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Sample records for radioisotope production lab-d

  1. Present status of OAP radioisotope production

    International Nuclear Information System (INIS)

    Charoen, Sakda

    2006-01-01

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

  2. 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.

  3. Production and utilization of radioisotopes

    International Nuclear Information System (INIS)

    Sekine, Toshiaki; Matsuoka, Hiromitsu

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Williams, C.

    1975-01-01

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

  5. Energy-Recovery Linacs for Commercial Radioisotope Production

    International Nuclear Information System (INIS)

    Johnson, Rolland Paul

    2016-01-01

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

  6. Energy-Recovery Linacs for Commercial Radioisotope Production

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-11-19

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

  7. Production of radioisotopes using accelerators

    International Nuclear Information System (INIS)

    Qaim, S.M.

    1990-01-01

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

  8. Radioisotopes production and applications

    International Nuclear Information System (INIS)

    Dash, Ashutosh

    2015-01-01

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

  9. Radioisotope handling facilities and automation of radioisotope production

    International Nuclear Information System (INIS)

    2004-12-01

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

  10. Manual of radioisotope production

    International Nuclear Information System (INIS)

    1966-01-01

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

  11. 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?.

  12. Developments in radioisotope production and labelling of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Lambrecht, R.M.

    1998-01-01

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

  13. HAC and production of radioisotopes and labelled compounds

    International Nuclear Information System (INIS)

    Nozaki, T.

    1984-01-01

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

  14. Status and prospects on radioisotope production in Korea

    International Nuclear Information System (INIS)

    Han, H. S.; Cho, W. K.; Park, U. J.; Hong, Y. D.; Park, K. B.

    2002-01-01

    In Korea, radioisotopes has been produced using small-sized research reactors (TRIGA Mark II, III) from 1961 to 1995. The Korea Atomic Energy Research Institute (KAERI) completed the High-flux Advanced Neutron Application Reactor (HANARO) in 1995 and a radioisotope production facilities (RIPF) in 1997. Medical and industrial radionuclides such as 131 I, 99m Tc, 166 Ho, 192 Ir and 60 Co, are routinely produced utilizing HANARO. Several hundreds kilo curies of these nuclides were supplied to domestic users in 2001. The Korea Cancer Center Hospital (KCCH) first installed a cyclotron (MC-50) for neutron therapy and RI production in 1984. At present, the cyclotron routinely produced radionuclides such as 201 TI, 67 Ga, 123 I and 18 F. Also, it is capable of producing several radionuclides, including 111 In, 51 Cr, 124 I, 54 Mn, 22 Na, etc. Baby cyclotrons were installed in Seoul National University Hospital, Sam sung Medical Center and Asan Medical Center. The main purpose of the introduction of baby cyclotrons was to produce short-lived positron emitters such as 18 F, 15 O and 11 C for PET. Radioisotope production facilities were imported and installed as subsidiaries of cyclotron. In Korea, more than 60 kinds of radioisotopes are currently used in the field of their applications and most of them are imported form foreign vendors. For the quality assurance of final products such as radiopharmaceuticals and industrial sources, facilities for production should be installed and maintained in accordance with regulation rules and also the production system should be operated under quality management system. Since 1992 the Korean government has been encouraging Mid and Long Term Nuclear R and D Programs to enhance capability in nuclear technology development. In order to actively promote the utilization, research and development of technology applying radiation and RI, the Korean government established 'a comprehensive promotion plan for utilization, research and development

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

    International Nuclear Information System (INIS)

    Stang, L.G. Jr.

    1963-01-01

    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 Ag 110 , In 114 , 116 , Dy 155m , 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

  16. Radioisotope production by reactors and cyclotrons in Japan

    International Nuclear Information System (INIS)

    Murakami, Yukio

    1978-01-01

    Present status of radioisotope production in Japan and the increasing demand from various fields are generally reviewed. Future problems associated with the shortage of economical supply are also discussed. The first half of this report is devoted to general review of the increasing demand for various radioisotopes from increasing number of users. The present status and future trends of the distribution of users of specific radioisotopes and their demands are shown. The remaining half of this report reviews the production with reactors and cyclotrons. The Japanese reactors producing radioisotopes are limited to low flux (10 13 ) research reactors at JAERI. Some problems associated with the improvement of availability and with the organizational structure are discussed. As for the production with cyclotrons, available facilities and the method of production are explained in detail. For clinical use, especially for the production of short lived radioisotopes, the advantage of a small special purpose cyclotron at each medical organization is emphasized. (Aoki, K.)

