluate the geometric product formula i.e. area (or entropy) product formula of outer horizon (${\\cal H}^{+}$) and inner horizon (${\\cal H}^{-}$) for charged accelerating black hole. We find that mass-independent area functional relation of ${\\cal H}^{\\pm}$ for this black hole in terms of black hole charge, acceleration, cosmological constant and \\emph{cosmic string tension} respectively. We also compute the \\emph{Penrose inequality} for this black hole. Finally we compute the specific heat for this BH to determine the local thermodynamic stability of this black hole. Under certain criterion the black hole displayed second order phase transition.

  12. Radioisotope measurement system

    International Nuclear Information System (INIS)

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

  13. Radioisotopes in industry

    International Nuclear Information System (INIS)

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

  14. 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.

  15. The challenges of commercial isotope production on a linear accelerator

    International Nuclear Information System (INIS)

    The pulsed beam structure inherent to linear accelerators differentiates it from the characteristic cw nature of cyclotrons. This property can result in additional challenges in isotope production targetry where issues of low melting point, rapid thermal cycling, inadequate cooling designs etc. can have an effect. In contrast, the advantages of multiple simultaneous target stations at several beam energies makes this device especially attractive. It allows for the possibility of economically producing specialized research isotopes in combination with large quantities of established commercial products. The operational history of the Denton LINAC facility will be presented as it relates to those particular challenges of isotope production with a high power LINAC beam

  16. Markets for reactor-produced non-fission radioisotopes

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, J.L.

    1977-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-01-01

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

  19. 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...

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Burlison, J.S. (comp.)

    1980-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Burlison, J.S. (comp.)

    1981-08-01

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

  4. Actual and future situations of the use of radioisotopes

    International Nuclear Information System (INIS)

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

  5. 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.

  6. Radioisotopic heat source

    International Nuclear Information System (INIS)

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

  7. Utilization of pion production accelerators in biomedical applications

    International Nuclear Information System (INIS)

    A discussion is presented of biomedical applications of pion-producing accelerators in a number of areas, but with emphasis on pion therapy for treatment of solid, non-metastasized malignancies. The problem of cancer management is described from the standpoint of the physicist, magnitude of the problem, and its social and economic impact. Barriers to successful treatment are identified, mainly with regard to radiation therapy. The properties and characteristics of π mesons, first postulated on purely theoretical grounds by H. Yukawa are described. It is shown how they can be used to treat human cancer and why they appear to have dramatic advantages over conventional forms of radiation by virtue of the fact that they permit localization of energy deposition, preferentially, in the tumor volume. The Clinton P. Anderson Meson Physics Facility (LAMPF), and its operating characteristics, are briefly described, with emphasis on the biomedical channel. The design of a relatively inexpensive accelerator specifically for pion therapy is described as is also the status of clinical trials using the existing Clinton P. Anderson Meson Physics Facility. The advantages of proton over electron accelerator for the production of high quality, high intensity negative pion beams suitable for radiation therapy of malignancies is also addressed. Other current, medically related applications of LAMPF technology are also discussed

  8. Electron accelerator-based production of molybdenum-99: Bremsstrahlung and photoneutron generation from molybdenum vs. tungsten

    Science.gov (United States)

    Tsechanski, A.; Bielajew, A. F.; Archambault, J. P.; Mainegra-Hing, E.

    2016-01-01

    A new "one-stage" approach for production of 99Mo and other radioisotopes by means of an electron linear accelerator is described. It is based on using a molybdenum target both as a bremsstrahlung converter and as a radioisotope producing target for the production of 99Mo via the photoneutron reaction 100Mo(γ,n)99Mo. Bremsstrahlung characteristics, such as bremsstrahlung efficiency, angular distribution, and energy deposition for molybdenum targets were obtained by means of the EGSnrc Monte Carlo simulation code system. As a result of our simulations, it is concluded that a 60 MeV electron beam incident on a thick Mo target will have greater bremsstrahlung efficiency than the same thickness (in units of r0) W target, for target thickness z > 1.84r0, where r0 is the electron range. A 50 MeV electron beam incident on a Mo target will result in greater bremsstrahlung efficiency than the same thickness W target (in units of r0) for target thickness case: z ⩾ 2.0r0. It is shown for the one-stage approach with thicknesses of (1.84-2.0)r0, that the 99Mo-production bremsstrahlung efficiency of a molybdenum target is greater by ∼100% at 30 MeV and by ∼70% at 60 MeV compared to the values for tungsten of the same thickness (in units of the appropriate r0) in the traditional two-stage approach (W converter and separate 99Mo producing target). This advantage of the one-stage approach arises from the fact that the bremsstrahlung produced is attenuated only once from attenuation in the molybdenum converter/target. In the traditional, two-stage approach, the bremsstrahlung generated in the W-converter/target is attenuated both in the converter in the 99Mo-producing molybdenum target. The photoneutron production yield of molybdenum and tantalum (as a substitute for tungsten) target was calculated by means of the MCNP5 transport code. On the basis of these data, the specific activity for the one-stage approach of three enriched 100Mo-targets of a 2 cm diameter and

  9. Accelerator

    International Nuclear Information System (INIS)

    The invention claims equipment for stabilizing the position of the front covers of the accelerator chamber in cyclic accelerators which significantly increases accelerator reliability. For stabilizing, it uses hydraulic cushions placed between the electromagnet pole pieces and the front chamber covers. The top and the bottom cushions are hydraulically connected. The cushions are disconnected and removed from the hydraulic line using valves. (J.P.)

  10. Radiological Hazard of Spallation Products in Accelerator-Driven System

    International Nuclear Information System (INIS)

    The central issue underlying this paper is related to elucidating the hazard of radioactive spallation products that might be an important factor affecting the design option of accelerator-driven systems (ADSs). Hazard analysis based on the concept of Annual Limit on Intake identifies alpha-emitting isotopes of rare earths (REs) (dysprosium, gadolinium, and samarium) as the dominant contributors to the overall toxicity of traditional (W, Pb, Pb-Bi) targets. The matter is addressed from several points of view: code validation to simulate their yields, choice of material for the neutron producing targets, and challenging the beam type. The paper quantitatively determines the domain in which the toxicity of REs exceeds that of polonium activation products broadly discussed now in connection with advertising lead-bismuth technology for the needs of ADSs

  11. Industrial radioisotope economics. Findings of the study group

    International Nuclear Information System (INIS)

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

  12. 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)

  13. Medical applications of accelerators

    CERN Document Server

    Rossi, Sandro

    1998-01-01

    At Present, about five thousands accelerators are devoted to biomedical applications. They are mainly used in radiotherapy, research and medical radioisotopes production. In this framework oncological hadron-therapy deserves particular attention since it represents a field in rapid evolution thanks to the joint efforts of laboratories with long experiences in particle physics. It is the case of CERN where the design of an optimised synchrotron for medical applications has been pursued. These lectures present these activities with particular attention to the new developments which are scientifically interesting and/or economically promising.

  14. Radioisotopes and rice

    International Nuclear Information System (INIS)

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

  15. Radioisotopes for medical applications

    International Nuclear Information System (INIS)

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

  16. Radioisotopes for medical applications

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-03-01

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

  17. Calculation of proton-induced reactions on Tellurium isotopes below 60 MeV for medical radioisotope production

    International Nuclear Information System (INIS)

    The 123Te(p,n)123I, 124Te(p,n)124I and 124Te(p,2n)123I reactions, among the many reaction channels opened, are the major reactions under consideration from a diagnostic purpose because reaction residuals as the gamma emitters are used for most radiopharmaceutical applications involving radioiodine. Based on the available experimental data, the absorption cross sections and elastic scattering angular distributions of the proton-induced nuclear reaction on Te isotopes below 60 NeV are calculated using the optical model code APMNK. The transmission coefficients of neutron, proton, deuteron, trition and alpha particles are calculated by CUNF code and are fed into the GNASH code. By adjusting level density parameters and the pair correction values of some reaction channels, as well as the composite nucleus state density constants of the pre-equilibrium model, the production cross sections and energy-angle correlated spectra of the secondary light particles, as well as production cross sections and energy distributions of heavy recoils and gamma rays are calculated by the statistical plus pre-equilibrium model code GNAH. The calculated results are analysed and compared with the experimental data taken from the EXFOR. The optimized global optical model parameters give overall agreement with the experimental data over both the entire energy range and all tellurium isotopes. (author)

  18. Highly Productive Application Development with ViennaCL for Accelerators

    Science.gov (United States)

    Rupp, K.; Weinbub, J.; Rudolf, F.

    2012-12-01

    The use of graphics processing units (GPUs) for the acceleration of general purpose computations has become very attractive over the last years, and accelerators based on many integrated CPU cores are about to hit the market. However, there are discussions about the benefit of GPU computing when comparing the reduction of execution times with the increased development effort [1]. To counter these concerns, our open-source linear algebra library ViennaCL [2,3] uses modern programming techniques such as generic programming in order to provide a convenient access layer for accelerator and GPU computing. Other GPU-accelerated libraries are primarily tuned for performance, but less tailored to productivity and portability: MAGMA [4] provides dense linear algebra operations via a LAPACK-comparable interface, but no dedicated matrix and vector types. Cusp [5] is closest in functionality to ViennaCL for sparse matrices, but is based on CUDA and thus restricted to devices from NVIDIA. However, no convenience layer for dense linear algebra is provided with Cusp. ViennaCL is written in C++ and uses OpenCL to access the resources of accelerators, GPUs and multi-core CPUs in a unified way. On the one hand, the library provides iterative solvers from the family of Krylov methods, including various preconditioners, for the solution of linear systems typically obtained from the discretization of partial differential equations. On the other hand, dense linear algebra operations are supported, including algorithms such as QR factorization and singular value decomposition. The user application interface of ViennaCL is compatible to uBLAS [6], which is part of the peer-reviewed Boost C++ libraries [7]. This allows to port existing applications based on uBLAS with a minimum of effort to ViennaCL. Conversely, the interface compatibility allows to use the iterative solvers from ViennaCL with uBLAS types directly, thus enabling code reuse beyond CPU-GPU boundaries. Out-of-the-box support

  19. Occupational radiation doses of workers at Pakistan research reactor-I (parr-1) and at radioisotope production plant (ripp) during 1995 to 1999

    International Nuclear Information System (INIS)

    Radiation doses of workers working at Pakistan Research Reactor -I (PARR-I) and Radioisotope Production Plant (RIPP) during the period of 1995 to 1999 have been analysed. It is observed that annual average effective dose values per worker during this period are quite low and well under the limit of 20 mSv/y averaged over a period of five consecutive years. The highest annual dose received by any worker during this period was 13.2 mSv at PARR-I and 31.4 mSv at RIPP. Both are below the maximum dose limit of 50 mSv/worker during any single year over a period of five years. The highest accumulated dose received by any worker in the reported period was 30 mSv and 56.1 mSv at PARR-I and RIPP respectively. These values are less than the limit of 100 mSv that should not be exceeded during five years. None of the workers at both places exceeded any relevant dose limit. The probability of excess cancer risk due to annual average dose values lies in the range of 15 to 151 cancers in a population of one million, which is relatively very low as compared to actual deaths per million that lie in the range of 373 to 994 in various industries. Thus, it is concluded that the PARR-I and RIPP operation is radiologically safe and the workers are well trained and aware of the radiation protection procedures. (author)

  20. PRODUCTION AND APPLICATIONS OF NEUTRONS USING PARTICLE ACCELERATORS

    Energy Technology Data Exchange (ETDEWEB)

    David L. Chichester

    2009-11-01

    Advances in neutron science have gone hand in hand with the development and of particle accelerators from the beginning of both fields of study. Early accelerator systems were developed simply to produce neutrons, allowing scientists to study their properties and how neutrons interact in matter, but people quickly realized that more tangible uses existed too. Today the diversity of applications for industrial accelerator-based neutron sources is high and so to is the actual number of instruments in daily use is high, and they serve important roles in the fields where they're used. This chapter presents a technical introduction to the different ways particle accelerators are used to produce neutrons, an historical overview of the early development of neutron-producing particle accelerators, a description of some current industrial accelerator systems, narratives of the fields where neutron-producing particle accelerators are used today, and comments on future trends in the industrial uses of neutron producing particle accelerators.

  1. Plasma production for electron acceleration by resonant plasma wave

    Science.gov (United States)

    Anania, M. P.; Biagioni, A.; Chiadroni, E.; Cianchi, A.; Croia, M.; Curcio, A.; Di Giovenale, D.; Di Pirro, G. P.; Filippi, F.; Ghigo, A.; Lollo, V.; Pella, S.; Pompili, R.; Romeo, S.; Ferrario, M.

    2016-09-01

    Plasma wakefield acceleration is the most promising acceleration technique known nowadays, able to provide very high accelerating fields (10-100 GV/m), enabling acceleration of electrons to GeV energy in few centimeter. However, the quality of the electron bunches accelerated with this technique is still not comparable with that of conventional accelerators (large energy spread, low repetition rate, and large emittance); radiofrequency-based accelerators, in fact, are limited in accelerating field (10-100 MV/m) requiring therefore hundred of meters of distances to reach the GeV energies, but can provide very bright electron bunches. To combine high brightness electron bunches from conventional accelerators and high accelerating fields reachable with plasmas could be a good compromise allowing to further accelerate high brightness electron bunches coming from LINAC while preserving electron beam quality. Following the idea of plasma wave resonant excitation driven by a train of short bunches, we have started to study the requirements in terms of plasma for SPARC_LAB (Ferrario et al., 2013 [1]). In particular here we focus on hydrogen plasma discharge, and in particular on the theoretical and numerical estimates of the ionization process which are very useful to design the discharge circuit and to evaluate the current needed to be supplied to the gas in order to have full ionization. Eventually, the current supplied to the gas simulated will be compared to that measured experimentally.

  2. Development and application of industrial radioisotope instruments in China

    International Nuclear Information System (INIS)

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

  3. Radioisotopes in medicine

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-11-01

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

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

    International Nuclear Information System (INIS)

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

  5. Waste minimization in the Los Alamos Medical Radioisotope Program

    International Nuclear Information System (INIS)

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

  6. Safe Handling of Radioisotopes

    International Nuclear Information System (INIS)

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

  7. The future of medical radioisotope supply

    International Nuclear Information System (INIS)

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

  8. Medical Isotope Production With The Accelerator Production of Tritium (APT) Facility

    International Nuclear Information System (INIS)

    In order to meet US tritium needs to maintain the nuclear weapons deterrent, the Department of Energy (DOE) is pursuing a dual track program to provide a new tritium source. A record of decision is planned for late in 1998 to select either the Accelerator Production of Tritium (APT) or the Commercial Light Water Reactor (CLWR) as the technology for new tritium production in the next century. To support this decision, an APT Project was undertaken to develop an accelerator design capable of producing 3 kg of tritium per year by 2007 (START I requirements). The Los Alamos National Laboratory (LANL) was selected to lead this effort with Burns and Roe Enterprises, Inc. (BREI) / General Atomics (GA) as the prime contractor for design, construction, and commissioning of the facility. If chosen in the downselect, the facility will be built at the Savannah River Site (SRS) and operated by the SRS Maintenance and Operations (M ampersand O) contractor, the Westinghouse Savannah River Company (WSRC), with long-term technology support from LANL. These three organizations (LANL, BREI/GA, and WSRC) are working together under the direction of the APT National Project Office which reports directly to the DOE Office of Accelerator Production which has program authority and responsibility for the APT Project

  9. On production and acceleration of polarized heavy ions at tandem electrostatic accelerator (TEA)

    International Nuclear Information System (INIS)

    The possibilities of polarized experiments with heavy ions on TEA at terminal voltage 7.5MV are discussed. The scheme of polarized ion source (PIS) of 14N and its injection into the accelerator is described. The data energies at accelerator output and target nucleus maximum charges for nuclear reactions of above Coulomb barrier were obtained. The optics of ion movement from PIS to the target and spin dynamics calculation results of 14N ions moving in the same channel on axial and the most remote side trajectory is analyzed. The most suitable variants of transportation and acceleration of polarized heavy ions for providing the measurement optimal conditions in target were determined. 12 refs.; 3 figs.; 3 tabs

  10. Radioisotopes in sedimentology

    International Nuclear Information System (INIS)

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

  11. Separation of radioisotopes from fuel reprocessing waste

    International Nuclear Information System (INIS)

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

  12. Development of radioisotope preparation and application technology

    International Nuclear Information System (INIS)

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

  13. 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.

  14. Milliwatt Radioisotope Stirling Convertor Project

    Data.gov (United States)

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

  15. The status of the tandem accelerator ANTARES

    Energy Technology Data Exchange (ETDEWEB)

    Fallon, J.; Boldeman, J.; Cohen, D.; Tuniz, C.; Ellis, P. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

    1996-12-31

    The ANTARES facility at the Lucas Heights Research Laboratories has now operated for 4 years. A research program in Accelerator Mass Spectrometry, lon Beam Analysis and small scale radioisotope production has been pursued. During the same period, the accelerator has been significantly upgraded from the configuration which existed at Rutgers University, NJ, USA, before shipment to Australia in 1989. AMS measurement techniques of several long lived isotopes have been developed for environmental, industry and biomedical applications. Both the experimental program and the engineering developments are discussed further.

  16. 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.

  17. Medical application of radioisotopes

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  19. Connecting inflation with late cosmic acceleration by particle production

    Science.gov (United States)

    Nunes, Rafael C.

    2016-04-01

    A continuous process of creation of particles is investigated as a possible connection between the inflationary stage with late cosmic acceleration. In this model, the inflationary era occurs due to a continuous and fast process of creation of relativistic particles, and the recent accelerating phase is driven by the nonrelativistic matter creation from the gravitational field acting on the quantum vacuum, which finally results in an effective equation of state (EoS) less than ‑ 1. Thus, explaining recent results in favor of a phantom dynamics without the need of any modifications in the gravity theory has been proposed. Finally, we confront the model with recent observational data of type Ia Supernova, history of the Hubble parameter, baryon acoustic oscillations (BAOs) and the cosmic microwave background (CMB).

  20. Connecting inflation with late cosmic acceleration by particle production

    CERN Document Server

    Nunes, Rafael C

    2016-01-01

    A continuous process of creation of particles is investigated as a possible connection between the inflationary stage with late cosmic acceleration. In this model, the inflationary era occurs due to a continuous and fast process of creation of relativistic particles, and the recent accelerating phase is driven by the non-relativistic matter creation from the gravitational field acting on the quantum vacuum, which finally results in an effective equation of state less than $-1$. Thus, explaining recent results in favor of a phantom dynamics without the need of any modifications in the gravity theory has been proposed. Finally, we confront the model with recent observational data of type Ia Supernova, history of the Hubble parameter, baryon acoustic oscillations, and the cosmic microwave background.

  1. Comparing Production Cross Sections for QCD Matter, Higgs Boson, Neutrino with Dark Energy in Accelerating Universe

    CERN Document Server

    Ghaffary, Tooraj

    2016-01-01

    In this research, the production cross sections for QCD matter, neutrino and dark energy due to acceleration of Universe is calculated. To obtain these cross sections, the Universe production cross section is multiplied by the particle or dark energy distribution in accelerating Universe. Also missing cross section for each matter and dark energy due to formation of event horizon, is calculated. It is clear that the cross section of particles produced near event horizon of Universe is much larger for higher acceleration of Universe. This is because as the acceleration of Universe becomes larger, the Unruh temperature becomes larger and the thermal radiations of particles are enhanced. There are different channels for producing Higgs boson in accelerating Universe. Universe maybe decay to quark and gluons, and then these particles interact with each other and Higgs boson is produced. Also, some Higgs boson are emitted directly from event horizon of Universe. Comparing Higgs boson cross sections via different c...

  2. Symposium on isotope production and applications

    International Nuclear Information System (INIS)

    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

  3. Accelerator mass spectrometry as a bioanalytical tool for nutritional research

    Energy Technology Data Exchange (ETDEWEB)

    Vogel, J.S.; Turteltaub, K.W.

    1997-09-01

    Accelerator Mass Spectrometry is a mass spectrometric method of detecting long-lived radioisotopes without regard to their decay products or half-life. The technique is normally applied to geochronology, but recently has been developed for bioanalytical tracing. AMS detects isotope concentrations to parts per quadrillion, quantifying labeled biochemicals to attomole levels in milligram- sized samples. Its advantages over non-isotopeic and stable isotope labeling methods are reviewed and examples of analytical integrity, sensitivity, specificity, and applicability are provided.

  4. Utilization of accelerators for transmutation and energy production

    Energy Technology Data Exchange (ETDEWEB)

    Sheffield, Richard L [Los Alamos National Laboratory

    2010-09-24

    Given the increased concern over reliable, emission-free power, nuclear power has experienced a resurgence of interest. A sub-critical accelerator driven system (ADS) can drive systems that have either safety constraints (waste transmutation) or reduced fissile content (thorium reactor). The goals of ADS are some or all of the following: (1) to significantly reduce the generation or impacts due to the minor actinides on the packing density and long-term radiotoxicity in the repository design, (2) preserve/use the energy-rich component of used nuclear fuel, and (3) reduce proliferation risk. ADS systems have been actively studied in Europe and Asia over the past two decades and renewed interest is occurring in the U.S. This talk will cover some of the history, possible applicable fuel cycle scenarios, and general issues to be considered in implementing ADS systems.

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

    International Nuclear Information System (INIS)

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

  6. Environmental implications of accelerated gasohol production: preliminary assessment

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This report assesses the environmental impacts of increasing US production of fuel ethanol by 330 million gallons per year in the 1980 to 1981 time frame in order to substitute gasohol for 10% of the unleaded gasoline consumed in the United States. Alternate biomass feedstocks are examined and corn is selected as the most logical feedstock, based on its availability and cost. Three corn conversion processes that could be used to attain the desired 1980 to 1981 production are identified; fermentation plants that use a feedstock of starch and wastes from an adjacent corn refining plants are found to have environmental and economic advantages. No insurmountable environmental problems can be achieved using current technology; the capital and operating costs of this control are estimated. If ethanol production is increased substantially after 1981, the environmentally acceptable use or disposal of stillage, a liquid by-product of fermentation, could become a serious problem.

  7. Ashing vs. electric generation in accelerator driven system

    International Nuclear Information System (INIS)

    Accelerator Driven Systems have been conceived as an alternative for the processing of the radioactive wastes contained in spent fuel elements from nuclear power plants. These systems are formed by the coupling of a nuclear reactor - preferably a subcritical reactor - with a particle accelerator providing particles with energy in the order of the GeV. The long-lived fission products and actinides of the spent fuels are transformed by nuclear reactions in stable isotopes or in short-lived radioisotopes. The basic parameters for the electric energy production of the different systems are analysed. (author)

  8. Reviews of accelerator science and technology

    CERN Document Server

    Chou, Weiren

    2008-01-01

    Particle accelerators are a major invention of the 20th century. In the last eight decades, they have evolved enormously and have fundamentally changed the way we live, think and work. Accelerators are the most powerful microscopes for viewing the tiniest inner structure of cells, genes, molecules, atoms and their constituents such as protons, neutrons, electrons, neutrinos and quarks. This opens up a whole new world for materials science, chemistry and molecular biology.Accelerators with megawatt beam power may ultimately solve a critical problem faced by our society, namely, the treatment of nuclear waste and the supply of an alternative type of energy. There are also tens of thousands of small accelerators all over the world. They are used every day for medical imaging, cancer therapy, radioisotope production, high-density chip-making, mass spectrometry, cargo x-ray/gamma-ray imaging, detection of explosives and illicit drugs, and weapons. This volume provides a comprehensive review of this driving and fas...