  17. Technical and economical availability of radioisotopes production in Brazil

    International Nuclear Information System (INIS)

    Lima, J.O.V.

    1981-10-01

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

  18. Radioisotope production at PUSPATI - five year programme

    International Nuclear Information System (INIS)

    Yusof Azuddin Ali; Abdul Rahman Mohamad Ali.

    1983-01-01

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

  19. Radiation protection programme for a radioisotope production facility

    International Nuclear Information System (INIS)

    Makgato, Thutu Nelson

    2015-02-01

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

  20. The production and application of radioisotopes

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  1. Radioisotope production linac

    International Nuclear Information System (INIS)

    Stovall, J.E.; Hansborough, L.D.; O'Brien, H.A.

    1981-01-01

    A 70-MeV proton beam would open a new family of medical radioisotopes (including the important 123 I) to wide application. A 70-MeV, 500-μA linac is described, based on recent innovations in accelerator technology. It would be 27.3 m long, cost approx. $6 million, and the cost of power deposited in the radioisotope-production target is comparable to existing cyclotrons. By operating the rf-power system to its full capability, the same accelerator is capable of producing a 1140-μA beam, and the cost per beam watt on the target is less than half that of comparable cyclotrons. The technology to build such a linac is in a mature stage of developmnt, ready for use by industry

  2. 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.

  3. Studies on the production and application of radioisotopes

    International Nuclear Information System (INIS)

    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

  4. Radioisotope production in fusion reactors

    International Nuclear Information System (INIS)

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

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    Hata, Kentaro; Terunuma, Kusuo

    1994-02-01

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

  6. Comparison of the production of medical radioisotopes on reactor and cyclotron

    International Nuclear Information System (INIS)

    Vucina, J.; Vuksanovic, Lj.; Dobrijevic, R.; Karanfilov, E.

    1997-01-01

    The production of radioisotopes for nuclear-medical applications can be performed either on nuclear reactor or on cyclotron. According to the nuclear reactions applied the radioisotopes of different physical characteristics can be produced. In the paper a comparison of the radioisotopes production given. Compared are the main steps in the production: choice of the nuclear reaction, targetry, irradiation and radiochemical separations performed on the irradiated target to isolate the desired radioisotope. The main characteristics of the produced radioisotopes are given and discussed. (author)

  7. Economic Contributions of Radioisotope Production Reactor in Korea

    International Nuclear Information System (INIS)

    Nam, Ji Hee; Kim, Seung Su; Moon, Kee Whan

    2010-01-01

    Radioisotopes (RIs) have been used extensively in the fields of industrial, the agricultural, and the medical applications. Especially the deficiency of radioisotopes such as Mo-99 and I-131 in the medical applications recently is becoming the main issue in our society. Radioisotope with the characteristics of public goods in some aspects is mainly playing as the intermediate inputs or goods in the process of the industrial production, with being expected to produce the economic benefits by creating the new demand in the market or enlarging the value added for the related goods and services. In this study, the contribution effects for Korean economy by the construction and operation of the reactor for radioisotope production would be evaluated the effects produced by the activities such as a RI supplies into domestic industry, the RI exports, the neutron transmutation doping services called NTD, and the exports of RI production reactors

  8. Production of radioisotopes with BR2 facilities

    International Nuclear Information System (INIS)

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

    1978-01-01

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

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

    International Nuclear Information System (INIS)

    Park, J.H.; Han, H.S.; Park, K.B.

    2000-01-01

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

  10. Production and application of radioisotopes - a Canadian perspective

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  11. 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)

  12. Modern radioisotope production technologies for medicine

    International Nuclear Information System (INIS)

    Bechtold, V.; Schweickert, H.

    1989-01-01

    The advantages of the accelerator production of radioisotopes for medical purposes, are, above all, the high specific activity attainable as well as the possibility of the generation of nuclei with only a few neutrons which disintegrate due to β + emission or electron capture. It is, for example, possible to diagnostically utilize the developing long-range γ quanta by means of computerized tomography. The production of I-123 at the cyclotron of Karlsruhe (nuclear reaction, target, irradiation arrangement) as well as of ultra-pure I-123 with the help of compact cyclotrons, and the plant developed for this are described in brief. As another radioisotope which can be produced with the help of the compact cyclotron, Rb-81 is mentioned, the disintegration product Kr-81m of which is used in pulmonary diagnostics. (RB) [de

  13. Facilities for the production and processing of radioisotopes

    International Nuclear Information System (INIS)

    Fourie, P.J.