  9. Optimal subsidy policy for accelerating the diffusion of green products

    Directory of Open Access Journals (Sweden)

    Hongguang Peng

    2013-06-01

    Full Text Available Purpose: We consider a dynamic duopoly market in which two firms respectively produce green products and conventional products. The two types of product can substitute each other in some degree. Their demand rates depend on not only prices but the consumers’ increasing environmental awareness. Too high initial cost relative to conventional products becomes one of the major obstacles that hinder the adoption of green products. The government employs subsidy policy to trigger the adoption of green products. The purpose of the paper is to explore the optimal subsidy strategy to fulfill the government’s objective. Design/methodology/approach: We suppose the players in the game employ open-loop strategies, which make sense since the government generally cannot alter his policy for political and economic purposes. We take a differential game approach and use backward induction to analyze the firms’ pricing strategy under Cournot competition, and then focus upon a Stackelberg equilibrium to find the optimal subsidy strategy of the government. Findings: The results show that the more remarkable the energy or environmental performance, or the bigger the initial cost of green products, the higher the subsidy level should be. Due to the increasing environmental awareness and the learning curve, the optimal subsidy level decreases over time. Research limitations/implications: In our model several simplifying assumptions are made to keep the analysis more tractable. In particular, we have assumed only one type of green product. In reality several types of product with different energy or environmental performances exist. Our research can be extended in future work to take into account product differentiation on energy or environmental performance and devise a discriminatory subsidy policy accordingly. Originality/value: In the paper we set the objective of the government as minimizing the total social cost induced by the energy consumption or

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  12. Uses of radioisotopes in Sudan

    International Nuclear Information System (INIS)

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

  13. Computation and Analysis of the Global Distribution of the Radioxenon Isotope 133Xe based on Emissions from Nuclear Power Plants and Radioisotope Production Facilities and its Relevance for the Verification of the Nuclear-Test-Ban Treaty

    Science.gov (United States)

    Wotawa, Gerhard; Becker, Andreas; Kalinowski, Martin; Saey, Paul; Tuma, Matthias; Zähringer, Matthias

    2010-05-01

    Monitoring of radioactive noble gases, in particular xenon isotopes, is a crucial element of the verification of the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The capability of the noble gas network, which is currently under construction, to detect signals from a nuclear explosion critically depends on the background created by other sources. Therefore, the global distribution of these isotopes based on emissions and transport patterns needs to be understood. A significant xenon background exists in the reactor regions of North America, Europe and Asia. An emission inventory of the four relevant xenon isotopes has recently been created, which specifies source terms for each power plant. As the major emitters of xenon isotopes worldwide, a few medical radioisotope production facilities have been recently identified, in particular the facilities in Chalk River (Canada), Fleurus (Belgium), Pelindaba (South Africa) and Petten (Netherlands). Emissions from these sites are expected to exceed those of the other sources by orders of magnitude. In this study, emphasis is put on 133Xe, which is the most prevalent xenon isotope. First, based on the emissions known, the resulting 133Xe concentration levels at all noble gas stations of the final CTBT verification network were calculated and found to be consistent with observations. Second, it turned out that emissions from the radioisotope facilities can explain a number of observed peaks, meaning that atmospheric transport modelling is an important tool for the categorization of measurements. Third, it became evident that Nuclear Power Plant emissions are more difficult to treat in the models, since their temporal variation is high and not generally reported. Fourth, there are indications that the assumed annual emissions may be underestimated by factors of two to ten, while the general emission patterns seem to be well understood. Finally, it became evident that 133Xe sources mainly influence the sensitivity of the

  14. Recent developments in radiation equipment and radioisotopes

    International Nuclear Information System (INIS)

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

  15. Subsystem for control of isotope production with linear electron accelerator

    CERN Document Server

    Karasyov, S P; Uvarov, V L

    2001-01-01

    In this report the high-current LINAC subsystem for diagnostic and monitoring the basic technological parameters of isotope production (energy flux of Bremsstrahlung photons and absorbed doze in the target,target activity, temperature and consumption of water cooling the converter and target) is described.T he parallel printer port (LPT) of the personal computer is proposed to use as an interface with the measurement channels.

  16. Accelerator Production and Separations for High Specific Activity Rhenium-186

    Energy Technology Data Exchange (ETDEWEB)

    Jurisson, Silvia S. [Univ. of Missouri, Columbia, MO (United States); Wilbur, D. Scott [Univ. of Washington, Seattle, WA (United States)

    2016-04-01

    Tungsten and osmium targets were evaluated for the production of high specific activity rhenium-186. Rhenium-186 has potential applications in radiotherapy for the treatment of a variety of diseases, including targeting with monoclonal antibodies and peptides. Methods were evaluated using tungsten metal, tungsten dioxide, tungsten disulfide and osmium disulfide. Separation of the rhenium-186 produced and recycling of the enriched tungsten-186 and osmium-189 enriched targets were developed.

  17. Accelerator production of the positron emitter zirconium-89

    International Nuclear Information System (INIS)

    Highlights: ► We present a method for zirconium-89 production using a low-energy cyclotron. ► Excitation functions and theoretical yields of 89Zr via several reactions were calculated. ► Deposition of Y2O3 on Cu substrate was carried out via by the sedimentation method. ► Production yield of about 60.77 MBq 89Zr per μA h was experimentally obtained. - Abstract: We here presented a method for zirconium-89 production using a low-energy cyclotron. The half-life of 89Zr (T1/2 = 78.4 h) is suitable for immunoPET. 89Zr was produced via the 89Y(p, n)89Zr nuclear process at 20 μA current and 15 → 5 MeV protons beam (20 min). Yield of about 60.77 MBq 89Zr per μAh was experimentally obtained. Also, excitation functions and theoretical yields via 89Y(p, n)89Zr, 89Y(d, 2n)89Zr, natSr(α, xn)89Zr and 90Zr(n, 2n)89Zr reactions were calculated by EMPIRE (version 3.1 Rivoli), ALICE/ASH (pre-equilibrium and equilibrium) and TALYS-1.26 (direct, pre-equilibrium, and equilibrium) codes and TENDL-2010 database. The obtained results have been discussed and compared with the available experimental data.

  18. The use of ion exchange chromatography in the cyclotron production of the radioisotopes 85Sr, 54Mn, 57Co and 109Cd

    International Nuclear Information System (INIS)

    This dissertation shows the successful application of ion exchange chromatography to the isolation of carrier free cyclotron produced radioisotopes. A simple method is presented for the isolation of 85Sr from a 10 g rubidium chloride target. Cation exchange with AG50-X12 is used to retain 85Sr from a bombarded target dissolved in 0.1 mol/dm3 hydrochloric acid. Rubidium is effectively eluted with 0.5 mol/dm3 hydrochloric acid and trace impurities such as copper, iron and 65Zn are eluted with 0.5 mol/dm3 hydrochloric acid/φ=0.95 acetone (where φ is the volume fraction of acetone). Strontium-85 is eluted in nearly 100% yield with 3.0 mol/dm3 nitric acid. The isolation of 54Mn, 57Co and 109Cd from a composite iron-silver target is performed with AG50-X4 cation exchange resin in a hydrochloric acid-acetone medium subsequent to the removal of silver by reduction with hydrazine hydrate. Cadmium-109 is eluted with 0.1 mol/dm3 hydrochloric acid/φ=0.80 acetone and is further refined by absorption onto a AG1-X8 anion exchange column and subsequent washing with 0.25 mol/dm3 nitric acid/0.1 mol/dm3 hydrobromic acid. The elution of copper, iron, 65Zn and other impurities from the cation exhanger is performed with 0.5 mol/dm3 hydrochloric acid/φ=0.83 acetone. Cobalt-57 is quantitively eluted with 0.35 mol/dm3 hydrochloric acid/φ=0.90 acetone, and 54Mn, the remaining element on the column, is recovered with 3.0 mol/dm3 hydrochloric acid

  19. Characterization of Corrosion Products on Carbon Steel Exposed to Natural Weathering and to Accelerated Corrosion Tests

    OpenAIRE

    Renato Altobelli Antunes; Rodrigo Uchida Ichikawa; Luis Gallego Martinez; Isolda Costa

    2014-01-01

    The aim of this work was to compare the corrosion products formed on carbon steel plates submitted to atmospheric corrosion in urban and industrial atmospheres with those formed after accelerated corrosion tests. The corrosion products were characterized by X-ray diffraction, Mössbauer spectroscopy, and Raman spectroscopy. The specimens were exposed to natural weathering in both atmospheres for nine months. The morphologies of the corrosion products were evaluated using scanning electron micr...

  20. LANL sunnyside experiment: Study of neutron production in accelerator-driven targets

    International Nuclear Information System (INIS)

    Measurements have been made of the neutron production in prototypic targets for accelerator driven systems. Studies were conducted on four target assemblies containing lead, lithium, tungsten, and a thorium-salt mixture. Integral data on total neutron production were obtained as well as more differential data on neutron leakage and neutron flux profiles in the blanket/moderator region. Data analysis on total neutron production is complete and shows excellent agreement with calculations using the LAHET/MCNP code system

  1. Accelerator based production of auger-electron-emitting isotopes for radionuclide therapy

    International Nuclear Information System (INIS)

    In this research project the focus has been on the identification and production of new, unconventional Auger-electron-emitting isotopes for targeted radionuclide therapy of cancer. Based on 1st principles dosimetry calculations on the subcellular level, the Auger-emitter 119Sb has been identified as a potent candidate for therapy. The corresponding imaging analogue 117Sb has been shown from planar scintigraphy and single-photon emission computed tomography (SPECT) to be suitable for SPECT-based dosimetry of a future Sb-labeled radiopharmaceutical. The production method of these radioisotopes has been developed using a low-energy cyclotron via the nuclear reactions 119Sn(p,n)119Sb and 117Sn(p,n)117Sb including measurements of the excitation function for the former reaction. Moreover, a new high-yield radiochemical separation method has been developed to allow the subsequent separation of the produced 119Sb from the enriched 119Sn target material with high radionuclidic- and chemical purity. A method that also allows efficient recovery of the 119Sn for recycling. To demonstrate the ability of producing therapeutic quantities of 119Sb and other radioisotopes for therapy with a low-energy cyclotron, two new 'High Power' cyclotron targets were developed in this study. The target development was primarily based on theoretical thermal modeling calculations using finite-element-analysis software. With these targets, I have shown that it will be possible to produce several tens of GBq of therapeutics isotopes (e.g. 119Sb or 64Cu) using the PETtrace cyclotron commonly found at the larger PET-centers in the hospitals. Finally, research in a new method to measure the radiotoxicity of Auger-emitters invitro using cellular microinjection has been carried out. The purpose of this method is to be able to experimentally evaluate and compare the potency of the new and unconventional Auger-emitters (e.g. 119Sb). However, due to experimental complications, the development of this

  2. Accelerator based production of auger-electron-emitting isotopes for radionuclide therapy

    Energy Technology Data Exchange (ETDEWEB)

    Thisgaard, H.

    2008-08-15

    In this research project the focus has been on the identification and production of new, unconventional Auger-electron-emitting isotopes for targeted radionuclide therapy of cancer. Based on 1st principles dosimetry calculations on the subcellular level, the Auger-emitter 119Sb has been identified as a potent candidate for therapy. The corresponding imaging analogue 117Sb has been shown from planar scintigraphy and single-photon emission computed tomography (SPECT) to be suitable for SPECT-based dosimetry of a future Sb-labeled radiopharmaceutical. The production method of these radioisotopes has been developed using a low-energy cyclotron via the nuclear reactions 119Sn(p,n)119Sb and 117Sn(p,n)117Sb including measurements of the excitation function for the former reaction. Moreover, a new high-yield radiochemical separation method has been developed to allow the subsequent separation of the produced 119Sb from the enriched 119Sn target material with high radionuclidic- and chemical purity. A method that also allows efficient recovery of the 119Sn for recycling. To demonstrate the ability of producing therapeutic quantities of 119Sb and other radioisotopes for therapy with a low-energy cyclotron, two new 'High Power' cyclotron targets were developed in this study. The target development was primarily based on theoretical thermal modeling calculations using finite-element-analysis software. With these targets, I have shown that it will be possible to produce several tens of GBq of therapeutics isotopes (e.g. 119Sb or 64Cu) using the PETtrace cyclotron commonly found at the larger PET-centers in the hospitals. Finally, research in a new method to measure the radiotoxicity of Auger-emitters invitro using cellular microinjection has been carried out. The purpose of this method is to be able to experimentally evaluate and compare the potency of the new and unconventional Auger-emitters (e.g. 119Sb). However, due to experimental complications, the development

  3. Physical aspects of radioisotope brachytherapy

    International Nuclear Information System (INIS)

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

  4. Control of radioisotopes and radiation sources in Indonesia

    International Nuclear Information System (INIS)

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

  5. Characterization of Corrosion Products on Carbon Steel Exposed to Natural Weathering and to Accelerated Corrosion Tests

    Directory of Open Access Journals (Sweden)

    Renato Altobelli Antunes

    2014-01-01

    Full Text Available The aim of this work was to compare the corrosion products formed on carbon steel plates submitted to atmospheric corrosion in urban and industrial atmospheres with those formed after accelerated corrosion tests. The corrosion products were characterized by X-ray diffraction, Mössbauer spectroscopy, and Raman spectroscopy. The specimens were exposed to natural weathering in both atmospheres for nine months. The morphologies of the corrosion products were evaluated using scanning electron microscopy. The main product found was lepidocrocite. Goethite and magnetite were also found on the corroded specimens but in lower concentrations. The results showed that the accelerated test based on the ASTM B117 procedure presented poor correlation with the atmospheric corrosion tests whereas an alternated fog/dry cycle combined with UV radiation exposure provided better correlation.

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

    CERN Document Server

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

    2015-01-01

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

  7. 99Mo Production via 100Mo(n,2n)99Mo using accelerator neutrons

    OpenAIRE

    Nagai Yasuki

    2014-01-01

    A new production method of 99Mo using accelerator neutrons via the 100Mo(n,2n)99Mo reaction was proposed. Intense neutrons with a most probable energy of 14 MeV can be produced by bombarding Be or C with 40 MeV deuteron beams. Research and development works of 99Mo produced by neutrons from the 3H(d,n)4He reaction were carried out. High quality 99mTc was obtained by employing a sublimation method. Accelerator neutrons are shown to have a great potential to produce a wide variety of radioisoto...

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

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A.

    1986-08-01

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

  9. Accelerated hydrolysis of substituted cellulose for potential biofuel production: kinetic study and modeling.

    Science.gov (United States)

    Mu, Bingnan; Xu, Helan; Yang, Yiqi

    2015-11-01

    In this work, kinetics of substitution accelerated cellulose hydrolysis with multiple reaction stages was investigated to lay foundation for mechanism study and molecular design of substituting compounds. High-efficiency hydrolysis of cellulose is critical for cellulose-based bioethanol production. It is known that, substitution could substantially decrease activation energy and increase reaction rate of acidic hydrolysis of glycosidic bonds in cellulose. However, reaction kinetics and mechanism of the accelerated hydrolysis were not fully revealed. In this research, it was proved that substitution therefore accelerated hydrolysis only occurred in amorphous regions of cellulose fibers, and was a process with multiple reaction stages. With molar ratio of substitution less than 1%, the overall hydrolysis rate could be increased for around 10 times. We also quantified the relationship between the hydrolysis rate of individual reaction stage and its major influences, including molar ratio of substitution, activation energy of acidic hydrolysis, pH and temperature. PMID:26253917

  10. Accelerator driven systems for transmutation and energy production: challenges and dangers

    International Nuclear Information System (INIS)

    Accelerator driven systems (ADS) are an old technological idea: relativistic proton accelerators deliver their beams onto massive heavy element targets, thus producing abundant neutron fluences. Placing this target into sub-critical nuclear fission assemblies is yielding substantial fission reactions, thus additional fission energy (Rubbia called such a system ''energy amplifier''). This technology has recently attracted considerable attention due to advances in the construction of powerful accelerators. It allows the safe and cheap production of nuclear energy simultaneously with the destruction (transmutation) of long lived radioactive waste, in particular plutonium and other minor actinides (neptunium and americium). The principles and the present-state-of-the-art are described, including first experiments to transmute plutonium this way. This technology needs, however, many more years of further ''research and development'' before large scale ADS's can be constructed. It may be even necessary to investigate the question, if all basic physics phenomena of this technology are already sufficiently well understood. (orig.)

  11. Applications of radioisotopes in industry and healthcare in Vietnam

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-10-01

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

  12. Applications of radioisotopes in industry and healthcare in Vietnam

    International Nuclear Information System (INIS)

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

  13. Acceleration of Fe-silicate mineral dissolution for CO2 sequestration via microbial siderophore production

    Science.gov (United States)

    Torres, M. A.; Nealson, K. H.; West, A.

    2013-12-01

    While the dissolution of silicate minerals will ultimately neutralize anthropogenic CO2 emissions, the slow natural timescale of this process limits its ability to mitigate any of the societal impacts of high atmospheric pCO2. As a result, much research has been focused on developing ways to significantly accelerate silicate mineral dissolution rates. Harnessing the effects of microbial activity is one particularly attractive strategy because research has shown that microbes can appreciably accelerate mineral dissolution rates and they require little external energy input. At present, one major hurdle in the development of microbe-based CO2 sequestration techniques is the observation that bacteria only accelerate dissolution rates under particular culturing conditions. In this work, natural and genetic mutant strains of the bacterial genera Shewanella, Pseudomonas, and Marinobacter are used to identify the geochemical and genetic factors that underlie the 'accelerated-weathering phenotype' in order to support the development of microbe-based CO2 sequestration techniques using olivine as a model mineral. Preliminary results suggest that microbial siderophore production at circum-neutral pH results in significantly accelerated olivine dissolution rates.

  14. Radioisotope studies on coconut nutrition

    International Nuclear Information System (INIS)

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

  15. Formation of medical radioisotopes {sup 111}In, {sup 117m}Sn, {sup 124}Sb, and {sup 177}Lu in photonuclear reactions

    Energy Technology Data Exchange (ETDEWEB)

    Danagulyan, A. S.; Hovhannisyan, G. H., E-mail: hov-gohar@ysu.am; Bakhshiyan, T. M. [Yerevan State University (Armenia); Avagyan, R. H.; Avetisyan, A. E.; Kerobyan, I. A.; Dallakyan, R. K. [A.I. Alikhanian National Science Laboratory (Yerevan Physics Institute) (YerPhI) (Armenia)

    2015-06-15

    The possibility of the photonuclear production of radioisotopes {sup 111}In, {sup 117m}Sn, {sup 124}Sb, and {sup 177}Lu is discussed. Reaction yields were measured by the gamma-activation method. The enriched tin isotopes {sup 112,} {sup 118}Sn and Te and HfO{sub 2} of natural isotopic composition were used as targets. The targets were irradiated at the linear electron accelerator of Alikhanian National Science Laboratory (Yerevan) at the energy of 40 MeV. The experimental results obtained in this way reveal that the yield and purity of radioisotopes {sup 111}In and {sup 117}mSn are acceptable for their production via photonuclear reactions. Reactions proceeding on targets from Te and HfO{sub 2} of natural isotopic composition and leading to the formation of {sup 124}Sb and {sup 177}Lu have small yields and are hardly appropriate for the photoproduction of these radioisotopes even in the case of enriched targets.

  16. Neutron Production Using Alpha-Be Reaction on the Neutron Generator Accelerator

    International Nuclear Information System (INIS)

    In order to obtain data for development of small scale Accelerator Driven System (ADS), calculations of neutron production that use alpha-Be reaction on the acceleration energy range of 100 to 500 keV have been carried out. The result of neutron yield calculation was compared with calculation result of D-T reaction and both calculations were treated for thick target. At the energy of 100 keV; alpha-Be reaction produces neutron yield about 1/10 compared to that of D-T reaction and increases to 1/5 at energy of 500 keV. At the same acceleration voltage of 250 kV, where the alpha energy is 500 keV and deuteron energy is 250 keV; the neutron yield of alpha-Be reaction is 1/3 of that in D-T reaction. On the last mentioned condition and considering that target cost of Be is cheaper than the cost of T, neutron production on a neutron generator accelerator that uses alpha-Be reaction is a competitive method as neutron source, especially for ADS. (author)

  17. X-ray production experiments on the RACE Compact Torus Accelerator

    International Nuclear Information System (INIS)

    The Purpose of the Compact Torus Accelerator (CTA) program at LLNL is to prove the principle of a unique accelerator concept based on magnetically confined compact torus (CT) plasma rings and to study applications. Successful achievement of these goals could lead to a high power-density driver for many applications including an intense x-ray source for nuclear weapons effects simulation and an inertial fusion driver. Fusion applications and a description of the CTA concept are included in a companion paper at this conference. This paper will describe the initial experiments on soft x-ray production conducted on the plasma Ring ACcelerator Experiment (RACE) and compare the results to modeling studies. The experiments on CT stagnation and soft x-ray production were conducted with unfocused rings as a first of CT dynamics and the physics of x-ray production. The x-ray fluences observed are consistent with expectations based on calculations employing a radiation-hydrodynamics code. We conclude with a diffusion of future x-ray production studies that can be conducted on RACE and a possible multi-megajoule upgrade

  18. Current Status of Radioisotope Applications in Defence

    Directory of Open Access Journals (Sweden)

    P. K. Bhatnagar

    1987-07-01

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

  19. Trends in the development of radioisotope batteries

    International Nuclear Information System (INIS)

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

  20. Study of Radioisotope Requirements For Power Devices

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Nathan W

    1962-01-01

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

  1. Career opportunities in the applications of radiation and radioisotopes

    International Nuclear Information System (INIS)

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

  2. 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)

  3. 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)

    This document presents a forecast of 99Mo/99mTc 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)

  4. CAS Accelerators for Medical Applications in Vösendorf, Austria

    CERN Multimedia

    CERN Accelerator School

    2015-01-01

    The CERN Accelerator School (CAS) and MedAustron jointly organised a course on Accelerators for Medical Applications in Vösendorf, Austria between 26 May and 5 June 2015. The course was held at the Eventhotel Pyramide on the outskirts of Vienna, and was attended by 76 participants from 29 countries, coming from as far away as Canada, China, Lithuania, Thailand, Ukraine and Russia.       The intensive programme comprised 37 lectures. The emphasis was on using charged particle beams for cancer therapy and the programme began by covering the way in which particles interact with biological material, how this translates into the dose needed for treatment and how this dose is best delivered. The different accelerator options for providing the particles needed were then presented in some detail. The production of radioisotopes and how these are used for diagnostics and therapy was also covered, together with a look at novel acceleration techniques that may play a role i...

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

    International Nuclear Information System (INIS)

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

  6. 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.

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

    International Nuclear Information System (INIS)

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

  8. Sprint acceleration mechanics: the major role of hamstrings in horizontal force production

    Directory of Open Access Journals (Sweden)

    Jean-Benoit eMORIN

    2015-12-01

    Full Text Available Recent literature supports the importance of horizontal ground reaction force (GRF production for sprint acceleration performance. Modeling and clinical studies have shown that the hip extensors are very likely contributors to sprint acceleration performance. We experimentally tested the role of the hip extensors in horizontal GRF production during short, maximal, treadmill sprint accelerations. Torque capabilities of the knee and hip extensors and flexors were assessed using an isokinetic dynamometer in 14 males familiar with sprint running. Then, during 6-s sprints on an instrumented motorized treadmill, horizontal and vertical GRF were synchronized with electromyographic (EMG activity of the vastus lateralis, rectus femoris, biceps femoris and gluteus maximus averaged over the first half of support, entire support, entire swing and end-of-swing phases. No significant correlations were found between isokinetic or EMG variables and horizontal GRF. Multiple linear regression analysis showed a significant relationship (P = 0.024 between horizontal GRF and the combination of biceps femoris EMG activity during the end of the swing and the knee flexors eccentric peak torque. In conclusion, subjects who produced the greatest amount of horizontal force were both able to highly activate their hamstring muscles just before ground contact and present high eccentric hamstring peak torque capability.

  9. Current Outlook for 99mTc Distribution Based on Electron Accelerator Production

    Energy Technology Data Exchange (ETDEWEB)

    Benjamin L. Nelson; W. David Bence; John R. Snyder

    2007-07-01

    In 1999 a practical example illustrating the economical and reliable production of 99mTc from an accelerator was developed. It included the realistic costs involved in establishing and operating the accelerator facility and the distribution of the 99mTc to regions in Florida. However, the technology was never commercialized. Recent political and economic developments prompted this second look at accelerator produced 99mTc. The practicality of this system in 2007 dollars was established to account for inflation and current demand. The same distribution model and production schedule from the Global ‘99 study were used. Numbers were found using current rates and costs where possible and indexed estimations when necessary. Though several of the costs increased significantly and the sale price remains at approximately 35¢/mCi, the unit cost of 99mTc throughput only increased from 12.8¢/mCi to 15.0¢/mCi or approximately 17.2% from 1999 to 2007 thus continuing to be economically viable. This study provides ground work for creating business development models at additional locations within the U.S.