    1980-01-01

    Radioisotopes which are used in South Africa are produced in the nuclear reactor SAFARI 1 of the AEB and the CSIR cyclotron in Pretoria or are being imported from various overseas manufactures. The safe and efficient production and use of radioisotopes is possible when being handled by sufficiently trained personnel using special designed equipment and facilities. The Isotope Production Centre is situated next to the reactor and waste treatment buildings. New production facilities shielded with lead and equipped with remote handling equipment are being erected and will be commissioned early during 1980 [af

  14. 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

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

    International Nuclear Information System (INIS)

    Mushtaq, A.

    2013-01-01

    Radioisotope production to service different sectors of economic significance constitutes an important ongoing activity of many national nuclear programs. Radioisotopes, formed by nuclear reactions on targets in a reactor or cyclotron, require further processing in almost all cases to obtain them in a form suitable for use. The availability of short-lived radionuclides from radionuclide generators provides an inexpensive and convenient alternative to in-house radioisotope production facilities such as cyclotrons and reactors. The reactor offers large volume for irradiation, simultaneous irradiation of several samples, economy of production and possibility to produce a wide variety of radioisotopes. The accelerator-produced isotopes relatively constitute a smaller percentage of total use. (author)

  16. Development of radioisotope production in JAERI

    International Nuclear Information System (INIS)

    Yamabayashi, H.; Kato, H.; Umezawa, H.

    1992-01-01

    Since 1962, we have been developing methods and technology for producing a wide variety of processed radioisotopes and sealed radiation sources by using the JAERI's reactors, JRR-2, JRR-3, JRR-4 and JMTR, and providing the products to domestic users. At present, 29 nuclides and 31 products are on our list of processed radioisotopes. Some of those isotopes such as P-32, S-35, Cr-51 and short-lived nuclides are being produced regularly for distribution, but most of the rest are produced upon request. The radiation sources of Co-60 needles and Ir-192 pellets for industrial use and Gd-153 pellet, 7 kinds of Ir-192 and Au-198 grain for medical applications are produced and distributed routinely. (author)

  17. Improvement of radioisotope production technology

    International Nuclear Information System (INIS)

    Li Yongjian

    1987-01-01

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

  18. 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)

    2001-05-01

    charged particle beams (p, d, He, a), evaluation of the available data (both by fitting and theory); Compilation of production cross-section data on radioisotopes most commonly used in medicine, evaluation of the data; Development of calculational tools for predicting unknown data. Although the major emphasis in the CRP was on the energy region up to 30 MeV, higher energy data up to 60-80 MeV were also considered. It was realized that the evaluation methodology for charged particle data was not yet well developed and some teach-in effort was initially necessary. The CRP produced a much needed database and a handbook, covering reactions used for monitoring beam currents and for routine production of medically important radioisotopes. It is believed that the recommended cross-sections are accurate enough to meet the demands of all current applications, although further development of evaluation methodology and more experiments will be needed for exact determination of the errors and their correlations. In addition to the cross-sections, yields of the radioisotopes, calculated from the recommended data, are provided for the convenience of the user. A part of the results has been used in the Reference Neutron Activation Library, which was developed under another CRP. The database is available cost-free on the following Web page: http://www-nds.iaea.org/medical/

  19. Radioisotope production

    International Nuclear Information System (INIS)

    1988-01-01

    The trial production runs started in the previous report period were continued and have been extended to 67 Ga, 81 Rb/ 81m Kr and 111 In, the production of which will be taken over from the Pretoria cyclotron at the end of this year, when that machine is scheduled to be shut down. After commissioning of the target water cooling system and the helium cooling system for beam foil windows at the beginning of this year, these production runs could also be extended to high beam currents (up to 50 μA). Test consignments of a number of products have been supplied to various potential future users, and 123 I, in the form of Na 123 I capsules as well as 123 I-sodium hippurate, and 52 Fe-citrate have actually been used with success in trial diagnostic studies on patients. A procedure for labelling IPPA and 3-IPMPA with 123 I has been developed, while initial work has also been done on the radioiodination of monoclonal antifibrine antibodies. The last major facility needed for the commencement of the routine radioisotope production programme, namely the multiple-target facility, is now ready for installation in the production vault within the next few weeks, and routine production runs are expected to start in November 1988. 4 figs., 18 refs

  20. Radioisotope production in the I. Ph. P. E. cyclotron for medical application

    Energy Technology Data Exchange (ETDEWEB)

    Krasnov, N.N.; Dmitriyev, P.P.; Konjakhin, N.A.; Ognev, A.A. (Gosudarstvennyj Komitet po Ispol' zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst.)