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

    International Nuclear Information System (INIS)

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

  11. Study of muon-induced neutron production using accelerator muon beam at CERN

    International Nuclear Information System (INIS)

    Cosmogenic muon-induced neutrons are one of the most problematic backgrounds for various underground experiments for rare event searches. In order to accurately understand such backgrounds, experimental data with high-statistics and well-controlled systematics is essential. We performed a test experiment to measure muon-induced neutron production yield and energy spectrum using a high-energy accelerator muon beam at CERN. We successfully observed neutrons from 160 GeV/c muon interaction on lead, and measured kinetic energy distributions for various production angles. Works towards evaluation of absolute neutron production yield is underway. This work also demonstrates that the setup is feasible for a future large-scale experiment for more comprehensive study of muon-induced neutron production

  12. VEDs for charged particle accelerators: Indian scenario

    International Nuclear Information System (INIS)

    In the initial times after their invention, the charged particle accelerators have, primarily, been used for fundamental studies on nuclei and atoms. From the first modern accelerator, the cathode ray tube, used by J.J. Thomson for the discovery of electron, very recently the gigantic 27 km circumference Large Hadron Collider (LHC) is operational in the search of Higg's boson and related physics issues. Particle accelerators have emerged as powerful microscopes for investigating the finest details of cells, genes, molecules, atoms, protons, neutrons, muons, electrons, quarks and, possibly, still undiscovered even more fundamental constituents of the universe, such as dark matter and dark energy. Several noble prize winning discoveries have been made using accelerators. Accelerators are now being used in a wide area of industrial and medical applications. They are used for the production of radioisotopes for medical imaging, cancer therapy, food sterilization, treatment of waste water, sterilization of medical equipment, material modification, mass spectroscopy, cargo scanning, fabrication of semiconductors etc. Ongoing effort towards the development of accelerators with megawatt beam power is showing hope for a cleaner source of nuclear energy and treatment of nuclear waste. Several tens of thousands of accelerators are presently operational in the world for basic research and applications. Development of new accelerators has several times been driven by new technologies and materials and sometimes they have driven the technological developments towards cutting edge. Some examples are ultra-high vacuum in large volumes, superfluid helium in cryogenics, cryocoolers, superconducting magnets and RF cavities, high power vacuum electronic devices, global control systems, superfast computing and communication networks, giant data storage/processing systems etc. India has been pursuing a fairly robust programme of accelerator development at various institutions. It

  13. Solid targetry at the TESLA Accelerator Installation

    International Nuclear Information System (INIS)

    According to the concept of the TESLA Accelerator Installation, the channel for production of radioisotopes has to routinely produce 201Tl, 111In, 67Ga, 123I and 18F, and a number of other radionuclides for experimental purposes. The production of 123I and 18F will be performed in dedicated, commercial target stations, while a versatile solid target irradiation system is designed for the routine and experimental production of all other radioisotopes. The solid target station is designed to accept targets for both the 7 deg. and 90 deg. irradiation geometry. The targets used for the routine production will be prepared by electroplating on a silver substrate. They can be irradiated with a 1.5 kW beam using the 7 deg. geometry. The cooling of these targets is enhanced by fins on the back of the silver substrate designed so that the highest temperature on the surface of the target does not exceed 110 deg. C. The irradiation procedures will conform to the GMP requirements for the production of radiopharmaceuticals. The irradiated targets will be transported directly into the appropriate hot cell for radiochemical processing. All cells will be equipped with a target dissolution unit for etching the irradiated, electroplated film. After decontamination and sufficient cooling down, these targets will be reused several times

  14. Evaluated activation cross-sections and intercomparison of the production parameters for the medically relevant radioisotopes 64Cu and 86Y

    Indian Academy of Sciences (India)

    A Sayed; A Elbinawi; M Al-Abyad; U Seddik; I I Bashter

    2015-04-01

    A theoretical study of the nuclear reaction cross-section for the production of 64Cu and 86Y was performed from the nuclear reactions 64Ni(p, n)64Cu, 64Ni(d, 2n)64Cu, 66Zn(d, )64Cu, 68Zn(p, n)64Cu, 86Sr(p, n)86gY, 87Sr(p, 2n)86gY and 88Sr(p, 3n)86gY. The calculations were performed using three codes EMPIRE, TALYS and ALICE-IPPE. The excitation function curves for the investigated reactions have been constructed from the enriched targets using 64Ni, 66Zn, 68Zn, 86Sr, 87Sr and 88Sr. The calculated excitation functions and the experimental data were compared. Mean standardized deviation, mean relative deviation and mean ratio statistical parameters were introduced to control the quality of the fitting between both the experimentally and the theoretically calculated cross-sections.

  15. INTELLIGENT PRODUCT BASED ON MOBILE AGENT TO ACCELERATE THE NEW PRODUCT DEVELOPMENT PROCESS

    Directory of Open Access Journals (Sweden)

    Abdelhak Boulaalam

    2013-01-01

    Full Text Available To improve the ever-increasing demands products that are customized, all business activities performed along the product life cycle must be coordinated and efficiently managed along the extended enterprise. For this, enterprise had wanted to retain control over the whole product lifecycle especially when the product is in use/repair/recycling (End of Life phase. Although there have been many previous research works about product lifecycle management in the Beginning of Life (BOL and Middle of Life (MOL phases, few addressed the End of Life (EOL phase, in particular. In this study, based on Auto-ID combined with mobile multi-agent system technologies, we will try to improve innovation: (a by minimize the lunch phase, (b and the involvement of the customer in product lifecycle (voice of customer."

  16. The Brazilian status on ADS R and D: Preliminary road map to a program on accelerator utilization on basic and applied nuclear physics, products and services and to drive an experimental neutron source sub critical facility

    International Nuclear Information System (INIS)

    Brazil, still a developing country, has an Industrial Nuclear Program, that although small has already achieved a good standard: two NPPs in operation, i.e., ANGRA I and II with 2 GW installed electric capacity are generating approximately 2% of the total installed electricity, a third unit under construction, a fuel cycle industry, INB, with the capability to provide fuel elements for the NPPs. The Brazilian Navy pursues a nuclear program for nuclear propulsion which includes all the front end of the fuel cycle, including the enrichment by ultracentrifuge that is being transferred also to the industrial sector (INB). Research and development is conducted by the various Research Institutes of the Brazilian Nuclear Energy Commission (CNEN): IPEN, CDTN, and IEN which have appropriate technical capability and facilities (research reactors and accelerators) to support the industrial nuclear program, provide products and services for the Brazilian society (e.g., radioisotopes), as well as to develop new technologies. It is fair to say, however, that the Brazilian research institutions do need some new challenges, mainly to motivate and to stimulate a new generation of young engineers and scientists to pursue careers in nuclear energy R and D. The Brazilian Nuclear Physics research, being pursued mainly by the Universities, has an outstanding standard. This is documented by the number of publications in international journals, scientific citations, the number and quality of scientists, and by its capability to form human resources (Ph.D. students). However, it is felt that this scientific potential, a few exceptions apart, still needs to transfer the benefits of the scientific knowledge to the Brazilian society. These boundary conditions call for a R and D program which identifies synergies, society needs, is in agreement with the international developments in science and technology, meets sustainability criteria, matches the Brazilian reality, provides an umbrella for

  17. The RF system for the Accelerator Production of Tritium (APT) Low Energy Demonstration Accelerator (LEDA) at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Lynch, M.T.; Rees, D.; Tallerico, P.; Regan, A. [Accelerator Operations & Technology Division, Los Alamos National Laboratory, Los Alamos, NM (United States)

    1996-09-01

    To develop and demonstrate the crucial front end of the APT accelerator and some of the critical components for APT, Los Alamos is building a CW proton accelerator (LEDA) to provide 100 mA at up to 40 MeV. LEDA will be installed where the SDI-sponsored Ground Test Accelerator was located. The first accelerating structure for LEDA is a 7-MeV RFQ operating at 350 MHz, followed by several stages of a coupled-cavity Drift Tube Linac (CCDTL) operating at 700 MHz. The first stage of LEDA will go to 12 MeV. Higher energies, up to 40 MeV, come later in the program. Three 1.2-MW CW RF systems will be used to power the RFQ. This paper describes the RF systems being assembled for LEDA, including the 350 and 700-MHz klystrons, the High Voltage Power Supplies, transmitters, RF transport, window/coupler assemblies, and controls. Some of the limitations imposed by the schedule and the building itself are addressed.

  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. Solid targetry at the TESLA Accelerator Installation

    CERN Document Server

    Comor, J J; Rajcevic, M; Kosutic, D; Spasic, M; Vidovic, A; Duricic, J; Nedeljkovic, N

    2002-01-01

    According to the concept of the TESLA Accelerator Installation, the channel for production of radioisotopes has to routinely produce sup 2 sup 0 sup 1 Tl, sup 1 sup 1 sup 1 In, sup 6 sup 7 Ga, sup 1 sup 2 sup 3 I and sup 1 sup 8 F, and a number of other radionuclides for experimental purposes. The production of sup 1 sup 2 sup 3 I and sup 1 sup 8 F will be performed in dedicated, commercial target stations, while a versatile solid target irradiation system is designed for the routine and experimental production of all other radioisotopes. The solid target station is designed to accept targets for both the 7 deg. and 90 deg. irradiation geometry. The targets used for the routine production will be prepared by electroplating on a silver substrate. They can be irradiated with a 1.5 kW beam using the 7 deg. geometry. The cooling of these targets is enhanced by fins on the back of the silver substrate designed so that the highest temperature on the surface of the target does not exceed 110 deg. C. The irradiation ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-10-01

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

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

    International Nuclear Information System (INIS)

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

  2. A cord blood monocyte–derived cell therapy product accelerates brain remyelination

    Science.gov (United States)

    Buntz, Susan; Scotland, Paula; Xu, Li; Noeldner, Pamela; Patel, Sachit; Wollish, Amy; Gunaratne, Aruni; Gentry, Tracy; Matsushima, Glenn K.; Kurtzberg, Joanne; Balber, Andrew E.

    2016-01-01

    Microglia and monocytes play important roles in regulating brain remyelination. We developed DUOC-01, a cell therapy product intended for treatment of demyelinating diseases, from banked human umbilical cord blood (CB) mononuclear cells. Immunodepletion and selection studies demonstrated that DUOC-01 cells are derived from CB CD14+ monocytes. We compared the ability of freshly isolated CB CD14+ monocytes and DUOC-01 cells to accelerate remyelination of the brains of NOD/SCID/IL2Rγnull mice following cuprizone feeding–mediated demyelination. The corpus callosum of mice intracranially injected with DUOC-01 showed enhanced myelination, a higher proportion of fully myelinated axons, decreased gliosis and cellular infiltration, and more proliferating oligodendrocyte lineage cells than those of mice receiving excipient. Uncultured CB CD14+ monocytes also accelerated remyelination, but to a significantly lesser extent than DUOC-01 cells. Microarray analysis, quantitative PCR studies, Western blotting, and flow cytometry demonstrated that expression of factors that promote remyelination including PDGF-AA, stem cell factor, IGF1, MMP9, MMP12, and triggering receptor expressed on myeloid cells 2 were upregulated in DUOC-01 compared to CB CD14+ monocytes. Collectively, our results show that DUOC-01 accelerates brain remyelination by multiple mechanisms and could be beneficial in treating demyelinating conditions. PMID:27699230

  3. Production Level CFD Code Acceleration for Hybrid Many-Core Architectures

    Science.gov (United States)

    Duffy, Austen C.; Hammond, Dana P.; Nielsen, Eric J.

    2012-01-01

    In this work, a novel graphics processing unit (GPU) distributed sharing model for hybrid many-core architectures is introduced and employed in the acceleration of a production-level computational fluid dynamics (CFD) code. The latest generation graphics hardware allows multiple processor cores to simultaneously share a single GPU through concurrent kernel execution. This feature has allowed the NASA FUN3D code to be accelerated in parallel with up to four processor cores sharing a single GPU. For codes to scale and fully use resources on these and the next generation machines, codes will need to employ some type of GPU sharing model, as presented in this work. Findings include the effects of GPU sharing on overall performance. A discussion of the inherent challenges that parallel unstructured CFD codes face in accelerator-based computing environments is included, with considerations for future generation architectures. This work was completed by the author in August 2010, and reflects the analysis and results of the time.

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

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A.

    1985-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-08-01

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

  6. Beam line shielding calculations for an Electron Accelerator Mo-99 production facility

    Energy Technology Data Exchange (ETDEWEB)

    Mocko, Michal [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-05-03

    The purpose of this study is to evaluate the photon and neutron fields in and around the latest beam line design for the Mo-99 production facility. The radiation dose to the beam line components (quadrupoles, dipoles, beam stops and the linear accelerator) are calculated in the present report. The beam line design assumes placement of two cameras: infra red (IR) and optical transition radiation (OTR) for continuous monitoring of the beam spot on target during irradiation. The cameras will be placed off the beam axis offset in vertical direction. We explored typical shielding arrangements for the cameras and report the resulting neutron and photon dose fields.

  7. A Los Alamos concept for accelerator transmutation of waste and energy production (ATW)

    International Nuclear Information System (INIS)

    This document contains the diagrams presented at the ATW (Accelerator Transmutation of Waste and Energy Production) External Review, December 10-12, 1990, held at Los Alamos National Laboratory. Included are the charge to the committee and the presentations for the committee's review. Topics of the presentations included an overview of the concept, LINAC technology, near-term application -- high-level defense wastes (intense thermal neutron source, chemistry and materials), advanced application of the ATW concept -- fission energy without a high-level waste stream (overview, advanced technology, and advanced chemistry), and a summary of the research issues

  8. Radioisotopes: problems of responsibility arising from medicine

    International Nuclear Information System (INIS)

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

  9. Radioisotope Power Systems Technology Development Project

    Data.gov (United States)

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

  10. Over-the-road shock and vibration testing of the radioisotope thermoelectric generator transportation system

    International Nuclear Information System (INIS)

    Radioisotope Thermoelectric Generators (RTG) convert heat generated by radioactive decay into electricity through the use of thermocouples. The RTGs have a long operating life, are reasonably lightweight, and require little or no maintenance, which make them particularly attractive for use in spacecraft. However, because RTGs contain significant quantities of radioactive materials, normally plutonium-238 and its decay products, they must be transported in packages built in accordance with Title 10, Code of Federal Regulations, Part 71 (10 CFR 71). To meet these regulations, a RTG Transportation System (RTGTS) that fully complies with 10 CFR 71 has been developed, which protects RTGs from adverse environmental conditions during normal conditions of transport (e.g., shock, vibration, and heat). To ensure the protection of RTGs from shock and vibration loadings during transport, extensive over-the-road testing was conducted on the RTG'S to obtain real-time recordings of accelerations of the air-ride suspension system trailer floor, packaging, and support structure. This paper provides an overview of the RTG'S, a discussion of the shock and vibration testing, and a comparison of the test results to the specified shock response spectra and power spectral density acceleration criteria

  11. Activation products in a treatment room of a 15 MV linear accelerator for medical use

    Energy Technology Data Exchange (ETDEWEB)

    De Leon M, H. A.; Soto B, T. G.; Rivera P, E.; Hernandez D, V. M.; Vega C, H. R., E-mail: asa_15@hotmail.com [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Apdo. Postal 336, 98000 Zacatecas (Mexico)

    2012-10-15

    Linacs working above 8 MV produce an undesirable neutron field mainly through ({gamma}, n) nuclear reactions. Due to room-return effect inside the vault there is a thermal neutron flux that is constant regarded the distance to the isocenter. When thermal neutrons collide with the bunker walls and the Linac head some radioisotopes are induced in the concrete, wedges and collimators due to neutron and photon activation. The aim of this work is to study the induced radioisotopes in concrete samples and a wedge, which emits gamma-ray during its decay, the presence of this protons will represent a radiological risk for the patient. Induced radioisotopes were studied with a 15 MV Linac, and a gamma-ray spectrometer with a Nal(Tl) scintillator where 846.8, 1368.6 and 1778.8 keV gamma-rays were observed, these photons are produced during the decay of {sup 54}Mn, {sup 24}Na and {sup 28}Al respectively, being in agreement with radionuclides reported in the literature. (Author)

  12. Artificial radioisotopes in food chains

    International Nuclear Information System (INIS)

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

  13. Development of radioisotope tracer technology

    International Nuclear Information System (INIS)

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

  14. Development of radioisotope tracer technology

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-04-01

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

  15. Target/Blanket Design for the Accelerator Production of Tritium Plant

    International Nuclear Information System (INIS)

    The Accelerator Production of Tritium Target/Blanket (T/B) system is comprised of an assembly of tritium-producing modules supported by safety, heat removal, shielding, and retargeting systems. The T/B assembly produces tritium using a high-energy proton beam, a tungsten/lead spallation neutron source and 3He gas as the tritium-producing feedstock. The supporting heat removal systems remove the heat deposited by the proton beam during both normal and off-normal conditions. The shielding protects workers from ionizing radiation, and the retargeting systems remove and replace components that have reached their end of life. All systems reside within the T/B building, which is located at the end of a linear accelerator. For the nominal production mode, protons are accelerated to an energy of 1030 MeV at a current of 100 mA and are directed onto the T/B assembly. The protons are expanded to a 0.19- x 1.9-m beam spot before striking a centrally located tungsten neutron source. A surrounding lead blanket produces additional neutrons from scattered high-energy particles. A total of 27 neutrons are produced per incident proton. Tritium is produced by neutron capture in 3He gas that is contained in aluminum tubes throughout the blanket. The 3He/tritium mixture is removed on a semi-continuous basis for purification in an adjacent Tritium Separation Facility. Systems and components are designed with safety as a primary consideration to minimize risk to the workers and the public. Materials and component designs were chosen based on the experiences of operating spallation neutron sources that have been designed and built for the neutron science community. An extensive engineering development and demonstration program provides detailed information for the completion of the design

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

    International Nuclear Information System (INIS)

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

  17. 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.

  18. Production of clinical useful quantities of 18 F by an electrostatic tandem accelerator

    International Nuclear Information System (INIS)

    The 3 MV electrostatic tandem accelerator in Lund, Sweden, is routinely used for production of the short lived (half-life 110 minutes) isotope 18 F. A beam of 5.7 MeV protons irradiates an open silver-target containing 0.5 ml H218 O water, enriched to 97%. Using a beam current of 10-12 mA and an irradiation time of 60-120 minutes, the nuclear reaction 18 O(p,n)18 F gives a 18 F-yield of typically 2.7-4.5 GBq. The produced 18 F is used for synthesis of 2-18 FDG. This radio pharmaceutical (an analogue to glucose) is used in oncological positron emission tomography (PET) studies at the nearby hospital. In this report technical details of the production, as well as a short outline of the synthesis and application in oncology, are given. (authors)

  19. Microbial electrolysis contribution to anaerobic digestion of waste activated sludge, leading to accelerated methane production

    DEFF Research Database (Denmark)

    Liu, Wenzong; Cai, Weiwei; Guo, Zechong;

    2016-01-01

    Methane production rate (MPR) in waste activated sludge (WAS) digestion processes is typically limitedby the initial steps of complex organic matter degradation, leading to a limited MPR due to sludgefermentation speed of solid particles. In this study, a novel microbial electrolysis AD reactor (ME......-AD) wasused to accelerate methane production for energy recovery from WAS. Carbon bioconversion wasaccelerated by ME producing H2 at the cathode. MPR was enhanced to 91.8 gCH4/m3 reactor/d in themicrobial electrolysis ME-AD reactor, thus improving the rate by 3 times compared to control conditions (30.6 gCH4......-AD reactor allowed to significantly enhance carbon degradation and methaneproduction from WAS....

  20. Production and isolation of homologs of flerovium and element 115 at the Lawrence Livermore National Laboratory Center for Accelerator Mass Spectrometry

    International Nuclear Information System (INIS)

    New procedures have been developed to isolate no-carrier-added (NCA) radionuclides of the homologs and pseudo-homologs of flerovium (Hg, Sn) and element 115 (Sb), produced by 12-15 MeV proton irradiation of foil stacks with the tandem Van-de-Graaff accelerator at the Lawrence Livermore National Laboratory Center for Accelerator Mass Spectrometry (CAMS) facility. The separation of 113Sn from natIn foil was performed with anion-exchange chromatography from hydrochloric and nitric acid matrices. A cation-exchange chromatography method based on hydrochloric and mixed hydrochloric/ hydroiodic acids was used to separate 124Sb from natSn foil. A procedure using Eichrom TEVA resin was developed to separate 197Hg from Au foil. These results demonstrate the suitability of using the CAMS facility to produce NCA radioisotopes for studies of transactinide homologs. (author)

  1. Simulations of slow positron production using a low energy electron accelerator

    CERN Document Server

    O'Rourke, B E; Kinomura, A; Kuroda, R; Minehara, E; Ohdaira, T; Oshima, N; Suzuki, R

    2011-01-01

    Monte Carlo simulations of slow positron production via energetic electron interaction with a solid target have been performed. The aim of the simulations was to determine the expected slow positron beam intensity from a low energy, high current electron accelerator. By simulating (a) the fast positron production from a tantalum electron-positron converter and (b) the positron depth deposition profile in a tungsten moderator, the slow positron production probability per incident electron was estimated. Normalizing the calculated result to the measured slow positron yield at the present AIST LINAC the expected slow positron yield as a function of energy was determined. For an electron beam energy of 5 MeV (10 MeV) and current 240 $\\mu$A (30 $\\mu$A) production of a slow positron beam of intensity 5 $\\times$ 10$^{6}$ s$^{-1}$ is predicted. The simulation also calculates the average energy deposited in the converter per electron, allowing an estimate of the beam heating at a given electron energy and current. For...

  2. Radiation protection system installation for the accelerator production of tritium/low energy demonstration accelerator project (APT/LEDA)

    CERN Document Server

    Wilmarth, J E; Tomei, T L

    2000-01-01

    The APT/LEDA personnel radiation protection system installation was accomplished using a flexible, modular proven system which satisfied regulatory orders, project design criteria, operational modes, and facility requirements. The goal of providing exclusion and safe access of personnel to areas where prompt radiation in the LEDA facility is produced was achieved with the installation of a DOE-approved Personnel Access Control System (PACS). To satisfy the facility configuration design, the PACS, a major component of the overall radiation safety system, conveniently provided five independent areas of personnel access control. Because of its flexibility and adaptability the Los-Alamos Neutron- Science-Center-(LANSCE)-designed Radiation Security System (RSS) was efficiently configured to provide the desired operational modes and satisfy the APT/LEDA project design criteria. The Backbone Beam Enable (BBE) system based on the LANSCE RSS provided the accelerator beam control functions with redundant, hardwired, ta...

  3. Electron Acceleration and Ionization Production in High-Power Heating Experiments at HAARP

    Science.gov (United States)

    Mishin, E. V.; Pedersen, T.

    2012-12-01

    Recent ionospheric modification experiments with the 3.6 MW transmitter at the High Frequency Active Auroral Research Program (HAARP) facility in Alaska led to discovery of artificial ionization descending from the nominal interaction altitude in the background F-region ionosphere by ~60-80 km. Artificial ionization production is indicated by significant 427.8 nm emissions from the 1st negative band of N2+ and the appearance of transmitter-induced bottomside traces in ionosonde data during the periods of most intense optical emissions. However, the exact mechanisms producing the artificial plasmas remain to be determined. Yet the only existing theoretical models explain the development of artificial plasma as an ionizing wavefront moving downward due to ionization by electrons accelerated by HF-excited strong Langmuir turbulence (SLT) generated near the plasma resonance, where the pump frequency matches the plasma frequency. However, the observations suggest also the significance of interactions with upper hybrid and electron Bernstein waves near multiples of the electron gyrofrequency. We describe recent observations and discuss suitable acceleration mechanisms.

  4. Study of medical RI production with accelerator-based neutron sources

    International Nuclear Information System (INIS)

    The single-photon emission computed tomography (SPECT) and positron emission tomography (PET) have been widely adopted for nuclear medicine imaging to make diagnoses of body functions, identification of site of cancers, and so on. Now, almost all of medical radio isotopes are produced by nuclear reactors or charged particle accelerators. We propose a new route to produce the medical radio isotopes with accelerator-based neutron sources. In this paper, as an example, we introduce the proposed production method of 99Mo, which is the mother nuclide of 99mTc for SPECT. We determined the 100Mo(n,2n)99Mo reaction cross section to 1,415±82mb and it was consistent with the value (1,398mb) obtained from JENDL-4.0. Therefore, it indicates yields of produced RIs can be predicted with nuclear data based simulations. The simulation also can be used to design irradiation condition. In this paper some results of the simulations are also shown. (author)

  5. A 50-MeV mm-wave electron linear accelerator system for production of tunable short wavelength synchrotron radiation

    International Nuclear Information System (INIS)

    The Advanced Photon Source (APS) at Argonne in collaboration with the University of Illinois at Chicago and the University of Wisconsin at Madison is developing a new millimeter wavelength, 50-MeV electron linear accelerator system for production of coherent tunable wavelength synchrotron radiation. Modern micromachining techniques based on deep etch x-ray lithography, LIGA (Lithografie, Galvanoformung, Abformung), capable of producing high-aspect ratio structures are being considered for the fabrication of the accelerating components

  6. Near-threshold pion production with radioactive beams at the Rare Isotope Accelerator

    CERN Document Server

    Li, B A; Zuo, W; Li, Bao-An; Yong, Gao-Chan; Zuo, Wei

    2005-01-01

    Using an isospin- and momentum-dependent transport model we study near-threshold pion production in heavy-ion collisions induced by radioactive beams at the planned Rare Isotope Accelerator (RIA). We revisit the question of probing the high density behavior of nuclear symmetry energy $E_{sym}(\\rho)$ using the $\\pi^-/\\pi^+$ ratio. It is found that both the total and differential $\\pi^-/\\pi^+$ ratios remain sensitive to the $E_{sym}(\\rho)$ when the momentum-dependence of both the isoscalar and isovector potentials are consistently taken into account. Moreover, the multiplicity and spectrum of $\\pi^-$ mesons are found more sensitive to the $E_{sym}(\\rho)$ than those of $\\pi^+$ mesons. Finally, effects of the Coulomb potential on the pion spectra and $\\pi^-/\\pi^+$ ratio are also discussed.

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

    International Nuclear Information System (INIS)

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

  8. A neutron booster for spallation sources—application to accelerator driven systems and isotope production

    Science.gov (United States)

    Galy, J.; Magill, J.; Van Dam, H.; Valko, J.

    2002-06-01

    One can design a critical system with fissile material in the form of a thin layer on the inner surface of a cylindrical neutron moderator such as graphite or beryllium. Recently, we have investigated the properties of critical and near critical systems based on the use of thin actinide layers of uranium, plutonium and americium. The thickness of the required fissile layer depends on the type of fissile material, its concentration in the layer and on the geometrical arrangement, but is typically in the μm-mm range. The resulting total mass of fissile material can be as low as 100 g. Thin fissile layers have a variety of applications in nuclear technology—for example in the design neutron amplifiers for medical applications and "fast" islands in thermal reactors for waste incineration. In the present paper, we investigate the properties of a neutron booster unit for spallation sources and isotope production. In those applications a layer of fissile material surrounds the spallation source. Such a module could be developed for spallation targets foreseen in the MYRRHA (L. Van Den Durpel, H. Aı̈t Abderrahim, P. D'hondt, G. Minsart, J.L. Bellefontaine, S. Bodart, B. Ponsard, F. Vermeersch, W. Wacquier. A prototype accelerator driven system in Belgium: the Myrrha project, Technical Committee Meeting on Feasibility and Motivation for Hybrid concepts for Nuclear Energy generation and Transmutation, Madrid, Spain, September 17-19, 1997 [1]). or MEGAPIE (M. Salvatores, G.S. Bauer, G. Heusener. The MEGAPIE initiative: executive outline and status as per November 1999, MPO-1-GB-6/0_GB, 1999 [2]) projects. With a neutron multiplication factor of the booster unit in the range 10-20 (i.e. with a keff of 0.9-0.95), considerably less powerful accelerators would be required to obtain the desired neutron flux. Instead of the powerful accelerators with proton energies of 1 GeV and currents of 10 mA foreseen for accelerator driven systems, similar neutron fluxes can be obtained

  9. Quantification of the production of hydrogen peroxide H2O2 during accelerated wine oxidation.

    Science.gov (United States)

    Héritier, Julien; Bach, Benoît; Schönenberger, Patrik; Gaillard, Vanessa; Ducruet, Julien; Segura, Jean-Manuel

    2016-11-15

    Understanding how wines react towards oxidation is of primary importance. Here, a novel approach was developed based on the quantitative determination of the key intermediate H2O2 produced during accelerated oxidation by ambient oxygen. The assay makes use of the conversion of the non-fluorescent Amplex Red substrate into a fluorescent product in presence of H2O2. The total production of H2O2 during 30min was quantified with low within-day and between-day variabilities. Polymerized pigments, but not total polyphenols, played a major role in the determination of H2O2 levels, which were lower in white wines than red wines. H2O2 amounts also increased with temperature and the addition of metal ions, but did not depend on the concentration of many other wine constituents such as SO2. H2O2 levels did not correlate with anti-oxidant properties. We believe that this novel methodology might be generically used to decipher the oxidation mechanisms in wines and food products. PMID:27283717

  10. 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.

  11. Acceleration of Topographic Map Production Using Semi-Automatic DTM from Dsm Radar Data

    Science.gov (United States)

    Rizaldy, Aldino; Mayasari, Ratna

    2016-06-01

    Badan Informasi Geospasial (BIG) is government institution in Indonesia which is responsible to provide Topographic Map at several map scale. For medium map scale, e.g. 1:25.000 or 1:50.000, DSM from Radar data is very good solution since Radar is able to penetrate cloud that usually covering tropical area in Indonesia. DSM Radar is produced using Radargrammetry and Interferrometry technique. The conventional method of DTM production is using "stereo-mate", the stereo image created from DSM Radar and ORRI (Ortho Rectified Radar Image), and human operator will digitizing masspoint and breakline manually using digital stereoplotter workstation. This technique is accurate but very costly and time consuming, also needs large resource of human operator. Since DSMs are already generated, it is possible to filter DSM to DTM using several techniques. This paper will study the possibility of DSM to DTM filtering using technique that usually used in point cloud LIDAR filtering. Accuracy of this method will also be calculated using enough numbers of check points. If the accuracy meets the requirement, this method is very potential to accelerate the production of Topographic Map in Indonesia.

  12. Lithium antineutrino source in the tandem scheme of the accelerator and neutron producting tungsten target

    CERN Document Server

    Lyashuk, V I

    2016-01-01

    The antineutrinos of the neutron rich 8Li isotope is characterized by hard and good defined spectrum - averaged energy is 6.5 MeV and maximal - up to 13 MeV. An intensive antineutrino source with such parameters can be unique instrument for neutrino investigations and especially for search of sterile neutrinos. The 8Li can be produced by (n,gamma)-activation of 7Li isotope. The proposed scheme of the antineutrino source is based on the lithium blanket around the accelerator neutron producting target. We propose to use heavy water solution of the lithium hydroxide instead of lithium in metallic state. Such solution for lithium blanket substance ensure the large perspectives in real steps for creation of this installation. An analyses of neutron fields in the blanket and distribution of 8Li creation allows to propose the next principal steps in the construction of the lithium blanket. We propose to enclose the blanket volume isolating it's central part with more high 8Li production. This solution allows to decr...

  13. LLNL review of the 1994 accelerator production of tritium (APT) concept

    Energy Technology Data Exchange (ETDEWEB)

    Alesso, H.P.; Barnard, J.J.; Booth, R. [and others

    1995-03-08

    LLNL was asked in September 1994 to review the accelerator production of tritium (APT) concept as it had evolved up to the fall of 1994. The purpose was not to compare it to other sources of tritium, but to identify possible technical flaws in the concept and to assess feasibility. The APT concept reviewed was based on a 1.0 GeV normal conducting proton linac operating CW at currents up to 200 mA with a target of tungsten and blanket of {sup 3}He and lead. The LLNL review group concurs with the conclusions of four previous reviews (1989 to 1994) that this concept can meet the tritium requirements of a reduced stockpile of approximately 3,500 {+-} 1,500 warheads. The authors believe that the predicted tritium production rate is based on sound nuclear and transport models and that the schedules for technology demonstrations, design, and construction are realistic. They conclude that the technical risk of the concept is low and can be managed within the risk reduction program. The risk reduction program should focus on risk to the schedule and on cost reduction.

  14. Draft safety review plan for accelerator production of tritium (APT) project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The purpose of this ``living`` Safety Review Plan (SRP) is to describe the products and processes that will be followed to conduct a systematic review of the Accelerator Production of Tritium (APT) Facility Preliminary Safety Analysis Report (PSAR), and subsequently to prepare a draft Safety Evaluation Report (SER) on the PSAR. This plan is prepared for and will be implemented by the APT Independent Safety Review Committee (ISRC) over the period July 1, 1997 through September 30, 1998, in accordance with provisions established in DOE-STD-1104-96. A core team of DOE, INEEL, and AMPARO Corporation engineers and scientists will prepare the initial draft SER with assistance from other ISRC team members on an as needed basis. Guidelines for preparing the draft SER are presented in Section 7 of this SRP. The PSAR reviews will focus exclusively on safety. The ever-present two-part question will be: Does the subject matter have safety significance? If so, does the APT structural, system, component, and/or process engineering design ensure an acceptable margin of safety? The APT mission, efficiency, and cost are not considerations of this plan. A more detailed discussion of the review philosophy is presented in Section 5 of this SRP.

  15. Nuclear Data Requirements for the Production of Medical Isotopes in Fission Reactors and Particle Accelerators

    CERN Document Server

    Garland, M A; Talbert, R J; Mashnik, S G; Wilson, W B

    1999-01-01

    Through decades of effort in nuclear data development and simulations of reactor neutronics and accelerator transmutation, a collection of reaction data is continuing to evolve with the potential of direct applications to the production of medical isotopes. At Los Alamos the CINDER'90 code and library have been developed for nuclide inventory calculations using neutron-reaction (En < 20 MeV) and/or decay data for 3400 nuclides; coupled with the LAHET Code System (LCS), irradiations in neutron and proton environments below a few GeV are tractable; additional work with the European Activation File, the HMS-ALICE code and the reaction models of MCNPX (CEM95, BERTINI, or ISABEL with or without preequilibrium, evaporation and fission) have been used to produce evaluated reaction data for neutrons and protons to 1.7 GeV. At the Pacific Northwest National Laboratory, efforts have focused on production of medical isotopes and the identification of available neutron reaction data from results of integral measuremen...

  16. Radioisotopes and food preservation against insects

    International Nuclear Information System (INIS)

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

  17. 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…

  18. Calorimetric measurement of afterheat in target materials for the accelerator production of tritium

    International Nuclear Information System (INIS)

    The estimate of afterheat in a spallation target of lead (Pb) or tungsten (W), by calorimetry, is the purpose of this experiment in support of the Accelerator Production of Tritium (APT). Such measurements are needed to confirm code calculations, these being the only practical way of gaining this type of information in a form suitable to aid the design of the APT machine. Knowledge of the magnitude and duration of afterheat resulting from decay of activation products produced by proton bombardment of the target is necessary to quantify APT safety assumptions, to design target cooling and safety systems, and to reduce technical risk. Direct calorimetric measurement of the afterheat for the appropriate incident proton energies is more reliable than the available alternative, which is indirect, based on data from gamma-ray spectroscopy measurements. The basic concept, a direct measurement of decay afterheat which bypasses the laborious classical way of determining this quantity, has been demonstrated to work. The gamma-ray energy given off by the decay products produced in the activation of lead or tungsten with high-energy protons apparently does represent a significant fraction of the total decay energy. A calorimeter designed for measurement of isotopes decaying by alpha emission must be modified to reduce energy lost with escaping gamma rays. Replacement of the aluminum liner with a tungsten liner in the SSC measurement chamber resulted in a 270% increase in measured heat, proving that the energy loss in the earlier (1992) measurements was significant. Gamma-ray measurements are needed to confirm the gamma-ray absorption calculations for the calorimeter to determine the correction for loss of heat due to transmission of high-energy gamma rays through the calorimeter walls. The experiments at BLIP have shown that calorimetry can be a useful tool in measuring the afterheat in APT target materials

  19. Particle Accelerator Applications: Ion and Electron Irradiation in Materials Science, Biology and Medicine

    Science.gov (United States)

    Rodríguez-Fernández, Luis

    2010-09-01

    Although the developments of particle accelerators are devoted to basic study of matter constituents, since the beginning these machines have been applied with different purposes in many areas also. Today particle accelerators are essential instruments for science and technology. This work presents an overview of the main application for direct particle irradiation with accelerator in material science, biology and medicine. They are used for material synthesis by ion implantation and charged particle irradiation; to make coatings and micromachining; to characterize broad kind of samples by ion beam analysis techniques; as mass spectrometers for atomic isotopes determination. In biomedicine the accelerators are applied for the study of effects by charged particles on cells. In medicine the radiotherapy by electron irradiation is widely used, while hadrontherapy is still under development. Also, they are necessary for short life radioisotopes production required in radiodiagnostic.

  20. Particle Accelerator Applications: Ion and Electron Irradiation in Materials Science, Biology and Medicine

    International Nuclear Information System (INIS)

    Although the developments of particle accelerators are devoted to basic study of matter constituents, since the beginning these machines have been applied with different purposes in many areas also. Today particle accelerators are essential instruments for science and technology. This work presents an overview of the main application for direct particle irradiation with accelerator in material science, biology and medicine. They are used for material synthesis by ion implantation and charged particle irradiation; to make coatings and micromachining; to characterize broad kind of samples by ion beam analysis techniques; as mass spectrometers for atomic isotopes determination. In biomedicine the accelerators are applied for the study of effects by charged particles on cells. In medicine the radiotherapy by electron irradiation is widely used, while hadrontherapy is still under development. Also, they are necessary for short life radioisotopes production required in radiodiagnostic.

  1. 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)

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

    International Nuclear Information System (INIS)

    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)

  3. Thermal test of noncombustible urethane for applying to type B packages for radioisotope

    International Nuclear Information System (INIS)

    The package to safely transport the radioisotope, which is produced from HANARO, has to be developed to establish the distribution system of the radioisotope from production to consumption. KAERI is developing the type B package for Ir-192 600 ci. The type B package must be able to endure from thermal condition of 800 .deg. C. However, it is very difficult that the polyurethane, which is used as shock absorber, is maintained less than 327 .deg. C that is melting point of lead used as shielding material. Therefore, the specimens, which are applied noncombustible urethane and fireproof materials, are made. The experimental estimation for thermal condition of 800 .deg. C was conducted

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  6. Preliminary consideration of a double, 480 GeV, fast cycling proton accelerator for production of neutrino beams at Fermilab

    Energy Technology Data Exchange (ETDEWEB)

    Piekarz, Henryk; Hays, Steven; /Fermilab

    2007-03-01

    We propose to build the DSF-MR (Double Super-Ferric Main Ring), 480 GeV, fast-cycling (2 second repetition rate) two-beam proton accelerator in the Main Ring tunnel of Fermilab. This accelerator design is based on the super-ferric magnet technology developed for the VLHC, and extended recently to the proposed LER injector for the LHC and fast cycling SF-SPS at CERN. The DSF-MR accelerator system will constitute the final stage of the proton source enabling production of two neutrino beams separated by 2 second time period. These beams will be sent alternately to two detectors located at {approx} 3000 km and {approx} 7500 km away from Fermilab. It is expected that combination of the results from these experiments will offer more than 3 order of magnitudes increased sensitivity for detection and measurement of neutrino oscillations with respect to expectations in any current experiment, and thus may truly enable opening the window into the physics beyond the Standard Model. We examine potential sites for the long baseline neutrino detectors accepting beams from Fermilab. The current injection system consisting of 400 MeV Linac, 8 GeV Booster and the Main Injector can be used to accelerate protons to 45 GeV before transferring them to the DSF-MR. The implementation of the DSF-MR will allow for an 8-fold increase in beam power on the neutrino production target. In this note we outline the proposed new arrangement of the Fermilab accelerator complex. We also briefly describe the DSF-MR magnet design and its power supply, and discuss necessary upgrade of the Tevatron RF system for the use with the DSF-MR accelerator. Finally, we outline the required R&D, cost estimate and possible timeline for the implementation of the DSF-MR accelerator.

  7. Development of Next Generation Segmented Thermoelectric Radioisotope Power Systems

    Science.gov (United States)

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

    2005-12-01

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

  8. Educational applications on particle accelerators in Brazil

    International Nuclear Information System (INIS)

    The Brazilian production of radiopharmaceuticals and radioisotopes for medical usage dates back to the 70's, since the beginning up to 2006; it was a monopoly of the government-owned corporations. After the market was open for the private enterprise, the quantity of small particle accelerators is increasing. The difficulties are many, from industry installation to the hard time on finding qualified personnel. The lack of investment on this area brought few trained people and the trained ones keep working in the government laboratories. Facing this issue, a strong program was started on training and educating people on universities, businesses enterprises and at hospitals in order to increase the human resources capabilities in the country. Activities such as laboratory research and lectures are being made as well in order to adapt Brazil to the renascence of the nuclear technology and increase the knowledge in the field of particle accelerators. These investments on education are preparing professionals in several areas, such as: physics, engineering, pharmacy, medicine, administration, among others. It started on the universities not only with lectures and workshops, but also with research partnerships on the stand-by time of the particle accelerators. At clinics and hospitals the efforts are focused in the improvement and training of the particle accelerator product applications. One of the private enterprise corporations has trained more than 30 people from five different states and established partnership with five different universities, qualifying people on installation, operation, maintenance and administration of the whole process of implementation of a particle accelerator site. It's also collaborating with the universities and researchers in the development of new techniques: the irradiation of other material targets or the use of non-usual particle beams, allowing the study of the nuclear activation of the concrete walls of the particle accelerator

  9. Accelerating the explicitly restarted Arnoldi method with GPUs using an auto-tuned matrix vector product

    International Nuclear Information System (INIS)

    This paper presents a parallelized hybrid single-vector Arnoldi algorithm for computing approximations to Eigen-pairs of a nonsymmetric matrix. We are interested in the use of accelerators and multi-core units to speed up the Arnoldi process. The main goal is to propose a parallel version of the Arnoldi solver, which can efficiently use multiple multi-core processors or multiple graphics processing units (GPUs) in a mixed coarse and fine grain fashion. In the proposed algorithms, this is achieved by an auto-tuning of the matrix vector product before starting the Arnoldi Eigen-solver as well as the reorganization of the data and global communications so that communication time is reduced. The execution time, performance, and scalability are assessed with well-known dense and sparse test matrices on multiple Nehalems, GT200 NVidia Tesla, and next generation Fermi Tesla. With one processor, we see a performance speedup of 2 to 3x when using all the physical cores, and a total speedup of 2 to 8x when adding a GPU to this multi-core unit, and hence a speedup of 4 to 24x compared to the sequential solver. (authors)

  10. Performance Acceleration on Production Machines Using the Overall Equipment Effectiveness (OEE) Approach

    Science.gov (United States)

    Mansur, A.; Rayendra, R.; Mastur, MI

    2016-01-01

    Mistakes during working can trigger a decrease in production level that may lead financial loss to the company. The factors that affect the mistakes are called losses, such as breakdown loss, set up/ adjustment loss, idling and minor stoppage loss, reduced speed loss, reduced yield loss, and rework loss. The objective of the research is to accelerate the performance of the JSW 330T machine in PT. YogyaPresisiTehnikatamaIndustri. JSW 330T is a machine that has the highest downtime numbers. The method for measuring the effectiveness is using the Overall Equipment Effectiveness (OEE). The results of the research show that the JWQ 330T has average rate of the effectiveness (OEE) of 52.66%, availability ratioof 73.43%, performance efficiency rate of 83.58% and quality rate of 84.6%. From the six big losses calculation, the factor that affects the most on the low score of OEE is the breakdown loss which is 58.85% with total time loss of 929.65 hours in a year.

  11. Production Of Intense, Tunable, Quasi-monochromatic X- Rays Using The Rpi Linear Accelerator

    CERN Document Server

    Sones, B A

    2004-01-01

    This research investigated the production of parametric X-rays (PXR) using the 60-MeV electron linear accelerator at Rensselaer Polytechnic Institute. PXR is an intense, energy tunable, and polarized X-ray source derived from the interaction of relativistic electrons and the periodic structure of crystal materials. In this work, PXR photon yields and the associated bremsstrahlung background were characterized for graphite, LiF, Si, Ge, Cu, and W target crystals. A model that considers the experimental geometry and crystal mosaicity was employed to predict PXR energy broadening. Measured energy linewidths consistently agreed with predicted values except in cases using poor quality graphite in which the mosaicity was greater than the PXR characteristic angle, 8.5 mrad for 60 MeV electrons. When the predicted energy linewidth was more narrow than our Si X-ray detector resolution, a near-absorption edge transmission technique was used to measure the PXR energy linewidth for Si(400) FWHM of 134 eV at 9.0 keV (2%) ...

  12. Experimental facilities for quasimonochromatic polarized photon beam production in the Kharkov linear accelerator

    International Nuclear Information System (INIS)

    A set of equipment designed to obtain quasimonochromatic linearly polarized high-energy photons in a linear accelerator is described. A beam of quasimonochromatic linearly polarized photons was obtained by coherent bremsstrahlung of electrons in diamond monocrystals. The 1.4 GeV electron beam with a divergence of approximately 10-4 rad and intensity of 0.2-0.3 μA strikes monocrystalline diamond targets having a thickness of 0.3 and 0.08 mm. The targets are installed in a qoniometric device with an angle reading accuracy of 5x10-5 rad. A beam of linearly polarized photons with a collimation angle of approximately 10-4 rad shaped with the help of adjustable lead-baffled collimators strikes a liquid-hydrogen target located at the focal point of two magnetic spectrometers. The nuclear reaction products are analyzed in momentum and detected by scintillation counter telescopes. The total photon flux with an intensity from 108-1010 equiv. γ-quantum/s and corresponding polarization of 90-50% is measured by means of Wilson-type or secondary-emission quantometers

  13. Radioisotopes in Hydrology. Proceedings of a Symposium

    International Nuclear Information System (INIS)

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

  14. Some important applications of accelerators in medicine and industry

    International Nuclear Information System (INIS)

    Accelerators, and cyclotrons in particular, have long been dedicated to research. Nowadays, they are industrial devices heavily used in various fields. The Belgian company Ion Beam Applications, probably the largest private company manufacturing cyclotrons, has largely contributed to the dissemination of this technology into the medical and radio-pharmaceutical community. This paper will present different applications of cyclotrons in these fields, from radioisotope production to radiotherapy, based on IBA's experience since 1986, date of construction of the CYCLONE 30 prototype, a cyclotron that revolutionized cyclotron technology for medicine and industry. Possible industrial applications of cyclotrons will also be mentioned, together with applications of another type of accelerator recently introduced in the market by IBA: the Rhodotron. (author)

  15. CAS CERN Accelerator School: Cyclotrons, linacs and their applications. Proceedings

    International Nuclear Information System (INIS)

    These proceedings present the lectures given at the eighth specialized course organized by the CERN Accelerator School (CAS), the topic this time being 'Cyclotrons, Linacs and Their Applications'. Following an introductory lecture on linacs, the fundamental features of electron, ion and induction linacs are described together with their RF systems and particle sources. Cyclotrons are then introduced followed by details of their different types, their magnet and RF design, and their injection and extraction systems, with a glance towards exotic and possible future machines. Chapters are then presented on the use of linacs and cyclotrons for medical, fission, fusion and material applications, as well as for isotope production. Finally, descriptions of the design of a radioisotope facility, the matching of accelerators to their task and the computational tools used in their design are included. (orig.)

  16. 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.

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

    International Nuclear Information System (INIS)

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

  18. 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)

  19. On the production of flat electron bunches for laser wake field acceleration

    CERN Document Server

    Kando, M; Kotaki, H; Koga, J; Bulanov, S V; Tajima, T; Chao, A; Pitthan, R; Schüler, K P; Zhidkov, A G; Nemoto, K

    2006-01-01

    We suggest a novel method for injection of electrons into the acceleration phase of particle accelerators, producing low emittance beams appropriate even for the demanding high energy Linear Collider specifications. In this paper we work out the injection into the acceleration phase of the wake field in a plasma behind a high intensity laser pulse, taking advantage of the laser polarization and focusing. With the aid of catastrophe theory we categorize the injection dynamics. The scheme uses the structurally stable regime of transverse wake wave breaking, when electron trajectory self-intersection leads to the formation of a flat electron bunch. As shown in three-dimensional particle-in-cell simulations of the interaction of a laser pulse in a line-focus with an underdense plasma, the electrons, injected via the transverse wake wave breaking and accelerated by the wake wave, perform betatron oscillations with different amplitudes and frequencies along the two transverse coordinates. The polarization and focus...

  20. Utilization of radioisotopes in the agriculture

    International Nuclear Information System (INIS)

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

  1. Radioisotopes in the service of mankind: the work of Amersham International plc

    International Nuclear Information System (INIS)

    The paper concerns Amersham International plc - a high technology company providing specialised radioactive products for use in health care, life sciences research, and industry. A brief description is given of the development of the company, and the rise in the use of radioisotopes in our present day world. Details of Amersham's medical, industrial and research products are given, along with the marketing facilities of the products. (U.K.)

  2. Steps of radioisotope separation in Japan

    International Nuclear Information System (INIS)

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

  3. Quantitation of renal function using radioisotopic techniques.

    Science.gov (United States)

    O'Malley, J P; Ziessman, H A

    1993-03-01

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

  4. Medical Radioisotope Scanning. Proceedings of a Seminar

    International Nuclear Information System (INIS)

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

  5. NEW DIRECTIONS IN RADIOISOTOPE SPECTRUM IDENTIFICATION

    Energy Technology Data Exchange (ETDEWEB)

    Salaymeh, S.; Jeffcoat, R.

    2010-06-17

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

  6. Recent research activities and future subjects on stable- and radio-isotopes of chlorine in environment

    Energy Technology Data Exchange (ETDEWEB)

    Kushita, Kouhei [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-12-01

    This report reviews the recent studies on the stable- and radio-isotopes of chlorine from a viewpoint of environmental science, partly including historic references on this element. First, general properties, occurrence, and utilization of chlorine are described. Secondly, current status and research works on chlorine-compounds, which attract special attention in recent years as environmentally hazardous materials, are reported. Thirdly, research works on stable chlorine isotopes, {sup 35}Cl and {sup 37}Cl, are described with a focus laid on the newly-developed techniques; isotopic ratio mass spectrometry (IRMS) and thermal ionization mass spectrometry (TIMS). Fourthly, recent research works on chlorine radioisotopes, {sup 36}Cl etc., are described, focusing on the development of accelerator mass spectrometry (AMS) and its application to geochemistry and others. Finally, taking account of the above-mentioned recent works on Cl isotopes, possible future research subjects are discussed. (author)

  7. Recent research activities and future subjects on stable- and radio-isotopes of chlorine in environment

    International Nuclear Information System (INIS)

    This report reviews the recent studies on the stable- and radio-isotopes of chlorine from a viewpoint of environmental science, partly including historic references on this element. First, general properties, occurrence, and utilization of chlorine are described. Secondly, current status and research works on chlorine-compounds, which attract special attention in recent years as environmentally hazardous materials, are reported. Thirdly, research works on stable chlorine isotopes, 35Cl and 37Cl, are described with a focus laid on the newly-developed techniques; isotopic ratio mass spectrometry (IRMS) and thermal ionization mass spectrometry (TIMS). Fourthly, recent research works on chlorine radioisotopes, 36Cl etc., are described, focusing on the development of accelerator mass spectrometry (AMS) and its application to geochemistry and others. Finally, taking account of the above-mentioned recent works on Cl isotopes, possible future research subjects are discussed. (author)

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

    International Nuclear Information System (INIS)

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

  9. 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.