    1982-01-01

    The production methods for seven radioisotopes, Ga-67, Sr-85, Pd-103, In-111, Tm-167, Hg-197 and Pb-203, by using a classical 1.5m cyclotron in the Institute of Physics and Power Engineering, Obninsk, USSR, are described. At present, more than 50 cyclotrons in different countries are used for the production of radioisotopes applied to medicine. Radioisotopes are produced with the cyclotron in the I.Ph.P.E. in the form of irradiated targets, which are delivered to Moscow radiopharmaceutical factory, where radiopharmaceuticals are produced on the base of these targets. The cyclotron is operated in two regimes providing the acceleration of protons, deuterons and alpha -particles. Two types of target assemblies are used for irradiation, the one is intended for the internal beam, and the other is for the external beam. The reactions used for the production of seven radioisotopes described above, the types of targets, particle energy, respective irradiated materials, beam current, thick target yield and the amount of respective radioisotopes produced per year are reported. Metals have large heat conductivity, therefore the use of metal targets increases beam current, and increases the production rate of radioisotopes.

  1. Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Duong Van Dong; Pham Ngoc Dien; Bui Van Cuong; Mai Phuoc Tho; Nguyen Thi Thu; Vo Thi Cam Hoa

    2014-01-01

    After reconstruction, the Dalat Nuclear Research Reactor (DNRR) was inaugurated on March 20th, 1984 with the nominal power of 500 kW. Since then the production of radioisotopes and labelled compounds for medical use was started. Up to now, DNRR is still the unique one in Vietnam. The reactor has been operated safely and effectively with the total of about 37,800 hrs (approximately 1,300 hours per year). More than 90% of its operation time and over 80% of its irradiation capacity have been exploited for research and production of radioisotopes. This paper gives an outline of the radioisotope production programme using the DNRR. The production laboratory and facilities including the nuclear reactor with its irradiation positions and characteristics, hot cells, production lines and equipment for the production of Kits for labelling with 99m Tc and for quality control, as well as the production rate are mentioned. The methods used for production of 131 I, 99m Tc, 51 Cr, 32 P, etc. and the procedures for preparation of radiopharmaceuticals are described briefly. Status of utilization of domestic radioisotopes and radiopharmaceuticals in Vietnam is also reported. (author)

  2. 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.

  3. Production of radioisotopes within a plasma focus device

    International Nuclear Information System (INIS)

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

    2005-01-01

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

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

    International Nuclear Information System (INIS)

    Terentyev, G.O.

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    1991-01-01

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

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

    International Nuclear Information System (INIS)

    Soenarjo, Sunarhadijoso; Tamat, Swasono R.

    2000-01-01

    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)

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

    International Nuclear Information System (INIS)

    Liu Yishu

    2000-01-01

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

  8. 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)

  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. Abstracts of the second conference on radioisotopes and their applications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

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

  11. Present status of radioisotope production in JAERI

    International Nuclear Information System (INIS)

    Yamabayashi, Hisamichi

    1994-01-01

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

  12. Production and application of radioisotopes in Asian Countries

    International Nuclear Information System (INIS)

    He Youfeng

    1997-01-01

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

  13. Radioisotopes production for applications on the health

    International Nuclear Information System (INIS)

    Monroy G, F.; Alanis M, J.

    2010-01-01

    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: 99 Mo/ 99m Tc and 188 W/ 188 Re generators, the radio lanthanides: 151 Pm, 147 Pm, 161 Tb, 166 Ho, 177 Lu, 131 I and the 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 99 Mo/ 99m Tc and 188 W/ 188 Re presented in this work, because they are systems that allow to produce an artificial radioisotope of interest continually, in these cases the 99m Tc and the 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)

  14. Decontamination of radioisotope production facility

    International Nuclear Information System (INIS)

    Daryoko, M.; Yatim, S.; Suseno, H.; Wiratmo, M.