  10. Radioisotopes and radiation processing in industry

    International Nuclear Information System (INIS)

    Types of radiation technology and labelled atom application which are not widely known but are widely used in industry are considered. Attention is paid to 60Co radiation sources and electron accelerators used in commercial plants for irradiation. Industrial sterilization of single application medical products and pharmaceuticals, spices and other products, food-stuff irradiation, sewage disinfection, polymerization, fabrication of wood-plastic composites, vulcanization etc. are indicated as radiation technolgy application spheres. Attention is paid to radiation technology in the developing countries. Tracer techniques are applied practically in all industrial fields, in paricular, in chemical technology, metallurgy, mineral exploration, environmental protection and sanitation. The IAEA activity in the field of tracer technique and radiation technology application is stressed

  11. Radioisotope techniques for process optimization

    International Nuclear Information System (INIS)

    In obtaining the necessary information for process optimization radiotracer and radiometric gaging methods are often applied. They can be classified into 2 groups: stimulus and response methods used in equipments operating continuously or periodically, and monitoring and evaluation of the time or spatial changes of concentrations. In certain cases it is more economical to run the optimization procedure on a pilot plant than in a full-scale plant. Criterion equations developed according to the rules of the similarity theory are used in the extrapolation of results to the full-scale equipment. Six examples are presented, three of them for laboratory equipment and pilot plants (mixing of mutually miscible liquids, mixing of suspension, and packed columns) and the other three for industrial plants (the reactor of urea production, glass melting tank, and fodder plants). (author)

  12. On the Production of Flat Electron Bunches for Laser Wake Field Acceleration

    Energy Technology Data Exchange (ETDEWEB)

    Kando, M.; Fukuda, Y.; Kotaki, H.; Koga, J.; Bulanov, S.V.; Tajima, T.; /JAERI, Kyoto; Chao, A.; Pitthan, R.; /SLAC; Schuler, K.-P.; /DESY; Zhidkov, A.G.; /CRIEPI, Tokyo; Nemoto, K.; /CRIEPI, Tokyo

    2006-06-27

    We suggest a novel method for injection of electrons into the acceleration phase of particle accelerators, producing low emittance beams appropriate even for the demanding high energy Linear Collider specifications. In this paper we work out the injection into the acceleration phase of the wake field in a plasma behind a high intensity laser pulse, taking advantage of the laser polarization and focusing. With the aid of catastrophe theory we categorize the injection dynamics. The scheme uses the structurally stable regime of transverse wake wave breaking, when electron trajectory self-intersection leads to the formation of a flat electron bunch. As shown in three-dimensional particle-in-cell simulations of the interaction of a laser pulse in a line-focus with an underdense plasma, the electrons, injected via the transverse wake wave breaking and accelerated by the wake wave, perform betatron oscillations with different amplitudes and frequencies along the two transverse coordinates. The polarization and focusing geometry lead to a way to produce relativistic electron bunches with asymmetric emittance (flat beam). An approach for generating flat laser accelerated ion beams is briefly discussed.

  13. Design and realization of a high productivity cluster-based network application reconfigurable accelerator board

    Institute of Scientific and Technical Information of China (English)

    Zeng Yu; Li Jun; Sun Ninghui; Wang Jie; Liu Zhaohui

    2008-01-01

    Improving processor frequency to strengthen massive data processing capability will lead to incremental server marginal costs and bring about a series of problems such as power consumption, management complexity, etc. Based on the field programmable gate array (FPGA), TCP offload engine (TOE), zero-copy and other key technologies, this paper describes the design and realization of a reconfigurable accelerator board. In this board, TCP/IP protocol will be moved to high-speed reconfigurable accelerator board. The packets will be labeled according to the protocol and submitted to the upper data processing software after IP-quintuple filtering in hardware. Reconfigurable accelerator board obtains higher performance speed-up compared with ordinary NIC card.

  14. The PSI/ETH tandem accelerator facility

    Energy Technology Data Exchange (ETDEWEB)

    Synal, H.A.; Doebeli, M.; Fuhrmann, H.; Kubik, P.W.; Nebiker, P.W. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)] [and others

    1997-09-01

    The 1996 operation of the PSI/ETH tandem accelerator at ETH Hoenggerberg is summarised with a detailed compilation of the beam time statistics and the statistics of AMS samples for the different radioisotopes and for the major fields of research. (author) 2 tab.

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

    International Nuclear Information System (INIS)

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

  16. Radioisotope techniques for problem-solving on refineries

    International Nuclear Information System (INIS)

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

  17. Vitrified chemically bonded phosphate ceramics for immobilization of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Wagh, Arun S.

    2016-04-05

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

  18. Advanced Radiative Emitters for Radioisotope Thermophotovoltaic Power Systems Project

    Data.gov (United States)

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

  19. Efficient, Long-Lived Radioisotope Power Generator Project

    Data.gov (United States)

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

  20. The Tasse concept (thorium based accelerator driven system with simplified fuel cycle for long term energy production)

    Energy Technology Data Exchange (ETDEWEB)

    Berthou, V. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Slessarev, I.; Salvatores, M. [IRI, TU Delft (Netherlands)

    2001-07-01

    Within the framework of the nuclear waste management studies, the ''one-component''. concept has to be considered as an attractive option in the long-term perspective. This paper proposes a new system called TASSE (''Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy production''.), destined to the current French park renewal. The main idea of the TASSE concept is to simplify both the front and the back end of the fuel cycle, and his major goals are to provide electricity with low waste production, and with an economical competitiveness. (author)

  1. The Tasse concept (thorium based accelerator driven system with simplified fuel cycle for long term energy production)

    International Nuclear Information System (INIS)

    Within the framework of the nuclear waste management studies, the ''one-component''. concept has to be considered as an attractive option in the long-term perspective. This paper proposes a new system called TASSE (''Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy production''.), destined to the current French park renewal. The main idea of the TASSE concept is to simplify both the front and the back end of the fuel cycle, and his major goals are to provide electricity with low waste production, and with an economical competitiveness. (author)

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

    International Nuclear Information System (INIS)

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

  3. Acceleration and propagation of cosmic radiation. Production, oscillation and detection of neutrinos

    International Nuclear Information System (INIS)

    In recent years, the old problem of cosmic-ray acceleration and propagation has become alive again, with the discovery of the diffusive shock acceleration mechanism, and with the first measurements of the cosmic-ray antiproton flux, which appears to be higher than expected. I have shown that the new acceleration mechanism was slow and I have calculated the maximum energy that can be reached by particles accelerated in various astrophysical sites. I have also studied in detail a cosmic-ray propagation model which takes into account the antiproton measurements. Neutrino astronomy is a field much more recent and in rapid expansion, thanks to a convergence of interests between astrophysicists and elementary particle physicists. Several large neutrino detectors already exist; really huge ones are in project. I have studied the possible impact of the high energy (> 1 TeV) neutrino astronomy on models of cosmic-ray sources such as Cygnus X3. Comparing the low energy (∼ 10 MeV) cosmic-ray antineutrinos with other sources of neutrinos and antineutrinos (sun, supernova, earth...), I have pointed out that the antineutrino background resulting from all the nuclear power-stations of the planet was sizeable. This background is a nuisance for some astrophysical applications but could be useful for studies on vacuum or matter neutrino oscillations (MSW effect). I have also examined the MSW effect in another context: the travel through the earth of neutrinos from the supernova explosion SN1987a

  4. Miniaturized radioisotope solid state power sources

    Science.gov (United States)

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

    2000-01-01

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

  5. Performance tuned radioisotope thermophotovoltaic space power system

    Science.gov (United States)

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

    1998-01-01

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

  6. 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)

  7. The Case of the Missing Productivity Growth: Or, Does Information technology explain why productivity accelerated in the United States but not the United Kingdom?

    OpenAIRE

    Susanto Basu; Fernald, John G.; Nicholas Oulton; Sylaja Srinivasan

    2003-01-01

    Solow's paradox has disappeared in the United States but remains alive and well in the United Kingdom. In particular, the U.K. experienced an information and communications technology (ICT) investment boom in the 1990s in parallel with the U.S., but measured total factor productivity has decelerated rather than accelerated in recent years. We ask whether ICT can explain the divergent TFP performance in the two countries. Stories of ICT as a 'general purpose technology' suggest that measured T...

  8. Study on the production of medical RIs like 99Mo based on accelerator neutrons generated by C(d,n))

    International Nuclear Information System (INIS)

    This paper introduces the development state of the manufacturing method for 99mTc that satisfies the conditions for radioactive preparations. In this process, using the high-speed neutrons obtained in C(d,n) reaction due to the deuterons of approximately 40 MeV from an accelerator, 99Mo is obtained based on 100Mo(n,2n) reaction. The authors considered cyclotron as a prototype accelerator, and used a thermal separation process to separate/purify and produce the quality 99mTc from the generated 99Mo with low specific radioactivity. This paper also introduces the attractiveness of fast neutrons as 'new neutron source to supplement reactor neutrons,' by referring to the case of the production of 67Cu expected as therapeutic isotope, based on 68Zn(n,x)67Cu reaction. (A.O.)

  9. Accelerated oral nanomedicine discovery from miniaturized screening to clinical production exemplified by paediatric HIV nanotherapies

    Science.gov (United States)

    Giardiello, Marco; Liptrott, Neill J.; McDonald, Tom O.; Moss, Darren; Siccardi, Marco; Martin, Phil; Smith, Darren; Gurjar, Rohan; Rannard, Steve P.; Owen, Andrew

    2016-01-01

    Considerable scope exists to vary the physical and chemical properties of nanoparticles, with subsequent impact on biological interactions; however, no accelerated process to access large nanoparticle material space is currently available, hampering the development of new nanomedicines. In particular, no clinically available nanotherapies exist for HIV populations and conventional paediatric HIV medicines are poorly available; one current paediatric formulation utilizes high ethanol concentrations to solubilize lopinavir, a poorly soluble antiretroviral. Here we apply accelerated nanomedicine discovery to generate a potential aqueous paediatric HIV nanotherapy, with clinical translation and regulatory approval for human evaluation. Our rapid small-scale screening approach yields large libraries of solid drug nanoparticles (160 individual components) targeting oral dose. Screening uses 1 mg of drug compound per library member and iterative pharmacological and chemical evaluation establishes potential candidates for progression through to clinical manufacture. The wide applicability of our strategy has implications for multiple therapy development programmes. PMID:27767027

  10. THE EFFECTS OF HEIGHT AND DISTANCE ON THE FORCE PRODUCTION AND ACCELERATION IN MARTIAL ARTS STRIKES

    Directory of Open Access Journals (Sweden)

    Cynthia A. Bir

    2009-11-01

    Full Text Available Almost all cultures have roots in some sort of self defence system and yet there is relatively little research in this area, outside of a sports related environment. This project investigated different applications of strikes from Kung Fu practitioners that have not been addressed before in the literature. Punch and palm strikes were directly compared from different heights and distances, with the use of a load cell, accelerometers, and high speed video. The data indicated that the arm accelerations of both strikes were similar, although the force and resulting acceleration of the target were significantly greater for the palm strikes. Additionally, the relative height at which the strike was delivered was also investigated. The overall conclusion is that the palm strike is a more effective strike for transferring force to an object. It can also be concluded that an attack to the chest would be ideal for maximizing impact force and moving an opponent off balance

  11. Acceleration and propagation of cosmic rays. Production, oscillation and detection of neutrinos

    International Nuclear Information System (INIS)

    This thesis is devoted to studies on cosmic rays and neutrinos, particles astrophysically relevant. In recent years, the old problem of cosmic-ray acceleration and propagation has become alive again, with the discovery of the diffusive shock acceleration mechanism, and with the first measurements of the cosmic-ray antiproton flux, which appears to be higher than expected. I have shown that the new acceleration mechanism was slow and I have calculated the maximum energy that can be reached by particles accelerated in various astrophysical sites. I have also studied in detail a cosmic-ray propagation model which takes into account the antiproton measurements. Neutrino astronomy is a field much more recent and in rapid expansion, thanks to a convergence of interests between astrophysicists and elementary particle physicists. Several large neutrino detectors already exist; really huge ones are in project. I have studied the possible impact of the high energy (> 1 TeV) neutrino astronomy on models of cosmic-ray sources such as Cygnus X3. Comparing the low energy (∼ 10 MeV) cosmic-ray antineutrinos with other sources of neutrinos and antineutrinos (sun, supernova, earth ...), I have pointed out that the antineutrino background resulting from all the nuclear power-stations of the planet was sizeable. This background is a nuisance for some astrophysical applications but could be useful for studies on vacuum or matter neutrino oscillations (MSW effect). I have also examined the MSW effect in another context: the travel through the earth of neutrinos from the supernova explosion SN1987a

  12. Scientific and engineering services for the LANCE/ER accelerator production of tritium (APT) project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-05

    The APT project office is conducting a preconceptual design study for an accelerator driven concept to produce tritium. The facility will require new technology in many areas, since the scale of this accelerator is significantly larger then any in operation to date. The facility is composed of four subsystems: accelerator, target & blanket, balance of plant, and tritium purification system (TPS). New physics realms will be entered in order for the concept to be feasible; for example, extremely high energy levels of the entering protons that induce (multiplicative) spallation of the neutrons from the high Z target will occur. These are complex and require advance codes (MCNP) to predict the physics interactions and as well as deleterious material effects in the surrounding structures. Other issues include component cooling and complex thermal-hydraulics effects within the blanket and the beam {open_quotes}window.{close_quotes} In order to support a DOE mandated fast ROD schedule, Los Alamos APT staff will be provided with senior, engineering technical support staff with direct APT technology experience and whom are {open_quotes}on site{close_quotes}. This report contains resumes of the staff.

  13. Study of photon emission by electron capture during solar nuclei acceleration. 3: Photon production evaluations

    Science.gov (United States)

    Perez-Peraza, J.; Alvarez, M.; Gallegos, A.

    1985-01-01

    Lower limits of photon fluxes were evaluated from electron capture during acceleration in solar flares, because the arbitrary q sub c asterisk assumed in this work evolves very slow with velocity, probably much more slowly than the physical actual situation: in fact, more emission is expected toward the IR region. Nevertheless the authors claim to show that the factibility of sounding acceleration processes, charge evolution processes and physical parameters of the source itself, by the observational analysis of this kind of emissions. For instance, it would be interesting to search observationally, for the predicted flux and energy drift of F sub e ions interacting with the atomic 0 and F sub e of the source matter, or, even more feasible for the X-ray lines at 4.2 keV and 2.624 + 0.003 KeV from Fe and S ions in ionized Fe at T = 10 to the 7th power K respectively, the 418 + or - 2 eV and 20 + or - 4 eV lines of Fe and S in ionized Fe at 5 x 10 to the 6th power K, which are predicted from Fermi acceleration.

  14. Scientific and engineering services for the LANCE/ER accelerator production of tritium (APT) project

    International Nuclear Information System (INIS)

    The APT project office is conducting a preconceptual design study for an accelerator driven concept to produce tritium. The facility will require new technology in many areas, since the scale of this accelerator is significantly larger then any in operation to date. The facility is composed of four subsystems: accelerator, target ampersand blanket, balance of plant, and tritium purification system (TPS). New physics realms will be entered in order for the concept to be feasible; for example, extremely high energy levels of the entering protons that induce (multiplicative) spallation of the neutrons from the high Z target will occur. These are complex and require advance codes (MCNP) to predict the physics interactions and as well as deleterious material effects in the surrounding structures. Other issues include component cooling and complex thermal-hydraulics effects within the blanket and the beam open-quotes window.close quotes In order to support a DOE mandated fast ROD schedule, Los Alamos APT staff will be provided with senior, engineering technical support staff with direct APT technology experience and whom are open-quotes on siteclose quotes. This report contains resumes of the staff

  15. Radioisotopes in the training of medical students

    International Nuclear Information System (INIS)

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

  16. Rhenium Radioisotopes for Therapeutic Radiopharmaceutical Development

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-01-18

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

  17. Safe Handling of Radioisotopes. Medical Addendum

    International Nuclear Information System (INIS)

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

  18. Induced radioisotopes in a linac treatment hall

    International Nuclear Information System (INIS)

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

  19. Guide to the safe handling of radioisotopes in hydrology

    International Nuclear Information System (INIS)

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

  20. The application of the Accelerated Stability Assessment Program (ASAP) to quality by design (QbD) for drug product stability.

    Science.gov (United States)

    Waterman, Kenneth Craig

    2011-09-01

    An isoconversion paradigm, where times in different temperature and humidity-controlled stability chambers are set to provide a fixed degradant level, is shown to compensate for the complex, non-single order kinetics of solid drug products. A humidity-corrected Arrhenius equation provides reliable estimates for temperature and relative humidity effects on degradation rates. A statistical protocol is employed to determine best fits for chemical stability data, which in turn allows for accurate estimations of shelf life (with appropriate confidence intervals) at any storage condition including inside packaging (based on the moisture vapor transmission rate of the packaging and moisture sorption isotherms of the internal components). These methodologies provide both faster results and far better predictions of chemical stability limited shelf life (expiry) than previously possible. Precise shelf-life estimations are generally determined using a 2-week, product-specific protocol. Once the model for a product is developed, it can play a critical role in providing the product understanding necessary for a quality by design (QbD) filing for product approval and enable rational control strategies to assure product stability. Moreover, this Accelerated Stability Assessment Program (ASAP) enables the coupling of product attributes (e.g., moisture content, packaging options) to allow for flexibility in how control strategies are implemented to provide a balance of cost, speed, and other factors while maintaining adequate stability. PMID:21748541

  1. 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)

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

    International Nuclear Information System (INIS)

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

  3. Shaping of intensive secondary pulsed molecular beam and production of accelerated molecules and radicals in it

    CERN Document Server

    Makarov, G N

    2001-01-01

    The method is described for shaping the intensive secondary pulsed molecular beam, wherein the molecules kinetic energy may be controlled through the powerful IR laser radiation by means of the molecules oscillatory excitation in the source itself. The thickening jump (the shock wave), which is formed by interaction of the intensive pulsed supersonic molecular beam (or flux) with a solid surface, is used as the secondary beam source. The intensive (>= 10 sup 2 sup 0 molecules/stere. s) beams of the SF sub 6 and CF sub 3 I molecules with the kinetic energy correspondingly equal to approximately 1.5 eV and 1.2 eV without gas-carrier and molecular SF sub 6 beams with kinetic energy approx = 2.5 eV are obtained. The spectral and energy characteristics of the SF sub 6 molecules acceleration in the secondary beam are studied. The possibility of obtaining the accelerated radicals in the secondary molecular beam is indicated

  4. Gadolinium-148 And Other Spallation Production Cross Section Measurements For Accelerator Target Facilities

    CERN Document Server

    Kelley, K C

    2004-01-01

    At the Los Alamos Neutron Science Center accelerator complex, protons are accelerated to 800 MeV and directed to two tungsten targets, Target 4 at the Weapons Neutron Research facility and the 1L target at the Lujan Center. The Department of Energy requires hazard classification analyses to be performed on these targets and places limits on certain radionuclide inventories in the targets to avoid characterizing the facilities as “nuclear facilities.” Gadolinium-148 is a radionuclide created from the spallation of tungsten. Allowed isotopic inventories are particularly low for this isotope because it is an alpha-particle emitter with a 75-year half-life. The activity level of Gadolinium-148 is low, but it encompasses almost two-thirds of the total dose burden for the two tungsten targets based on present yield estimates. From a hazard classification standpoint, this severely limits the lifetime of these tungsten targets. The cross section is not well-established experimentally and this is t...

  5. Emerging applications of radioisotopes in nuclear medicine

    International Nuclear Information System (INIS)

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

  6. 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.

  7. Alpha indirect conversion radioisotope power source

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-02-15

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

  8. Radioisotope Power System Facility shielding analysis

    International Nuclear Information System (INIS)

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

  9. Status of the NASA Stirling Radioisotope Project

    Science.gov (United States)

    Schreiber, Jeffrey G.

    2007-01-01

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

  10. Training in radioisotope uses for agricultural investigations

    International Nuclear Information System (INIS)

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

  11. Environmental Remediation and Conversion of Carbon Dioxide (CO2 into Useful Green Products by Accelerated Carbonation Technology

    Directory of Open Access Journals (Sweden)

    Kwang-Suk You

    2010-01-01

    Full Text Available This paper reviews the application of carbonation technology to the environmental industry as a way of reducing carbon dioxide (CO2, a green house gas, including the presentation of related projects of our research group. An alternative technology to very slow natural carbonation is the co-called ‘accelerated carbonation’, which completes its fast reaction within few hours by using pure CO2. Carbonation technology is widely applied to solidify or stabilize solid combustion residues from municipal solid wastes, paper mill wastes, etc. and contaminated soils, and to manufacture precipitated calcium carbonate (PCC. Carbonated products can be utilized as aggregates in the concrete industry and as alkaline fillers in the paper (or recycled paper making industry. The quantity of captured CO2 in carbonated products can be evaluated by measuring mass loss of heated samples by thermo-gravimetric (TG analysis. The industrial carbonation technology could contribute to both reduction of CO2 emissions and environmental remediation.

  12. Adaptation of the autotrophic acetogen Sporomusa ovata to methanol accelerates the conversion of CO2 to organic products

    DEFF Research Database (Denmark)

    Tremblay, Pier-Luc; Höglund, Daniel; Koza, Anna;

    2015-01-01

    to grow quicker autotrophically with methanol, a toxic C1 compound, as the sole substrate. Better growth on different concentrations of methanol and with H2-CO2 indicated the adapted strain had a more efficient autotrophic metabolism and a higher tolerance to solvent. The growth rate on methanol......Acetogens are efficient microbial catalysts for bioprocesses converting C1 compounds into organic products. Here, an adaptive laboratory evolution approach was implemented to adapt Sporomusa ovata for faster autotrophic metabolism and CO2 conversion to organic chemicals. S. ovata was first adapted...... was increased 5-fold. Furthermore, acetate production rate from CO2 with an electrode serving as the electron donor was increased 6.5-fold confirming that the acceleration of the autotrophic metabolism of the adapted strain is independent of the electron donor provided. Whole-genome sequencing, transcriptomic...

  13. Environmental remediation and conversion of carbon dioxide (CO(2)) into useful green products by accelerated carbonation technology.

    Science.gov (United States)

    Lim, Mihee; Han, Gi-Chun; Ahn, Ji-Whan; You, Kwang-Suk

    2010-01-01

    This paper reviews the application of carbonation technology to the environmental industry as a way of reducing carbon dioxide (CO(2)), a green house gas, including the presentation of related projects of our research group. An alternative technology to very slow natural carbonation is the co-called 'accelerated carbonation', which completes its fast reaction within few hours by using pure CO(2). Carbonation technology is widely applied to solidify or stabilize solid combustion residues from municipal solid wastes, paper mill wastes, etc. and contaminated soils, and to manufacture precipitated calcium carbonate (PCC). Carbonated products can be utilized as aggregates in the concrete industry and as alkaline fillers in the paper (or recycled paper) making industry. The quantity of captured CO(2) in carbonated products can be evaluated by measuring mass loss of heated samples by thermo-gravimetric (TG) analysis. The industrial carbonation technology could contribute to both reduction of CO(2) emissions and environmental remediation.

  14. The effects of height and distance on the force production and acceleration in martial arts strikes.

    Science.gov (United States)

    Bolander, Richard P; Neto, Osmar Pinto; Bir, Cynthia A

    2009-11-01

    Almost all cultures have roots in some sort of self defence system and yet there is relatively little research in this area, outside of a sports related environment. This project investigated different applications of strikes from Kung Fu practitioners that have not been addressed before in the literature. Punch and palm strikes were directly compared from different heights and distances, with the use of a load cell, accelerometers, and high speed video. The data indicated that the arm accelerations of both strikes were similar, although the force and resulting acceleration of the target were significantly greater for the palm strikes. Additionally, the relative height at which the strike was delivered was also investigated. The overall conclusion is that the palm strike is a more effective strike for transferring force to an object. It can also be concluded that an attack to the chest would be ideal for maximizing impact force and moving an opponent off balance. Key PointsIt has been determined that the palm strike is more effective than the punch for developing force and for transferring momentum, most likely the result of a reduced number of rigid links and joints.A strike at head level is less effective than a strike at chest level for developing force and transferring momentum.Distance plays an effect on the overall force and momentum changes, and most likely is dependent on the velocity of the limb and alignment of the bones prior to impact.The teaching of self defence for novices and law enforcement would benefit from including the palm strike as a high priority technique.

  15. Shifts and Twists in the Relative Productivity of Skilled Labor: Reconciling Accelerated SBTC with the Productivity Slowdown

    OpenAIRE

    Philip Marey; Arnaud Dupuy

    2004-01-01

    Skill-biased technical change is usually interpreted in terms of the efficiency parameters of skilled and unskilled labor. This implies that the relative productivity of skilled workers changes proportionally in all tasks. In contrast, we argue that technical changes also affect the curvature of the distribution of relative productivity. Building on Rosen's (1978) tasks assignment model, this implies that not only the efficiency parameters of skilled and unskilled workers change, but also the...

  16. Utilization of radioisotopes and irradiation in crop protection research

    International Nuclear Information System (INIS)

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

  17. Study of Compton scattering X-rays production on a linear electron accelerator

    International Nuclear Information System (INIS)

    Compton scattering by collisions between relativistic electron beam and laser beam is a way to produce X-rays. Laser beam is seen as an undulator which gives electrons a periodic waved motion. This radiation emitted by electrons motion has some characteristics close to those of synchrotron radiation but can be produced by smaller machines. ELSA facility at CEA DAM DIF is a linear electron accelerator (17 MeV) running with a photo-injector and a laser (532 nm). Characteristics of electrons and laser beam are favourable to a Compton scattering X-rays experiment. Small interaction probability and small beam sizes (≤ 100 μm, 30 ps (LTMH)) require a careful optimization of spatial and temporal pulses covering. An aluminium bevel-edge allows visualizing beams with CCD and streak cameras. Imaging plates are used as ≤ 11 keV X-rays detectors. These detectors are very sensitive to low signal-to-noise ratio at low energy and give the beam profile. The imaging plates were coupled with a photomultiplier to manage the yield in real time. Experimental results are confirmed by simulations. (author)

  18. Feasibility Study on the Development of Proton Accelerator II

    Energy Technology Data Exchange (ETDEWEB)

    Whang, Ki Woong [Korea Accelerator and Plasma Research Association, Seoul (Korea, Republic of)

    1997-09-01

    Present status and research trend of KOMAC (Korea Multipurpose Accelerator Complex)-grade accelerator construction in Europe, Japan, America, and Russia are surveyed in view of basic nuclear technology study in 2nd feasibility study on the KOMAC. KOMAC can be applied to study the increasing of nuclear reactor safety, the Proto-plant of transmutation technology for low cost nuclear fuel, the nuclear data production, the life science, mechanical dynamics, the structure probe, the radioisotope production, the cancer therapy, and the defense industry etc. And also KOMAC structure selection is investigated in point of utilization aims referred from various proposal of LANL and ORNL in USA, Neutron Science Research program in Japan, Energy Amplifier in Europe, and Institute of Theoretical and Experimental physics in Russia. As a result of meeting, study team is approached to the conclusion the KOMAC should be constructed to get the nuclear transmutation technology and the world leadership in future nuclear industry. Member`s opinion of study team agreed new nuclear technology, such as Accelerator Driven Energy Amplifier will be possible to sustain a survival of human being in post 21c. 7 tabs., 10 figs. (author)

  19. The IMPELA TM 10 MeV, 50 kW electron linac: launching an industrial accelerator product

    Science.gov (United States)

    Stirling, Andrew J.

    1991-05-01

    In the previous conferences there has been no shortage of ideas, experiments and prototypes for industrial accelerators. Indeed, physicists propose new ideas at a rate faster than industry can get irradiators to the market. Certainly, the basic physics design must be sound, but this is a far from sufficient condition for an accelerator to succeed. Good physics design is needed to provide a good combination of electrical efficiency and useable power within the scan width. It may, however, be counterproductive if high performance compromises inherent reliability. From the engineering discipline is required an engineered control interface, an engineered product control and dosimetry system and traceable quality assurance. Just as important, the industrial client seeks an irradiator that is built quickly, and will be supported over a long service life (10-20 years). It is also necessary to assist the client in facility design, licencing and process verification. Providing these additional functions is a challenge for the business champions which equals what the technical champions face in obtaining full beam power.

  20. Design of a 7Li rotating target for neutron production using a Van de Graaff accelerator

    International Nuclear Information System (INIS)

    We present a rotating target used for the production of monokinetic neutron fluxes. The neutrons are produced from the 7Li(p,n)7Be reaction for fast neutron elastic and inelastic scattering experiments. This target has been operated with a proton beam current of 8 to 10 μA during six consecutive weeks and has given entire satisfaction

  1. Prospects for utilization of Electron Beam Accelerators (EBAs) for processing of food products

    International Nuclear Information System (INIS)

    Radiation processing using gamma radiation and high energy electron beams has been in practice for more than three decades in the industry. Since gamma radiation has the ability of higher penetration in the material, large scale irradiators (mainly based on mega curies of 60Co radioactive source) are successfully employed for treating bulk products in sterilization and food preservation applications. Electron beam, due to its low penetration, has been exploited exclusively for applications involving polymer modifications to irradiate thin finished end products like electrical cable insulations, heat shrinkable sheets, tubes, automobile tyres etc using high power EBAs (energies 0.5 MeV-4 MeV and powers around ∼100 kW). Out of around 2500 industrial EB units currently employed worldwide (with total installed power above 150 MWL 90% are in the low to medium energy range (0.5 MeV to 4 MeV) being used for polymer modifications. However, recent technological advances in the manufacturing sector of industrial high energy EBAs and product handling systems resulted in widening utilization of EB technology for applications involving bulk product irradiation

  2. Variable Conductance Heat Pipes for Radioisotope Stirling Systems Project

    Data.gov (United States)

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

  3. Short course on the use of radioisotopes in agriculture

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

    Lappin, Graham

    2015-01-01

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

  5. Safety Analysis for a Radioisotope Stirling Generator

    International Nuclear Information System (INIS)

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

  6. Study of the acceleration of ammonia generation process from poultry residues aiming at hydrogen production

    International Nuclear Information System (INIS)

    The hydrogen, utilized in fuel cells, can be produced from a variety of intermediate chemicals, between them, the ammonia. The ammonia gas as a raw material for the hydrogen production has been used due to its high energetic content, facility of decomposition, high availability, low prices, low storage pressure and its by-products are environmentally correct. One of the sources of ammonia is poultry and egg production systems. In these systems the ammonia is produced from the decomposition of uric acid present in the excreta of birds. The residue from the poultry-rearing farms is the broiler litter and from the egg production system is the excreta without any substrate. The characterization of these residues was performed using the Wavelength-Dispersive X-Ray Fluorescence (WDXRF), Elementary Analysis (CHN), Thermogravimetry and GC/MS - Gas chromatography/ Mass spectrometry. The studied factors which influence the ammonia volatilization were: nitrogen content, raising period, urease enzyme, temperature, pH and moisture content. The experiment results with poultry litter and excreta allow to conclude that the manipulation of the following parameters increased the ammonia emission: pH, nitrogen content, raising period, age of birds and excreta accumulation, urease enzyme and the temperature. The addition of different amounts of sand in the excreta and different volumes of water in the poultry litter inhibited the emission of ammonia. The variation of the quantity of material (broiler litter or excreta) and the volume of the flask used as incubator chamber showed no significant alterations to be chosen as a variable. The excreta was considered more appropriate than poultry litter for the objectives of this work due to the higher ammonia concentrations determined in this material. Due to the large amount of poultry litter and excreta from the production processes, the reuse of poultry residues to obtain ammonia is necessary to improve the quality of the local

  7. Efficiency of Pm-147 direct charge radioisotope battery

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-05-15

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

  8. 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. PMID:17575955

  9. Accelerator breeder nuclear fuel production: concept evaluation of a modified design for ORNL's proposed TME-ENFP

    International Nuclear Information System (INIS)

    Recent advances in accelerator beam technology have made it possible to improve the target/blanket design of the Ternary Metal Fueled Electronuclear Fuel Producer (TMF-ENFP), an accelerator-breeder design concept proposed by Burnss et al. for subcritical breeding of the fissile isotope 233U. In the original TMF-ENFP the 300-mA, 1100-MeV proton beam was limited to a small diameter whose power density was so high that a solid metal target could not be used for producing the spallation neutrons needed to drive the breeding process. Instead the target was a central column of circulating liquid sodium, which was surrounded by an inner multiplying region of ternary fuel rods (239Pu, 232Th, and 238U) and an outer blanket region of 232Th rods, with the entire system cooled by circulating sodium. In the modified design proposed here, the proton beam is sufficiently spread out to allow the ternary fuel to reside directly in the beam and to be preceded by a thin (nonstructural) V-Ti steel firThe spread beam mandated a change in the design configuration (from a cylindrical shape to an Erlenmeyer flask shape), which, in turn, required that the fuel rods (and blanket rods) be replaced by fuel pebbles. The fuel residence time in both systems was assumed to be 90 full power days. A series of parameter optimization calculations for the modified TMF-ENFP led to a semioptimized system in which the initial 239Pu inventory of the ternary fuel was 6% and the fuel pebble diameter was 0.5 cm. With this system the 233Pu production rate of 5.8 kg/day reported for the original TMF-ENFP was increased to 9.3 kg/day, and the thermal power production at beginning of cycle was increased from 3300 MW(t) to 5240 MW(t). 31 refs., 32 figs., 6 tabs

  10. Determination of Shelf Life for Butter and Cheese Products in Actual and Accelerated Conditions.

    Science.gov (United States)

    Park, Jung-Min; Shin, Jin-Ho; Bak, Da-Jeong; Kim, Na-Kyeong; Lim, Kwang-Sei; Yang, Cheul-Young; Kim, Jin-Man

    2014-01-01

    The aim of this study was to estimate the shelf life of butter and cheese products, with shelf life being a guide used to determine the storage period of food before deterioration. Butter and cheese samples stored at 10℃ and 15℃ had a shelf life of 221 d, while those stored at 25℃ and 35℃ had a shelf life of 109 d. Quality changes, including total cell count, coliform counts, Listeria monocytogenes counts, acid value, moisture content, pH, acidity and overall sensory evaluation, were monitored. In order to pass the overall sensory evaluation, a quality score of 5 points on a 9-point scale was required. For other quality criteria, legal quality limits were established based on the "Process Criteria and Ingredient Standard of Livestock Products" by the Animal, Plant and Fisheries Quarantine and Inspection Agency (Republic of Korea). The nonlegal quality limit was estimated by regression analysis between non-quality criteria (y) and overall sensory evaluation (x). The shelf life was estimated based on the number of days that the product passed the quality limit of the quality criteria. The shelf life of samples stored at 10℃, 15℃, 25℃ and 35℃ was 21.94, 17.18, 6.10 and 0.58 mon, respectively, for butter and 10.81, 9.47, 4.64 and 0.20 mon, respectively, for cheese.

  11. Strategy for securing the national supply of radioisotopes

    International Nuclear Information System (INIS)

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

  12. Prospect of radioisotopes and radiation utilization

    International Nuclear Information System (INIS)

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

  13. Treatment of animal wastes contaminated with radioisotopes

    International Nuclear Information System (INIS)

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

  14. Versatile PC-logger for radioisotope measurements

    International Nuclear Information System (INIS)

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

  15. Safe Handling of Radioisotopes. 1973 Edition

    International Nuclear Information System (INIS)

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

  16. Accelerating the Adoption of Second-Tier Reach Standards forApplicable Appliance Products in China

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Jiang; Fridley, David

    2007-03-01

    The minimum energy efficiency standards program for household appliances in China was initiated in 1989. Since 1996, CLASP and its implementing partner, LBNL, have assisted China in developing 11 minimum energy performance standards (MEPS) for 9 products and endorsement labels for 11 products including: refrigerators; air conditioners; clothes washers; televisions; printers; computers; monitors; fax machines; copiers; DVD/VCD players; external power supplies; and set-top boxes (under development). Before 2003, China's traditional approach to standards development involved small increases in efficiency requirements for implementation within 6 months of a standard's approval. Since 2003, China has adopted a new approach in setting MEPS. This new approach involves the development of two tiers of standards--one for initial implementation and a second tier at a more aggressive level of energy efficiency for implementation three to five years later. The second-tier standard is also referred to as a 'reach standard'. Reach standards have now been developed in China for: color TVs; refrigerators; air conditioners; and external power supplies. This report is presented in five sections. After the introduction in Section 1, Section 2 analyzes the distribution of the efficiency of refrigerators and air-conditioners in China based on data collected by the China Energy Label Center for the mandatory energy information label program. The results provide an assessment of the adoption of reach standards for these two products. Section 3 summarizes on-going collaborations with Shanghai related to early local adoption of reach standards, and presents both the impact and an analysis of barriers to the local adoption of reach standard for air-conditioners. Section 4 offers suggestions for local governments on how to move forward in adopting reach standards in their localities and concludes with a summary of the results and a plan for developing local capacity in

  17. Accelerator based Production of Auger-Electron-emitting Isotopes for Radionuclide Therapy

    DEFF Research Database (Denmark)

    Thisgaard, Helge

    In this research project the focus has been on the identification and production of new, unconventional Augerelectron- emitting isotopes for targeted radionuclide therapy of cancer. Based on 1st principles dosimetry calculations on the subcellular level, the Augeremitter 119Sb has been identified...... isotopes (e.g. 119Sb or 64Cu) using the PETtrace cyclotron commonly found at the larger PET-centers in the hospitals. Finally, research in a new method to measure the radiotoxicity of Auger-emitters invitro using cellular microinjection has been carried out. The purpose of this method is to be able...

  18. Determination of Shelf Life for Butter and Cheese Products in Actual and Accelerated Conditions

    OpenAIRE

    Park, Jung-Min; Shin, Jin-Ho; Bak, Da-Jeong; Kim, Na-Kyeong; Lim, Kwang-Sei; Yang, Cheul-Young; Kim, Jin-Man

    2014-01-01

    The aim of this study was to estimate the shelf life of butter and cheese products, with shelf life being a guide used to determine the storage period of food before deterioration. Butter and cheese samples stored at 10℃ and 15℃ had a shelf life of 221 d, while those stored at 25℃ and 35℃ had a shelf life of 109 d. Quality changes, including total cell count, coliform counts, Listeria monocytogenes counts, acid value, moisture content, pH, acidity and overall sensory evaluation, were monitore...

  19. Nanoscale-alumina induces oxidative stress and accelerates amyloid beta (Aβ) production in ICR female mice

    Science.gov (United States)

    Shah, Shahid Ali; Yoon, Gwang Ho; Ahmad, Ashfaq; Ullah, Faheem; Amin, Faiz Ul; Kim, Myeong Ok

    2015-09-01

    The adverse effects of nanoscale-alumina (Al2O3-NPs) have been previously demonstrated in both in vitro and in vivo studies, whereas little is known about their mechanism of neurotoxicity. It is the goal of this research to determine the toxic effects of nano-alumina on human neuroblastoma SH-SY5Y and mouse hippocampal HT22 cells in vitro and on ICR female mice in vivo. Nano-alumina displayed toxic effects on SH-SY5Y cell lines in three different concentrations also increased aluminium abundance and induced oxidative stress in HT22 cells. Nano-alumina peripherally administered to ICR female mice for three weeks increased brain aluminium and ROS production, disturbing brain energy homeostasis, and led to the impairment of hippocampus-dependent memory. Most importantly, these nano-particles induced Alzheimer disease (AD) neuropathology by enhancing the amyloidogenic pathway of Amyloid Beta (Aβ) production, aggregation and implied the progression of neurodegeneration in the cortex and hippocampus of these mice. In conclusion, these data demonstrate that nano-alumina is toxic to both cells and female mice and that prolonged exposure may heighten the chances of developing a neurodegenerative disease, such as AD.

  20. Nanoscale-alumina induces oxidative stress and accelerates amyloid beta (Aβ) production in ICR female mice.

    Science.gov (United States)

    Shah, Shahid Ali; Yoon, Gwang Ho; Ahmad, Ashfaq; Ullah, Faheem; Ul Amin, Faiz; Kim, Myeong Ok

    2015-10-01

    The adverse effects of nanoscale-alumina (Al2O3-NPs) have been previously demonstrated in both in vitro and in vivo studies, whereas little is known about their mechanism of neurotoxicity. It is the goal of this research to determine the toxic effects of nano-alumina on human neuroblastoma SH-SY5Y and mouse hippocampal HT22 cells in vitro and on ICR female mice in vivo. Nano-alumina displayed toxic effects on SH-SY5Y cell lines in three different concentrations also increased aluminium abundance and induced oxidative stress in HT22 cells. Nano-alumina peripherally administered to ICR female mice for three weeks increased brain aluminium and ROS production, disturbing brain energy homeostasis, and led to the impairment of hippocampus-dependent memory. Most importantly, these nano-particles induced Alzheimer disease (AD) neuropathology by enhancing the amyloidogenic pathway of Amyloid Beta (Aβ) production, aggregation and implied the progression of neurodegeneration in the cortex and hippocampus of these mice. In conclusion, these data demonstrate that nano-alumina is toxic to both cells and female mice and that prolonged exposure may heighten the chances of developing a neurodegenerative disease, such as AD.

  1. Highly charged ion production in ECRH plasma sources for heavy-ion accelerators and other applications

    International Nuclear Information System (INIS)

    The design and status of three ECRH ion sources under development at NSCL are briefly discussed. The RT-ECR ion source, with two minimum B plasma stages and ECRH heating at 6.4 GHz, produces useable intensities of fully stripped light ions up to oxygen; for heavier species, charges such as Argon 14+, Krypton 20+, Iodine 25+ and Tantalum 29+ have been measured. The 6.4 GHz CP-ECR, just beginning operation, has a high temperature metal vapor oven replacing the first plasma stage, and will be used for metal ion production. Initial results for Lithium ions are presented. The SC-ECR, now in the design stage, has a superconducting magnet structure to allow first harmonic ECRH heating at 30--35 GHz. With a higher cutoff density, it is hoped that A≅200 ions with Q>50+ will be realized

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

    International Nuclear Information System (INIS)

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

  3. 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

    CERN Document Server

    Tárkányi, F; Ditrói, F; Takács, S; Adam-Rebeles, R

    2016-01-01

    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 $^{197}$Au(d,xn)$^{197m,197g,195m,195g,193m,193g}$Hg and $^{197}$Au(d,x)$^{198m,198g,196m,196g,195,194}$Au nuclear reactions. The application for production of the medically relevant isotopes $^{198}$Au and $^{195m,195g,197m,197g}$Hg is discussed, including the comparison with other charged particle induced production routes. The possible use of the $^{197}$Au(d,x)$^{197m,197g,195m,193m}$Hg and $^{196m,196g}$Au reactions for monitoring deuteron beam parameters is also investigated.

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

    Science.gov (United States)

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

    1992-01-01

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

  5. 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.

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

    International Nuclear Information System (INIS)

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

  7. Efficiency of the sulfur–iodine thermochemical water splitting process for hydrogen production based on ADS (accelerator driven system)

    International Nuclear Information System (INIS)

    The current hydrogen production is based on fossil fuels; they have a huge contribution to the atmosphere's pollution. Thermochemical water splitting cycles don't present this issue because the required process heat is obtained from nuclear energy and therefore, the environmental impact is smaller than using conventional fuels. Although, solar hydrogen production could be also used for practical applications because it's lower environmental impact. One of the promising approaches to produce large quantities of hydrogen in an efficient way using nuclear energy is the sulfur–iodine (S–I) thermochemical water splitting cycle. The nuclear source proposed in this paper is a pebble bed gas cooled transmutation facility. Pebble bed very high temperature advanced systems have great perspectives to assume the future nuclear energy. Softwares based on CPS (chemical process simulation) can be used to simulate the thermochemical water splitting sulfur-iodine cycle for hydrogen production. In this paper, a model for analyzing the sulfur-iodine process sensibility respect to the thermodynamics parameters: temperature, pressure and mass flow is developed. Efficiency is also calculated and the influence of different parameters on this value. The behavior of the proposed model for different values of initial reactant's flow, is analyzed. - Highlights: • Chemical Process Simulation (CPS) of the complete sulfur iodine cycle. • Conceptual design of an accelerator driven system for hydrogen production. • Radial and axial temperature profile for the end of stationary cycle (EOC). • Thermal stability of the sulfuric and hydriodic acid sections determination. • Sulfur iodine cycle efficiency analyses for different heat flow from the ADS

  8. Efficient neutron production from sub-nanosecond laser pulse accelerating deuterons on target front side

    International Nuclear Information System (INIS)

    Neutron-producing experiments have been carried out on the Prague Asterix Laser System. At the fundamental wavelength of 1.315 μm, the laser pulse of a 600 J energy and 300 ps duration was focused on a thick deuterated-polyethylene target. Neutron yields reached (4.1 ± 0.8) × 108 at the peak intensity of ≈3 × 1016 W/cm2. A more detailed analysis of neutron time-of-flight signals showed that a significant fraction of neutron yields was produced both by the 2H(d,n)3He reaction and by other neutron-producing reactions. Neutron energies together with delayed neutron and gamma emission showed that MeV deuterons escaped from a laser-produced plasma and interacted ≈50 ns later with a borosilicate blast-shield glass. In order to increase DD neutron yields and to characterize deuteron beams via nuclear reactions, a secondary deuterated polyethylene target was used in a pitcher-catcher scheme at the target front side. In this experimental arrangement, the neutron yield reached (2.0 ± 0.5) × 109 with the peak neutron fluence of (2.5 ± 0.5) × 108 n/sr. From the neutron yield, it was calculated that the secondary target was bombarded by 2 × 1014 deuterons in the 0.5–2.0 MeV energy range. The neutron yield of 2 × 109 at the laser energy of 600 J implied the production efficiency of 3 × 106 n/J. A very important result is that the efficient neutron production was achieved with the low contrast, sub-nanosecond laser pulse of the intensity of 1016 W/cm2. The latter parameters can be achieved in a rep-rate mode more easily than ultra-high intensities and contrasts

  9. Renogram studies with dogs, using the radioisotope technetium-99m DTPA

    International Nuclear Information System (INIS)

    In the dog extensive kidney pathology is often not diagnosed by conventional tests. In this study renograms were conducted on conscious healthy Beagle dogs using the radioisotope technetium-99m DTPA. Because of problems foreseen in keeping dogs immobile the study was also conducted using the sedative acepromazine maleate and the narcotic thiopentonesodium on the same Beagles. Renograms were also conducted on dogs with acute and chronic renal pathology. It was found that during the renogram procedure the animal must be completely immobile. Constant infusion narcosis with thiopentonesodium produced this immobility without affecting the renogram in normal dogs, however administration of a thiopentone bolus did affect the renogram. Sedation with acepromazine maleate had the effect of significantly increasing the second phase of the renogram and in addition significantly accelerated the excretion phase. These effects are thought to be due to a decreased bloodpressure with concomintent renal bloodpooling and retarded renal bloodflow. It would appear that radioisotope renograms are valuable in the diagnosis and prognosis of clinical cases of acute as well as chronic renal pathology. It is especially useful in identifying cases of compensated renal pathology where it is more sensitive than the conventional tests. It can differentiate between different degrees of pathology between the left and right kidney. Seen from an economic viewpoint the conventional tests give adequate information in the case of acute renal failure. Radioisotope renogram appears to hold great promise for both clinical and research applications. The equipment required for this application, however, is so costly that it would only be financially feasible for major centres such as a Faculty of Veterinary Science. Much information can be gained from referred clinical cases

  10. Primate drum kit: a system for studying acoustic pattern production by non-human primates using acceleration and strain sensors.

    Science.gov (United States)

    Ravignani, Andrea; Matellán Olivera, Vicente; Gingras, Bruno; Hofer, Riccardo; Rodríguez Hernández, Carlos; Sonnweber, Ruth-Sophie; Fitch, W Tecumseh

    2013-01-01

    The possibility of achieving experimentally controlled, non-vocal acoustic production in non-human primates is a key step to enable the testing of a number of hypotheses on primate behavior and cognition. However, no device or solution is currently available, with the use of sensors in non-human animals being almost exclusively devoted to applications in food industry and animal surveillance. Specifically, no device exists which simultaneously allows: (i) spontaneous production of sound or music by non-human animals via object manipulation, (ii) systematical recording of data sensed from these movements, (iii) the possibility to alter the acoustic feedback properties of the object using remote control. We present two prototypes we developed for application with chimpanzees (Pan troglodytes) which, while fulfilling the aforementioned requirements, allow to arbitrarily associate sounds to physical object movements. The prototypes differ in sensing technology, costs, intended use and construction requirements. One prototype uses four piezoelectric elements embedded between layers of Plexiglas and foam. Strain data is sent to a computer running Python through an Arduino board. A second prototype consists in a modified Wii Remote contained in a gum toy. Acceleration data is sent via Bluetooth to a computer running Max/MSP. We successfully pilot tested the first device with a group of chimpanzees. We foresee using these devices for a range of cognitive experiments. PMID:23912427

  11. Conductive Fe3O4 Nanoparticles Accelerate Syntrophic Methane Production from Butyrate Oxidation in Two Different Lake Sediments

    Science.gov (United States)

    Zhang, Jianchao; Lu, Yahai

    2016-01-01

    Syntrophic methanogenesis is an essential link in the global carbon cycle and a key bioprocess for the disposal of organic waste and production of biogas. Recent studies suggest direct interspecies electron transfer (DIET) is involved in electron exchange in methanogenesis occurring in paddy soils, anaerobic digesters, and specific co-cultures with Geobacter. In this study, we evaluate the possible involvement of DIET in the syntrophic oxidation of butyrate in the enrichments from two lake sediments (an urban lake and a natural lake). The results showed that the production of CH4 was significantly accelerated in the presence of conductive nanoscale Fe3O4 or carbon nanotubes in the sediment enrichments. Observations made with fluorescence in situ hybridization and scanning electron microscope indicated that microbial aggregates were formed in the enrichments. It appeared that the average cell-to-cell distance in aggregates in nanomaterial-amended enrichments was larger than that in aggregates in the non-amended control. These results suggested that DIET-mediated syntrophic methanogenesis could occur in the lake sediments in the presence of conductive materials. Microbial community analysis of the enrichments revealed that the genera of Syntrophomonas, Sulfurospirillum, Methanosarcina, and Methanoregula were responsible for syntrophic oxidation of butyrate in lake sediment samples. The mechanism for the conductive-material-facilitated DIET in butyrate syntrophy deserves further investigation. PMID:27597850

  12. Primate Drum Kit: A System for Studying Acoustic Pattern Production by Non-Human Primates Using Acceleration and Strain Sensors

    Directory of Open Access Journals (Sweden)

    W. Tecumseh Fitch

    2013-07-01

    Full Text Available The possibility of achieving experimentally controlled, non-vocal acoustic production in non-human primates is a key step to enable the testing of a number of hypotheses on primate behavior and cognition. However, no device or solution is currently available, with the use of sensors in non-human animals being almost exclusively devoted to applications in food industry and animal surveillance. Specifically, no device exists which simultaneously allows: (i spontaneous production of sound or music by non-human animals via object manipulation, (ii systematical recording of data sensed from these movements, (iii the possibility to alter the acoustic feedback properties of the object using remote control. We present two prototypes we developed for application with chimpanzees (Pan troglodytes which, while fulfilling the aforementioned requirements, allow to arbitrarily associate sounds to physical object movements. The prototypes differ in sensing technology, costs, intended use and construction requirements. One prototype uses four piezoelectric elements embedded between layers of Plexiglas and foam. Strain data is sent to a computer running Python through an Arduino board. A second prototype consists in a modified Wii Remote contained in a gum toy. Acceleration data is sent via Bluetooth to a computer running Max/MSP. We successfully pilot tested the first device with a group of chimpanzees. We foresee using these devices for a range of cognitive experiments.