    1998-01-01

    The strippable coating method use phosphoric glycerol and irradiated latex as supporting agents have been investigated. The investigation used some decontaminating agents: EDTA, citric acid, oxalic acid and potassium permanganate were combined with phosphoric glycerol supporting agent, then EDTA Na 2 , sodium citric, sodium oxalic and potassium permanganate were combined with irradiated latex supporting agent. The study was needed to obtain the representative operating data, will be implemented to decontamination the Hot Cell for radioisotope production. The experiment used 50x50x1 mm stainless steel samples and contaminated by Cs-137 about 1.1x10 -3 μCi/cm 2 . This samples according to inner cover of Hot Cell material, and Hot Cell activities. The decontamination factor results of the investigation were: phosphoric glycerol as supporting agent, about 20 (EDTA as decontaminating agent) to 47 (oxalic acid as decontaminating agent), and irradiated latex as supporting agent, about 11.5 (without decontamination agent) to 27 (KMnO 4 as decontaminating agent). All composition of the investigation have been obtained the good results, and can be implemented for decontamination of Hot Cell for radioisotope production. The irradiated latex could be recommended as supporting agent without decontaminating agent, because it is very easy to operate and very cheap cost. (author)

  15. Medical radioisotope production - the Australian experience

    Energy Technology Data Exchange (ETDEWEB)

    Druce, M. [Australian Nuclear Science and Technology Organisation, Menai (Australia)

    1996-12-31

    The Australian government, through its instrumentality, the Australian Nuclear Science and Technology Organization (ANSTO), owns and operates a 10-MW Dido-class research reactor at Lucas Heights on the southern outskirts of Sydney. This is the only operating nuclear reactor in Australia. It was built in 1958 and has a maximum flux of 1 x 10{sup 14} n/cm{sup 2}{center_dot}s. ANSTO also jointly owns and operates a 30-MeV IBA negative ion cyclotron at Camperdown in central Sydney, which began operation in 1992. ANSTO is predominantly a research organization; however, radioisotopes are commercially produced through Australian Radioisotopes (ARI), an ANSTO business entity. Seventy-four people are employed by ARI, which is a vertically integrated organization, i.e., everything from target preparation to sale of products is undertaken.

  16. Production capabilities in US nuclear reactors for medical radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-11-01

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

  17. Production capabilities in US nuclear reactors for medical radioisotopes

    International Nuclear Information System (INIS)

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

    1992-11-01

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

  18. Solid targets for production of radioisotopes with cyclotron

    International Nuclear Information System (INIS)

    Paredes G, L.; Balcazar G, M.

    1999-01-01

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

  19. Reactor production and processing of radioisotopes for therapeutic applications in nuclear medicine

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Mirzadeh, S.; Beets, A.L.

    1995-01-01

    Nuclear reactors continue to play an important role in providing radioisotopes for nuclear medicine. Many reactor-produced radioisotopes are ''neutron rich'' and decay by beta-emission and are thus of interest for therapeutic applications. This talk discusses the production and processing of a variety of reactor-produced radioisotopes of current interest, including those produced by the single neutron capture process, double neutron capture and those available from beta-decay of reactorproduced radioisotopes. Generators prepared from reactorproduced radioisotopes are of particular interest since repeated elution inexpensively provides many patient doses. The development of the alumina-based W-188/Re-188 generator system is discussed in detail

  20. Administration of radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-01-15

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

  1. Administration of radioisotope production

    International Nuclear Information System (INIS)

    1964-01-01

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

  2. Radioisotope production in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Wan Awang, Wan Anuar [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)

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

    International Nuclear Information System (INIS)

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

    2010-04-01

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

  4. Indigenous development of TBq levels of "1"7"7Lu radioisotope production at RPhD for nuclear medicine applications - a successful venture

    International Nuclear Information System (INIS)

    Chakraborty, Sudipta; Vimalnath, K.V.; Dash, Ashutosh

    2017-01-01

    Lutetium-177 ("1"7"7Lu) has emerged as a potential radionuclide during last decade for the development of radionuclide therapy owing to its favorable nuclear decay characteristics (T_1_/_2=6.65 d, E_β_(_m_a_x) = 0.497 MeV, E_γ = 113 keV (6.4%) and 208 keV (11%)). The long half-life of this promising radioisotope offering distinct logistical advantage and feasibility of its large-scale production in medium flux Dhruva research reactor contributed to its success story