  13. Conductive Fe3O4 Nanoparticles Accelerate Syntrophic Methane Production from Butyrate Oxidation in Two Different Lake Sediments.

    Science.gov (United States)

    Zhang, Jianchao; Lu, Yahai

    2016-01-01

    Syntrophic methanogenesis is an essential link in the global carbon cycle and a key bioprocess for the disposal of organic waste and production of biogas. Recent studies suggest direct interspecies electron transfer (DIET) is involved in electron exchange in methanogenesis occurring in paddy soils, anaerobic digesters, and specific co-cultures with Geobacter. In this study, we evaluate the possible involvement of DIET in the syntrophic oxidation of butyrate in the enrichments from two lake sediments (an urban lake and a natural lake). The results showed that the production of CH4 was significantly accelerated in the presence of conductive nanoscale Fe3O4 or carbon nanotubes in the sediment enrichments. Observations made with fluorescence in situ hybridization and scanning electron microscope indicated that microbial aggregates were formed in the enrichments. It appeared that the average cell-to-cell distance in aggregates in nanomaterial-amended enrichments was larger than that in aggregates in the non-amended control. These results suggested that DIET-mediated syntrophic methanogenesis could occur in the lake sediments in the presence of conductive materials. Microbial community analysis of the enrichments revealed that the genera of Syntrophomonas, Sulfurospirillum, Methanosarcina, and Methanoregula were responsible for syntrophic oxidation of butyrate in lake sediment samples. The mechanism for the conductive-material-facilitated DIET in butyrate syntrophy deserves further investigation. PMID:27597850

  14. A neutron booster for spallation sources--application to accelerator driven systems and isotope production

    CERN Document Server

    Galy, J; Van Dam, H; Valko, J

    2002-01-01

    One can design a critical system with fissile material in the form of a thin layer on the inner surface of a cylindrical neutron moderator such as graphite or beryllium. Recently, we have investigated the properties of critical and near critical systems based on the use of thin actinide layers of uranium, plutonium and americium. The thickness of the required fissile layer depends on the type of fissile material, its concentration in the layer and on the geometrical arrangement, but is typically in the mu m-mm range. The resulting total mass of fissile material can be as low as 100 g. Thin fissile layers have a variety of applications in nuclear technology--for example in the design neutron amplifiers for medical applications and 'fast' islands in thermal reactors for waste incineration. In the present paper, we investigate the properties of a neutron booster unit for spallation sources and isotope production. In those applications a layer of fissile material surrounds the spallation source. Such a module cou...

  15. Optimizing production of Pb beams for 205,210Pb analysis by Accelerator Mass Spectrometry

    Science.gov (United States)

    Sookdeo, Adam; Cornett, Jack; Kieser, William E.

    2015-10-01

    The measurement of rare radioactive lead isotopes (205Pb or 210Pb) by AMS requires the production of strong Pb negative molecular anion beams from the ion source. This paper summarizes the results of tests of different target composition on the strength and stability of 208PbF3- currents and 210Pb counts. In an 834 SIMS-type Cs+ sputter source, the superhalogen, PbF3- had the largest current or ionization efficiency from a survey of Pb molecular anions. The target matrix that produced the largest current of PbF3- was composed of PbF2, AgF2 and CsF. The ratio of AgF2 and CsF does not affect the ionization efficiency of PbF3-. Chemically refluxed targets of PbF2, AgF2 and CsF increased the ionization efficiency of PbF3-. The count rate of the rare isotope, 210Pb, was increased with the addition of microgram quantities of stable PbF2 to the targets. In an SO-110 type Cs+ sputter source the ionization efficiency of PbF3- was increased with lower rather than higher Cs+ fluence.

  16. Radioisotopic splenoportography in patients with portal hypertension

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-05-01

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

  17. Radioisotopic splenoportography in patients with portal hypertension.

    Science.gov (United States)

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

    1989-05-01

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

  18. Radioisotopic splenoportography in patients with portal hypertension

    International Nuclear Information System (INIS)

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

  19. VELOCIRAPTOR: An X-band photoinjector and linear accelerator for the production of Mono-Energetic {gamma}-rays

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.G., E-mail: anderson131@llnl.gov [Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94551 (United States); Albert, F.; Bayramian, A.J.; Beer, G.; Bonanno, R.E.; Cross, R.R.; Deis, G.; Ebbers, C.A.; Gibson, D.J.; Hartemann, F.V.; Houck, T.L.; Marsh, R.A.; McNabb, D.P.; Messerly, M.J.; Scarpetti, R.D.; Shverdin, M.Y.; Siders, C.W.; Wu, S.S.; Barty, C.P.J. [Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94551 (United States); Adolphsen, C.E. [SLAC National Accelerator Laboratory, 2575 Sand Hill Rd., Menlo Park, CA 94025 (United States); and others

    2011-11-21

    The rf photoinjector and linear accelerator in the Mono-Energetic Gamma-ray (MEGa-ray) facility at LLNL is presented. This machine uses 11.4 GHz rf technology to accelerate a high-brightness electron beam up to 250 MeV to produce MeV {gamma}-rays through Compton scattering with a Joule-class laser pulse. Compton scattering-based generation of high flux, narrow bandwidth {gamma}-rays places stringent requirements on the performance of the accelerator. The component parts of the accelerator are presented and their requirements described. Simulations of expected electron beam parameters and the resulting light source properties are presented.

  20. Annual report 1991 of Munich University and Technical University Accelerator Laboratory

    International Nuclear Information System (INIS)

    The experimental work in the Accelerator Laboratory contains investigations of nuclear reactions and nuclear structure, studies of atom physics and the application of nuclear physics methods in physics and in interdisciplinary research. These applications are acceleration mass spectrometry to detect traces of radio-isotopes and material analysis with particle beams. The development of apparatus in the fields of accelereator construction, ion sources and targets are at the heart of the laboratory and help to establish its reputation. They are of the greatest importance for the education of students. The development stage for the superconducting post-accelerator TRITRON is complete and prototypes of the magnets and resonators were successfully tested and operated. The mass-production of all the components is under way or already finished. The standard injector for the tandem axxelerator and an injector for accelerator mass spectroscopy with stable isotopes are being newly designed. The experimental work is supplemented by the calculations of our theoretical collagues of core reaction mechanisms, core de-excitation and the Cerenkov radiation of core structures and transition strengths, by relativistic Hartree-Fock calculations and by star model calculations. (orig.)

  1. The downregulation of thioredoxin accelerated Neuro2a cell apoptosis induced by advanced glycation end product via activating several pathways.

    Science.gov (United States)

    Ren, Xiang; Ma, Haiying; Qiu, Yuanyuan; Liu, Bo; Qi, Hui; Li, Zeyu; Kong, Hui; Kong, Li

    2015-08-01

    Thioredoxin (Trx), a 12 kDa protein, has different functions in different cellular environments, playing important anti-oxidative and anti-apoptotic roles and regulating the expression of transcription factors. Advanced glycation end products (AGEs) are a heterogeneous group of irreversible adducts from glucose-protein condensation reactions and are considered crucial to the development of diabetic nephropathy, retinopathy, neurodegeneration and atherosclerosis. The aim of this study was to use a Trx inhibitor to investigate the effects and mechanism of Trx down-regulation on AGE-induced Neuro2a cell apoptosis. Neuro2a cells were cultured in vitro and treated with different conditions. The apoptosis and proliferation of Neuro2a cells were detected using flow cytometry, DNA-Ladder and CCK8 assays. Rho 123 was used to detect the mitochondrial membrane potential. ROS generation and caspase3 activity were detected using a DCFH-DA probe and micro-plate reader. Western blotting and real-time PCR were used to detect the expression of proteins and genes. We found that the down-regulation of thioredoxin could accelerate AGE-induced apoptosis in Neuro2a cells. A possible underlying mechanism is that the down-regulation of thioredoxin stimulated the up-regulation of ASK1, p-JNK, PTEN, and Txnip, as well as the down-regulation of p-AKT, ultimately increasing ROS levels and caspase3 activity.

  2. The downregulation of thioredoxin accelerated Neuro2a cell apoptosis induced by advanced glycation end product via activating several pathways.

    Science.gov (United States)

    Ren, Xiang; Ma, Haiying; Qiu, Yuanyuan; Liu, Bo; Qi, Hui; Li, Zeyu; Kong, Hui; Kong, Li

    2015-08-01

    Thioredoxin (Trx), a 12 kDa protein, has different functions in different cellular environments, playing important anti-oxidative and anti-apoptotic roles and regulating the expression of transcription factors. Advanced glycation end products (AGEs) are a heterogeneous group of irreversible adducts from glucose-protein condensation reactions and are considered crucial to the development of diabetic nephropathy, retinopathy, neurodegeneration and atherosclerosis. The aim of this study was to use a Trx inhibitor to investigate the effects and mechanism of Trx down-regulation on AGE-induced Neuro2a cell apoptosis. Neuro2a cells were cultured in vitro and treated with different conditions. The apoptosis and proliferation of Neuro2a cells were detected using flow cytometry, DNA-Ladder and CCK8 assays. Rho 123 was used to detect the mitochondrial membrane potential. ROS generation and caspase3 activity were detected using a DCFH-DA probe and micro-plate reader. Western blotting and real-time PCR were used to detect the expression of proteins and genes. We found that the down-regulation of thioredoxin could accelerate AGE-induced apoptosis in Neuro2a cells. A possible underlying mechanism is that the down-regulation of thioredoxin stimulated the up-regulation of ASK1, p-JNK, PTEN, and Txnip, as well as the down-regulation of p-AKT, ultimately increasing ROS levels and caspase3 activity. PMID:26142569

  3. Production-passage-time approximation: a new approximation method to accelerate the simulation process of enzymatic reactions.

    Science.gov (United States)

    Kuwahara, Hiroyuki; Myers, Chris J

    2008-09-01

    Given the substantial computational requirements of stochastic simulation, approximation is essential for efficient analysis of any realistic biochemical system. This paper introduces a new approximation method to reduce the computational cost of stochastic simulations of an enzymatic reaction scheme which in biochemical systems often includes rapidly changing fast reactions with enzyme and enzyme-substrate complex molecules present in very small counts. Our new method removes the substrate dissociation reaction by approximating the passage time of the formation of each enzyme-substrate complex molecule which is destined to a production reaction. This approach skips the firings of unimportant yet expensive reaction events, resulting in a substantial acceleration in the stochastic simulations of enzymatic reactions. Additionally, since all the parameters used in our new approach can be derived by the Michaelis-Menten parameters which can actually be measured from experimental data, applications of this approximation can be practical even without having full knowledge of the underlying enzymatic reaction. Here, we apply this new method to various enzymatic reaction systems, resulting in a speedup of orders of magnitude in temporal behavior analysis without any significant loss in accuracy. Furthermore, we show that our new method can perform better than some of the best existing approximation methods for enzymatic reactions in terms of accuracy and efficiency. PMID:18662102

  4. LED照明产品加速衰减试验方法研究%Accelerated Luminous Depreciation Testing for LED Lighting Products

    Institute of Scientific and Technical Information of China (English)

    钱诚; 孙博; 曹峻松

    2014-01-01

    With the application of energy-saving, environmental and durable LED lighting products, the reliability testing has become a pivot point for the large scale industrialization and popularization. The paper briefly introduces two methods to be respectively applied in the accelerated depreciation testing for the luminous flex of LED lighting products and the life of outdoor LED-driving power, which can sharply shorten the time for lifetime test, providing references for the LED lighting products’ reliability evaluation.

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

    Science.gov (United States)

    Duzik, Adam J.; Choi, Sang H.

    2016-01-01

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

  6. 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.

  7. Application of radioisotopes to studies of crystal imperfections

    International Nuclear Information System (INIS)

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

  8. Linear Accelerators

    CERN Document Server

    Vretenar, M

    2014-01-01

    The main features of radio-frequency linear accelerators are introduced, reviewing the different types of accelerating structures and presenting the main characteristics aspects of linac beam dynamics.

  9. Determination of the radiological impact of radioisotope waste disposal

    International Nuclear Information System (INIS)

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

  10. Results with radioisotope techniques in veterinary science in Hungary

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

    Adkins, Harold E.; Bearden, Thomas E.

    1991-01-01

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

  12. Ablation response testing of simulated radioisotope power supplies

    Science.gov (United States)

    Lutz, Steven A.; Chan, Chris C.

    1994-05-01

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

  13. The application of radioisotopes in the Argentine technology

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2012-12-01

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

  15. The Use of Radioisotopes to Study the Absorption, Distribution and Elimination of Various Insecticides in Animals

    International Nuclear Information System (INIS)

    When insecticides are used against farm-animal parasites it is important to ensure that no harm is done to the health of the animal or the consumer. Radioisotopes provide a means of studying the behaviour of labelled insecticides in animal organisms and of obtaining extremely accurate data on residues of insecticides and insecticide decomposition products in meat and milk. The paper gives details on the rate at which DDT-C14, polychloropinene-Cl36 and chlorophos-P32 are absorbed through the skin, accumulated in the organs and tissues and eliminated from the organisms of farm and laboratory animals. (author)

  16. Enzymatic synthesis of radioisotope-labeled nucleotides from the corresponding labeled nitrogen bases

    International Nuclear Information System (INIS)

    The authors have developed a procedure that permits the production of nucleotides multiply labeled with various radioisotopes, with a molar radioactivity equal to the molar radioactivity of the original nitrogen bases. The methods of isolation and purification of the enzyme preparations were studied on the enzyme systems converting nitrogen bases to nucleoside triphosphates in the presence of phosphoribosyl pyrophosphate or ribose-5-phosphate. The presence of nucleotide impurities in the enzyme preparation was determined spectrophotometrically. The authors were able to practically avoid nucleotide impurities by salting out the protein fraction of interest with ammonium sulfate. The authors succeeded in reducing the content of nucleotides in the enzyme preparation by a factor of 40

  17. International topical meeting on nuclear research applications and utilization of accelerators. Book of abstracts

    International Nuclear Information System (INIS)

    Applications of particle accelerators cover a number of areas, from strategic and applied research, safety and security, environmental applications, materials research and analytical sciences, to radioisotope production and radiation processing. Accelerator based techniques and pulsed neutron sources are expected to lead to new initiatives in materials research of relevance for both the nuclear and non-nuclear fields. Material science studies with the use of accelerators, neutron beams and other nuclear analytical methods are relevant to the development of advanced reactors, nuclear fuel cycle needs and fusion research. In this regard, a better understanding of the irradiation effects in materials for energy and non-energy applications is needed, and is reflected in accelerator techniques for modification and analysis of materials for nuclear technologies. Accelerator applications for innovative nuclear systems aiming at rad-waste transmutation (e.g., accelerator driven systems) are being pursued in many countries. Research and development using accelerators involves a broad spectrum of skills to build a cadre of trained experts in nuclear techniques in IAEA Member States, and to generate knowledge for innovative methodologies and tools. The present conference is also being held in cooperation with the American Nuclear Society (ANS), which successfully organized the series of accelerator applications conferences known as AccApp. The ANS series of topical meetings has provided a forum for the global exchange of scientific and technical knowledge on a wide variety of related topics since the first AccApp took place in 1997 in Albuquerque, USA. The last conference which was held in 2007 in Pocatello, USA, was jointly organized by the ANS and the IAEA. The main objectives of the conference are to promote exchange of information among IAEA Member States representatives/delegates and to discuss new trends in accelerator applications including nuclear materials research

  18. Use of copper radioisotopes in investigating disorders of copper metabolism

    Energy Technology Data Exchange (ETDEWEB)

    Camakaris, J.; Voskoboinik, I.; Brooks, H.; Greenough, M. [University of Melbourne, Parkville, VIC (Australia). Department of Genetics; Smith, S. [Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW (Australia). Radiopharmaceuticals Division; Mercer, J. [Deakin University, Rusden Campus, Clayton, VIC (Australia). Centre of Cellular and Molecular Biology

    1998-12-31

    Full text: Copper is an essential trace element for life as a number of vital enzymes require it. Copper deficiency can lead to neurological disorders, osteoporosis and weakening of arteries. However Cu is also highly toxic and homeostatic mechanisms have evolved to maintain Cu at levels which satisfy requirements but do not cause toxicity. Toxicity is mediated by the oxidative capacity of Cu and its ability to generate toxic free radicals. There are several acquired and inherited diseases due to either Cu toxicity or Cu deficiency. The study of these diseases facilitates identification of genes and proteins involved in copper homeostasis, and this in turn will provide rational therapeutic approaches. Our studies have focused on Menkes disease in humans which is an inherited and usually lethal copper deficiency. Using copper radioisotopes {sup 64}Cu (t 1/2 = 12.8 hr) and {sup 67}Cu (t 1/2 = 61 hr) we have studied the protein which is mutated in Menkes disease. This is a transmembrane copper pump which is responsible for absorption of copper into the body and also functions to pump out excess Cu from cells when Cu is elevated. It is therefore a vital component of normal Cu homeostasis. We have provided the first biochemical evidence that the Menkes protein functions as a P-type ATPase Cu pump (Voskoboinik et al., FEBS Letters, in press) and these data will be discussed. The assay involved pumping of radiocopper into purified membrane vesicles. Furthermore we have transfected normal and mutant Menkes genes into cells and are carrying out structure-function studies. We are also studying the role of amyloid precursor protein (APP) as a Cu transport protein in order to determine how Cu regulates this protein and its cleavage products. These studies will provide vital information on the relationship between Cu and APP and processes which lead to Alzheimers disease

  19. Remote control: Decommissioning RTGs [radioisotope theromelectric generators

    International Nuclear Information System (INIS)

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

  20. A roadmap for the development and validation of coated particle fuel for future space radioisotope heater units (RHUs) and radioisotope power systems (RPSs)

    Science.gov (United States)

    Sholtis, Joseph A.

    2001-02-01

    In early 1999, coated particle fuel was identified as offering promising advancements in design flexibility, performance, specific mass and volume, as well as safety for future space radioisotope heater units (RHUs) and radioisotope power systems (RPSs). Subsequent study, conducted during Fiscal Year 1999, provided confidence that these potential benefits were substantial and demonstrable if a modest follow-on investigative test effort was pursued. This paper lays out a roadmap for both immediate and near-term decision making, as well as any full-scale development and validation of coated particle fuel undertaken for future space RHUs, and RPSs. In an effort to obtain adequate and timely information at a reasonable cost for immediate and near-term decision making, as well as any subsequent development, production, and application decisions, a four-phased regimen of testing is identified. The four phases of testing are: (1) Pre-Decisional Testing: (2) Pre-Production Analytical Verification Testing: (3) Production Quality Assurance Testing: and (4) Post-Production Safety Verification Testing. Although all four of these phases of testing are considered essential, the first two phases are especially important for immediate and near-term decisions to advance and pursue coated particle fuel for space RHUs and RPSs. The third and fourth phases of testing are primarily identified and included for completeness at this early stage. It is concluded that there is every reason to believe that the potential benefits of coated particle fuel can be readily demonstrated through a modest investigative test effort. If such an effort is pursued and proves successful, coated particle fuel could then be developed with assurance that its ultimate benefits would revolutionize the design and space use of future RHUs and RPSs. It is hoped that this paper will serve as a starting point for further discussions and more specific planning activities aimed at advancing coated particle fuel for

  1. Simple production method for making 3 μg/cm2 cracked slacked carbon accelerator stripper foils

    International Nuclear Information System (INIS)

    A simple method for making thin 3 μg/cm2 carbon stripper foils for heavy ion bombardment and accelerator radiochronology is described along with a simple method for stripper foil thickness determination

  2. Production of high-energy colliding. gamma gamma. and. gamma. e beams with a high luminosity at VLEPP accelerators

    Energy Technology Data Exchange (ETDEWEB)

    Ginzburg, I.F.; Kotkin, G.L.; Serbo, V.G.; Tel' nov, V.I.

    1981-11-05

    Colliding ..gamma gamma.. and ..gamma..e beams with an energy and luminosity of the same order of magnitude as for e/sup +/e/sup -/ beams can be produced by scattering a laser light at the accelerators with colliding e/sup +/e/sup -/ beams with an energy > or approx. =100 GeV. Such accelerators are currently in the design stage.

  3. Radioisotope techniques for the study of protein turnover

    International Nuclear Information System (INIS)

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

  4. Radioisotope study of Eustachian tube. A preliminary report

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-08-01

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

  5. Optimization of water treatment facility by using radioisotope tracer

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  8. The use of radioisotopes for determination of complex equilibria

    International Nuclear Information System (INIS)

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

  9. Evaluation of a group of health professionals on the physics and toxicological concepts of the radiopharmaceuticals that uses 123I e 131I radioisotopes

    International Nuclear Information System (INIS)

    In order to evaluate the level of knowledge of a group of health professionals in the area west of the city of Rio de Janeiro, a survey of nurses, nursing technicians, doctors and graduate students in pharmacy, concerning production, radiation emitted, applications and toxicities of radiopharmaceuticals using 123I radioisotopes and 131I. These radioisotopes are widely used in Nuclear Medicine to aid in the diagnostic imaging and therapeutic procedures. In this paper is presented an approach on radiopharmaceuticals using radioisotopes mentioned above so that it has knowledge of what was asked to group of professionals here. With this work, it is expected to contribute to the knowledge of these professionals, as well as the general public, in Nuclear Physics and radiation protection concepts for the subject in question. (author)

  10. The cyclotron laboratory and the RFQ accelerator in Bern

    Energy Technology Data Exchange (ETDEWEB)

    Braccini, S.; Ereditato, A.; Kreslo, I.; Nirkko, M.; Weber, M. [Albert Einstein Center for Fundamental Physics, Laboratory for High Energy Physics (LHEP), University of Bern, Sidlerstrasse 5, CH-3012 Bern (Switzerland); Scampoli, P. [Albert Einstein Center for Fundamental Physics, Laboratory for High Energy Physics (LHEP), University of Bern, Sidlerstrasse 5, CH-3012 Bern, Switzerland and Department of Physical Sciences, University Federico II, Via Cintia, I-60126 Napoli (Italy); Bremen, K. von [SWAN Isotopen AG, Inselspital, CH-3010 Bern (Switzerland)

    2013-07-18

    Two proton accelerators have been recently put in operation in Bern: an 18 MeV cyclotron and a 2 MeV RFQ linac. The commercial IBA 18/18 cyclotron, equipped with a specifically conceived 6 m long external beam line ending in a separate bunker, will provide beams for routine 18-F and other PET radioisotope production as well as for novel detector, radiation biophysics, radioprotection, radiochemistry and radiopharmacy developments. The accelerator is embedded into a complex building hosting two physics laboratories and four Good Manufacturing Practice (GMP) laboratories. This project is the result of a successful collaboration between the Inselspital, the University of Bern and private investors, aiming at the constitution of a combined medical and research centre able to provide the most cutting-edge technologies in medical imaging and cancer radiation therapy. The cyclotron is complemented by the RFQ with the primary goals of elemental analysis via Particle Induced Gamma Emission (PIGE), and the detection of potentially dangerous materials with high nitrogen content using the Gamma-Resonant Nuclear Absorption (GRNA) technique. In this context, beam instrumentation devices have been developed, in particular an innovative beam profile monitor based on doped silica fibres and a setup for emittance measurements using the pepper-pot technique. On this basis, the establishment of a proton therapy centre on the campus of the Inselspital is in the phase of advanced study.

  11. Application of the approaches of Total Quality during the transportation and distribution of radioisotopes

    International Nuclear Information System (INIS)

    Nowadays a more and more growing tendency is manifested at managerial level toward the installation of Systems of Guarantee of Quality (SGC). In any company that doesn't have implanted a system of the quality, the economic losses for non quality can surpass 20%. In the companies dedicated to the transport of radioactive material, the cost of the non quality can be motivated fundamentally by: the late delivery of the radioisotopic material, for defects generated by the transport one that you/they affect the functional capacity of the product, and for losses of the bundles during the transport of the same ones. The previously signal elements can be enough reasons to take the managerial level to decide in favor of the installation of a SGC in these companies. With the present work, the authors show the possibility to introduce some inherent approaches to the concept of Total Quality during the implementation of a SGC supported in the normative ISO-9002, in companies of reduced budget dedicated to the transport and distribution of radioisotopic products

  12. Biological Effects of Transmutation and Decay of Incorporated Radioisotopes. Proceedings of a Panel

    International Nuclear Information System (INIS)

    A Panel on the Biological Effects of Transmutation and Decay of Incorporated Radioisotopes was held by the International Atomic Energy Agency in Vienna on 9 - 13 October 1967. Fourteen experts from nine countries, representing various relevant disciplines, attended. The Panel investigated the modes and mechanisms of action associated with transmutation and decay radiation events. The aim was to achieve a clearer picture of the present status of these studies and at the same time to help define the main problems and suggest possible ways of solving them. The Panel might thus go some way towards defining the hazards of using labelled compounds in human beings and standards for setting body-burden levels. The papers and discussions centred on the role which such physical and chemical factors of radioisotope decay as transmutation, recoil energy and disintegration radiation play in producing injury when such isotopes as 3H, 14C and 32P are incorporated into vital cellular macro-molecules. Past and present studies on mutation production, chromosome aberration, macro- molecular lesions, and cell survival, were reviewed and analysed. Data, concepts and experimental approaches were examined with an eye to possible productive lines of investigation. The present book contains the papers and discussions

  13. Progress in the Use of Isotopes: The Atomic Triad - Reactors, Radioisotopes and Radiation

    Science.gov (United States)

    Libby, W. F.

    1958-08-04

    Recent years have seen a substantial growth in the use of isotopes in medicine, agriculture, and industry: up to the minute information on the production and use of isotopes in the U.S. is presented. The application of radioisotopes to industrial processes and manufacturing operations has expanded more rapidly than any one except its most ardent advocates expected. New uses and new users are numerous. The adoption by industry of low level counting techniques which make possible the use of carbon-14 and tritium in the control of industrial processes and in certain exploratory and research problems is perhaps most promising of current developments. The latest information on savings to industry will be presented. The medical application of isotopes has continued to develop at a rapid pace. The current trend appears to be in the direction of improvements in technique and the substitution of more effective isotopes for those presently in use. Potential and actual benefits accruing from the use of isotopes in agriculture are reviewed. The various methods of production of radioisotopes are discussed. Not only the present methods but also interesting new possibilities are covered. Although isotopes are but one of the many peaceful uses of the atom, it is the first to pay its way. (auth)

  14. Recent developments in the application of electron accelerators for polymer processing

    Science.gov (United States)

    Chmielewski, A. G.; Al-Sheikhly, M.; Berejka, A. J.; Cleland, M. R.; Antoniak, M.

    2014-01-01

    There are now over 1700 high current, electron beam (EB) accelerators being used world-wide in industrial applications, most of which involve polymer processing. In contrast to the use of heat, which transfers only about 5-10% of input energy into energy useful for materials modification, radiation processing is very energy efficient, with 60% or more of the input energy to an accelerator being available for affecting materials. Historic markets, such as the crosslinking of wire and cable jacketing, of heat shrinkable tubings and films, of partial crosslinking of tire components and of low-energy EB to cure or dry inks and coatings remain strong. Accelerator manufacturers have made equipment more affordable by down-sizing units while maintaining high beam currents. Very powerful accelerators with 700 kW output have made X-ray conversion a practical alternative to the historic use of radioisotopes, mainly cobalt-60, for applications as medical device sterilization. New EB end-uses are emerging, such as the development of nano-composites and nano-gels and the use of EB processing to facilitate biofuel production. These present opportunities for future research and development.

  15. Material studies in the frame of CLIC Accelerating structures production conducted within the Mechanics program together with Metso Oy

    CERN Document Server

    Nurminen, Janne

    2012-01-01

    MeChanICs (Marie Curie Linking Industry to CERN) is an Industry to Academia Partnership and Pathways (IAPP) platform for precision manufacturing knowledge exchange bringing together five Finnish manufacturing companies with Helsinki Insitute of Physics (HIP) and CERN. The scientific objective of MeChanICs project is to contribute to the manufacturing RTD of CLIC enabling technologies. The focus is on the design, materials, machining, brazing and assembly of A CLIC accelerating structure. This study deals with the materials work package of the program and wants to explore the following items: 1) producing copper accelerating structures for CLIC from raw copper powder by near net shape hot isostatic pressing (HIP). 2) The feasibility to use HIP diffusion bonding of the accelerator structures as a function of surface quality and applied temperature and pressure. 3) Brazing for CLIC AS auxiliary systems, like water cooling or damping manifolds, to the disc stack by coating one of the brazing partners with an enab...

  16. STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    W. JOHNSON; R. RYDER; P. RITTENHOUSE

    2001-01-01

    The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria

  17. Leaky Fermi accelerators

    CERN Document Server

    Shah, Kushal; Rom-Kedar, Vered; Turaev, Dmitry

    2015-01-01

    A Fermi accelerator is a billiard with oscillating walls. A leaky accelerator interacts with an environment of an ideal gas at equilibrium by exchange of particles through a small hole on its boundary. Such interaction may heat the gas: we estimate the net energy flow through the hole under the assumption that the particles inside the billiard do not collide with each other and remain in the accelerator for sufficiently long time. The heat production is found to depend strongly on the type of the Fermi accelerator. An ergodic accelerator, i.e. one which has a single ergodic component, produces a weaker energy flow than a multi-component accelerator. Specifically, in the ergodic case the energy gain is independent of the hole size, whereas in the multi-component case the energy flow may be significantly increased by shrinking the hole size.

  18. Future accelerators (?)

    Energy Technology Data Exchange (ETDEWEB)

    John Womersley

    2003-08-21

    I describe the future accelerator facilities that are currently foreseen for electroweak scale physics, neutrino physics, and nuclear structure. I will explore the physics justification for these machines, and suggest how the case for future accelerators can be made.

  19. Sourceless formation evaluation. An LWD solution providing density and neutron measurements without the use of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Griffiths, R.; Reichel, N. [Schlumberger, Sungai Buloh (Malaysia)

    2013-08-01

    For many years the industry has been searching for a way to eliminate the logistical difficulties and risk associated with deployment of radioisotopes for formation evaluation. The traditional gamma-gamma density (GGD) measurement uses the scattering of 662-keV gamma rays from a 137Cs radioisotopic source, with a 30.17-year half-life, to determine formation density. The traditional neutron measurement uses an Am-Be source emitting neutrons with an energy around 4 MeV, with a half-life of 432 years. Both these radioisotopic sources pose health, security, and environmental risks. Pulsed-neutron generators have been used in the industry for several decades in wireline tools and more recently in logging-while-drilling tools. These generators produce 14-MeV neutrons, many of which interact with the nuclei in the formation. Elastic collisions allow a neutron porosity measurement to be derived, which has been available to the industry since 2005. Inelastic interactions are typically followed by the emission of a variety of high-energy gamma rays. Similar to the case of the GGD measurement, the transport and attenuation of these gamma rays is a strong function of the formation density. However, the gamma-ray source is now distributed over a volume within the formation, where gamma rays have been induced by neutron interactions and the source can no longer be considered to be a point as in the case of a radioisotopic source. In addition, the extent of the induced source region depends on the transport of the fast neutrons from the source to the point of gamma-ray production. Even though the physics is more complex, it is possible to measure the formation density if the fast neutron transport is taken into account when deriving the density answer. This paper briefly reviews the physics underlying the sourceless neutron porosity and recently introduced neutron-gamma density (SNGD) measurement, demonstrates how they can be used in traditional workflows and illustrates their

  20. Commissioning and initial operation of the Isotope Production Facility at the Los Alamos Neutron Science Center (LANSCE).

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, K. F. (Kenneth F.); Alvestad, H. W. (Henry W.); Barkley, W. C. (Walter C.); Barlow, D. B. (David B.); Barr, D. S. (Dean S.); Bennett, L. S. (Langdon S.); Bitteker, L. J. (Leo J.); Bjorklund, E. A. (Eric A.); Boedeker, W.; Borden, M. J. (Michael J.); Cardon, R.; Carr, G. (Gary); Casados, J. L. (Jeffrey L.); Cohen, Stanley; Cordova, J. F. (Justo J.; Faucett, John Allen,; Fresquez, M. (Matthew); Gallegos, F. R. (Floyd R.); Gilpatrick, J. D. (John Douglas); Gonzales, F. (Fermin); Gorman, F. W. (Frederick W.); Gulley, M. S. (Mark S.); Hall, M. J. (Michael J.); Hayden, D. J. (David J.); Heaton, R. C. (Richard C.); Henderson, D. B. (Dale B.); Ireland, D. B. (David B.); Jacobson, E. G. (Edward G.); Johns, G. D. (Glen D.); Kersteins, D. M. (Debora M.); Maestas, A. J. (Alfred J.); Martinez, A. M. (Alexandra M.); Martinez, D. G. (Derwin G.); Martinez, G.; Martinez, J.; Martinez, M. P. (Martin P.); Merl, R. B. (Robert B.); Merrill, J. B. (John B.); Meyer, B. J. (Bruce J.); Meyer, R., Sr.; Milder, M.; Morgan, E.; Nortier, M.; O' Hara, J. F. (James F.); Olivas, F. R. (Felix R.); Oothoudt, Michael; Pence, T. D. (Tim D.); Perets, Mikhaʾel ben Yosef; Peterson, E.; Pillai, C. (Chandra); Romero, F.; Rose, C.; Rybarcyk, L. J. (Lawrence J.); Sanchez, G. (Gary); Sandoval, J. B. (Jacob B.); Schaller, S. (Stuart); Shelley, F. E. (Fred E.); Shurter, R. B. (Robert B.); Sommer, Walter F.; Stettler, M. W. (Matthew W.); Stockton, J. L. (Jerry L.); Sturrock, J. C. (James C.); Tomei, T. L. (Tony L.); Valdez, F.; Vigil, V. P. (Victor P.); Walstrom, P. L. (Peter L.); Wanco, P. M. (Peter M.); Wilmarth, J.

    2004-01-01

    The recently completed 100-MeV H{sup +} Isotope Production Facility (IPF) at the LANSCE will provide radioisotopes for medical research and diagnosis, for basic research and for commercial use. A change to the LANSCE accelerator facility allowed for the installation of the IPF. Three components make up the LANSCE accelerator: an injector that accelerates the H{sup +} beam to 750-KeV, a drift-tube linac (DTL) that increases the beam energy to 100-MeV, and a side-coupled cavity linac (SCCL) that accelerates the beam to 800-MeV. The transition region, a space between the DTL and the SCCL, was modified to permit the insertion of a kicker magnet (23{sup o} kick angle) for the purpose of extracting a portion of the 100-MeV H{sup +} beam. A new beam line was installed to transport the extracted H{sup +} beam to the radioisotope production target chamber. This paper will describe the commissioning and initial operating experiences of IPF.

  1. Californium-252: a remarkable versatile radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Osborne-Lee, I.W.; Alexander, C.W.

    1995-10-10

    A product of the nuclear age, Californium-252 ({sup 252}Cf) has found many applications in medicine, scientific research, industry, and nuclear science education. Californium-252 is unique as a neutron source in that it provides a highly concentrated flux and extremely reliable neutron spectrum from a very small assembly. During the past 40 years, {sup 252}Cf has been applied with great success to cancer therapy, neutron radiography of objects ranging from flowers to entire aircraft, startup sources for nuclear reactors, fission activation for quality analysis of all commercial nuclear fuel, and many other beneficial uses, some of which are now ready for further growth. Californium-252 is produced in the High Flux Isotope Reactor (HFIR) and processed in the Radiochemical Engineering Development Center (REDC), both of which are located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The REDC/HFIR facility is virtually the sole supplier of {sup 252}Cf in the western world and is the major supplier worldwide. Extensive exploitation of this product was made possible through the {sup 252}Cf Market Evaluation Program, sponsored by the United States Department of Energy (DOE) [then the Atomic Energy Commission (AEC) and later the Energy Research and Development Administration (ERDA)]. This program included training series, demonstration centers, seminars, and a liberal loan policy for fabricated sources. The Market Evaluation Program was instituted, in part, to determine if large-quantity production capability was required at the Savannah River Laboratory (SRL). Because of the nature of the product and the means by which it is produced, {sup 252}Cf can be produced only in government-owned facilities. It is evident at this time that the Oak Ridge research facility can meet present and projected near-term requirements. The production, shipment, and sales history of {sup 252}Cf from ORNL is summarized herein.

  2. Californium-252: a remarkable versatile radioisotope

    International Nuclear Information System (INIS)

    A product of the nuclear age, Californium-252 (252Cf) has found many applications in medicine, scientific research, industry, and nuclear science education. Californium-252 is unique as a neutron source in that it provides a highly concentrated flux and extremely reliable neutron spectrum from a very small assembly. During the past 40 years, 252Cf has been applied with great success to cancer therapy, neutron radiography of objects ranging from flowers to entire aircraft, startup sources for nuclear reactors, fission activation for quality analysis of all commercial nuclear fuel, and many other beneficial uses, some of which are now ready for further growth. Californium-252 is produced in the High Flux Isotope Reactor (HFIR) and processed in the Radiochemical Engineering Development Center (REDC), both of which are located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The REDC/HFIR facility is virtually the sole supplier of 252Cf in the western world and is the major supplier worldwide. Extensive exploitation of this product was made possible through the 252Cf Market Evaluation Program, sponsored by the United States Department of Energy (DOE) [then the Atomic Energy Commission (AEC) and later the Energy Research and Development Administration (ERDA)]. This program included training series, demonstration centers, seminars, and a liberal loan policy for fabricated sources. The Market Evaluation Program was instituted, in part, to determine if large-quantity production capability was required at the Savannah River Laboratory (SRL). Because of the nature of the product and the means by which it is produced, 252Cf can be produced only in government-owned facilities. It is evident at this time that the Oak Ridge research facility can meet present and projected near-term requirements. The production, shipment, and sales history of 252Cf from ORNL is summarized herein

  3. Actual problems of the distribution of radioisotopes and the kinetics of their excretion

    International Nuclear Information System (INIS)

    The paper deals with the character of the distribution of radioisotopes (Cs, Rb, Sr, Ca, Ba, Ra, Ce, La, Pm, Sb, Te, Pu, Y, Zr, Ru, Nb, Po), depending on the way and rhythm of their administration, the physiological state of the organism and physico-chemical factors. It was shown that 10 to 18% of some radioisotopes (Cs137, Nb95, Zr95, Y91, Ru106, and Ce144) were retained in the lungs when administered by inhalation. Caesium and especially strontium are absorbed from the lungs extremely rapidly, while the absorption of ruthenium, cerium and particularly plutonium is slow. The type of distribution of radioactive isotopes does not depend on the species of the animal, as is sometimes the case with the kinetics of their elimination. The rate of Ce144 removal from canine and feline liver is exceedingly low, unlike that in rats, m ice, guinea pigs and rabbits. The amount of the deposited material and the kinetics of its elimination in case of Sr90 and Pu239 are determined by the rhythm and duration of the isotope intake. From the data presented it can be seen that the results of experiments with a single injection do not always characterize the kinetics of the accumulation of the isotope in cases of its continuous administration. Chelate compounds (EDTA, hexametaphosphate - HMP), isotope and non-isotope carriers, and the pH of the original solution change the distribution of hydrolysed elements (cerium, yttrium) and do not affect the type of distribution of elements that are highly-soluble in water. When the pH of the original solution increases, the amount of cerium and yttrium deposition also increases in the organs containing much reticuloendothelial elements (liver, spleen) and decreases in the skeleton and kidneys. The acceleration of the Ce144 and Y91 excretion caused by the chelate compounds (EDTA, HMP) is delayed with the increase of the pH of the original solution. (author)

  4. Thermophotoelectric converter with radioisotope source of thermal radiation

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  6. Process for radioisotope recovery and system for implementing same

    Science.gov (United States)

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

    2007-01-02

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

  7. Summary. The 19th quality control survey for radioisotope in vitro tests in Japan, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Shishiba, Yoshimasa; Shimizu, Taeko [Toranomon Hospital, Tokyo (Japan); Ichihara, Kiyoshi; Kousaka, Tadako; Kobayashi, Hisae; Tsushima, Toshio; Hoshino, Minoru; Mori, Mikio

    1998-11-01

    This summary concerns results of the survey in the title performed by the Subcommittee for Radioisotope in vitro Test in the Medical and Pharmaceutical Committee, Japan Radioisotope Association. The survey was conducted in 161 facilities in Japan including public and private hospitals, health institutes and reagent manufacturers. Samples were sent to the facilities and subjected to examinations of intra- and inter-day reproducibility, freeze-thawing effects and periodical changes of the measured values. Methods employed were RIA, IRMA, EIA, ELISA, LPIA, PAMIA, FIA, FPIA, NIA, LAT, CLIA and ECLIA. Results were analyzed by variation coefficients in the kit and between the kits. Samples were for: growth hormone, somatomedin C, follicle stimulating hormone, luteinizing hormone, prolactin, thyroid stimulating hormone, triiodothyronine, thyroxine, thyroxine binding globulin, calcitonin, insulin, C-peptide, glucagon, gastrin, testosterone, estradiol, progesterone, {beta}human chorionic gonadotropin, 17{alpha}-hydroxyprogesterone, aldosterone, cortisol, dehydroepiandrosterone, renin, immunogloblin E, digoxin, {alpha}-fetoprotein, carcinoembryonic antigen, tissue polypeptide antigen, CA125, CA19-9, CA15-3, prostatic acid phosphatase, prostate specific antigen, {beta}{sub 2}-microgloblin and ferritin. Results were found rather unsatistactory for some products in the clinical practice, necessary for improvement of detection for some tests and needed for some kits for solving the problems of difference between kits and of matrix effect. (K.H)

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

    International Nuclear Information System (INIS)

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

  9. Radioisotope Concentration in Lake Sediments of Maracaibo, Venezuela

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  11. [Set of radiocirculographic attachments for radioisotope laboratories].

    Science.gov (United States)

    Devishev, M I; Panfilova, N P; Ostrogradskaia, M G

    1980-01-01

    A set of radiocirculographic attachments is offered which serves for calibration and verification of readings taken from the apparatus during radiographic procedures. The set is designed for operation with all colimators of radiocirculographs produced in the USSR and Hungarian People's Republic. The set is able to imitate the investigation geometry, accumulation of radioactivity in the organ under study, absorption and scattering of radioactivty in the organism tissues. Series production of this device has already been initiated. PMID:7392870

  12. Radioisotopes Produced by Neutron Irradiation of Food

    OpenAIRE

    Seviour, Rebecca; Albright, Simon

    2016-01-01

    The use of neutrons for cargo interrogation has the potential to drastically improve threat detection. Previous research has focussed on the production of 24Na, based on the isotopes produced in pharmaceuticals and medical devices. For both the total acitivity and the ingestion dose we show that a variety of isotopes contribute and that 24Na is only dominant under certain conditions. The composition of the foods has a strong influence on the resulting activity and ingestion dose suggesting th...

  13. Radioisotope barium sulphate gauge MZB-2

    International Nuclear Information System (INIS)

    A method and the gauge for measuring content of barium sulphate are described. The gauge is intended for fast determination of barium sulphate in barite ore and in output products of the enrichment process. The measuring range 60-100% of BaSO4, accuracy ±1% and measuring time 60 s were reached. The barium sulphate gauge is used in barite mine ''Boguszow'' in Poland. (author)

  14. Advanced radioisotope power source options for Pluto Express

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. 1Alpha,25-(OH)2D3 acts in the early phase of osteoblast differentiation to enhance mineralization via accelerated production of mature matrix vesicles.

    Science.gov (United States)

    Woeckel, V J; Alves, R D A M; Swagemakers, S M A; Eijken, M; Chiba, H; van der Eerden, B C J; van Leeuwen, J P T M

    2010-11-01

    1Alpha,25-dihydroxyitamin D(3) (1,25D3) deficiency leads to impaired bone mineralization. We used the human pre-osteoblastic cell line SV-HFO, which forms within 19 days of culture an extracellular matrix that starts to mineralize around day 12, to examine the mechanism by which 1,25D3 regulates osteoblasts and directly stimulates mineralization. Time phase studies showed that 1,25D3 treatment prior to the onset of mineralization, rather than during mineralization led to accelerated and enhanced mineralization. This is supported by the observation of unaltered stimulation by 1,25D3 even when osteoblasts were devitalized just prior to onset of mineralization and after 1,25D3 treatment. Gene Chip expression profiling identified the pre-mineralization and mineralization phase as two strongly distinctive transcriptional periods with only 0.6% overlap of genes regulated by 1,25D3. In neither phase 1,25D3 significantly altered expression of extracellular matrix genes. 1,25D3 significantly accelerated the production of mature matrix vesicles (MVs) in the pre-mineralization. Duration rather than timing determined the extent of the 1,25D3 effect. We propose the concept that besides indirect effects via intestinal calcium uptake 1,25D3 directly accelerates osteoblast-mediated mineralization via increased production of mature MVs in the period prior to mineralization. The accelerated deposition of mature MVs leads to an earlier onset and higher rate of mineralization. These effects are independent of changes in extracellular matrix protein composition. These data on 1,25D3, mineralization, and MV biology add new insights into the role of 1,25D3 in bone metabolism and emphasize the importance of MVs in bone and maintaining bone health and strength by optimal mineralization status.

  17. Optimizing pulse shaping and zooming for acceleration to high velocities and fusion neutron production on the Nike laser

    Science.gov (United States)

    Karasik, Max; Weaver, J. L.; Aglitskiy, Y.; Zalesak, S. T.; Velikovich, A. L.; Oh, J.; Obenschain, S. P.; Arikawa, Y.; Watari, T.

    2010-11-01

    We will present results from follow-on experiments to the record-high velocities of 1000 km/s achieved on Nike [Karasik et al., Phys. Plasmas 17, 056317 (2010) ], in which highly accelerated planar foils of deuterated polystyrene were made to collide with a witness foil to produce extreme shock pressures and result in heating of matter to thermonuclear temperatures. Still higher velocities and higher target densities are required for impact fast ignition. The aim of these experiments is shaping the driving pulse to minimize shock heating of the accelerated target and using the focal zoom capability of Nike to achieve higher densities and velocities. Spectroscopic measurements of electron temperature achieved upon impact will complement the neutron time-of-flight ion temperature measurement. Work is supported by US DOE and Office of Naval Research.

  18. Use of zooming and pulseshaping for acceleration to high velocities and fusion neutron production on the Nike laser

    Science.gov (United States)

    Karasik, Max; Weaver, J. L.; Aglitskiy, Y.; Kehne, D. M.; Zalesak, S. T.; Velikovich, A. L.; Oh, J.; Obenschain, S. P.; Arikawa, Y.

    2011-10-01

    We will present results from follow-on experiments to the record-high velocities of 1000 km/s achieved on Nike [Karasik et al, Phys. Plasmas 17, 056317(2010)], in which highly accelerated planar foils of deuterated polystyrene were made to collide with a witness foil to produce ~ 1 Gbar shock pressures and result in heating of matter to thermonuclear temperatures. Still higher velocities and higher target densities are required for impact fast ignition. The aim of these experiments is using the focal zoom capability of Nike and shaping the driving pulse to minimize shock heating of the accelerated target to achieve higher densities and velocities. In-flight target density is inferred from target heating upon collision via DD neutron time-of-flight ion temperature measurement. Work is supported by US DOE (NNSA) and Office of Naval Research. SAIC

  19. Direct Acceleration of Pickup Ions at the Solar Wind Termination Shock the Production of Anomalous Cosmic Rays

    CERN Document Server

    Ellison, D C; Baring, M G; Ellison, Donald C.; Jones, Frank C.; Baring, Matthew G.

    1999-01-01

    We have modeled the injection and acceleration of pickup ions at the solar wind termination shock and investigated the parameters needed to produce the observed Anomalous Cosmic Ray (ACR) fluxes. A non-linear Monte Carlo technique was employed, which in effect solves the Boltzmann equation and is not restricted to near-isotropic particle distribution functions. This technique models the injection of thermal and pickup ions, the acceleration of these ions, and the determination of the shock structure under the influence of the accelerated ions. The essential effects of injection are treated in a mostly self-consistent manner, including effects from shock obliquity, cross-field diffusion, and pitch-angle scattering. Using recent determinations of pickup ion densities, we are able to match the absolute flux of hydrogen in the ACRs by assuming that pickup ion scattering mean free paths, at the termination shock, are much less than an AU and that modestly strong cross-field diffusion occurs. Simultaneously, we mat...

  20. Production of ultrahigh-energy cosmic rays via one-shot acceleration of galactic cosmic rays by jets

    CERN Document Server

    Caprioli, Damiano

    2015-01-01

    We propose that ultra-high-energy (UHE) cosmic rays (CRs) above $10^{18}$eV are produced in relativistic jets of powerful active galactic nuclei via an original mechanism, which we dub "espresso" acceleration: "seed" galactic CRs with energies $\\lesssim 10^{17}$eV that penetrate the jet sideways receive a "one-shot" boost of a factor of $\\sim\\Gamma^2$ in energy, where $\\Gamma$ is the Lorentz factor of the relativistic flow. For typical jet parameters, a few per cent of the CRs in the host galaxy can undergo this process, and powerful blazars with $\\Gamma\\gtrsim 30$ may accelerate UHECRs up to more than $10^{20}$eV. The chemical composition of espresso-accelerated UHECRs is determined by the one at the Galactic CR knee, and is expected to be proton-dominated at $10^{18}$eV and increasingly heavy at higher energies, in agreement with recent observations of the Pierre Auger Observatory.