  5. Recent progress in radioisotope production in Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    So, Le Van [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)

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

    International Nuclear Information System (INIS)

    Fisher, Charlie

    1974-01-01

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

  7. Twenty years of radioisotope production from Institute of Atomic Energy reactors

    International Nuclear Information System (INIS)

    Lun, Xiao

    1980-01-01

    The heavy water reactor in People's Republic of China went critical in November, 1958, and the radioisotope development work began since then. The thermal power of the reactor was 7 MW, and the maximum thermal neutron flux was 1.2 x 10 14 n/cm 2 /sec. Since 1967, it was operated at 10 MW. The first radioisotope product was 24 Na, using Na 2 CO 3 as a target, while the first chemically processed product was an electroplated reference source of 60 Co. The first processed radiochemical was the carrier-free H 2 SO 4 of 35 S. Since then, 131 I and 32 P for medical uses, colloidal 198 Au, colloidal Cr 32 PO 4 , chemicals containing 203 Hg, organic compounds labelled with 125 I, 131 I, 3 H and 14 C and smoke detectors have been produced to date. In addition, 22 Na, 54 Mn, 57 Co, 88 Y, 109 Cd have been prepared from a cyclotron. Now about 140 kinds of products can be supplied, and 60% of the users are the hospitals with nuclear medicine department. The present status of the kinds and production figures of nuclear medicines, radiopharmaceuticals, labelled compounds, radiation sources, and some works in progress are reported. General aspects of the application of radioisotopes in China are also described. Radioisotopes have been applied to agriculture, industry, medicine, and sciences such as physics, chemistry, biology and geography. (Wakatsuki, Y.)

  8. Reactor-produced therapeutic radioisotopes

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

    1982-01-01

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

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  12. A radioisotope production cyclotron designed to minimize dose

    International Nuclear Information System (INIS)

    Szlavik, F.F.; Moritz, L.E.

    1992-01-01

    This paper describes a radioisotope production cyclotron which has been designed to minimize the dose to personnel during operation and maintenance. The design incorporates lessons learned from the operation of a CP42 cyclotron and has resulted in a reduction of the dose by a factor of more than 10. (author)

  13. Manual for reactor produced radioisotopes

    International Nuclear Information System (INIS)

    2003-01-01

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

  14. Production, control and utilization of radioisotopes including radiopharmaceuticals

    International Nuclear Information System (INIS)

    Muenze, R.

    1985-05-01

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

  15. Production of radioisotopes for medical use

    International Nuclear Information System (INIS)

    Ido, Tatsuo

    1977-01-01

    As problems in the process of production of short-lived radioisotopes for medical use and in clinical application of them, the following three items were mentioned: 1. separation and purification in a short time, 2. devices to decrease exposure dose in workers, and 3. preservation of radiochemical purity and chemical purity, and avoidance of mixture of impurities. In consideration of these problems, an outline of on-line production system of radioactive gases (from irradiation by accelerated particles to separation, purification, and administration of them), which was exploited in National Institute of Radiological Sciences, was described. Production of 13 NH 3 , the aqueous solution of 18 F, and 123 I was also given an outline. Simultaneous production method of many nuclides by means of laminated target and compounds labelled with positron emitter were also described. (Tsunoda, M.)

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

    International Nuclear Information System (INIS)

    Kim, Minjin; Jung, H.S.

    2012-01-01

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

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

    International Nuclear Information System (INIS)

    Walt, T.N. van der

    1998-01-01

    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 18 F-FDG, 67 Ga-citrate, a 67 Ga-labelled resin. 111 In-chloride, 111 In-oxine and 111 In-labelled resin. 123 I-sodium iodide and 123 I-labelled compounds, 201 Tl-chloride, as well as the 81 Rb/ 81m Kr 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 22 Na, 55 Fe and 139 Ce, 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)

  18. Radioisotope tracer study in an aniline production reactor

    International Nuclear Information System (INIS)

    Pant, H.J.; Yelgoankar, V.N.; Mendhekar, G.N.

    1995-01-01

    A radioisotope tracer study was carried out in an aniline production reactor to investigate the cause of poor heat transfer from tube side to shell side in an aniline production (ANPO) reactor. The results of the study indicated that more than 50% of the shell volume was reduced due to deposition of the process material (i.e. fouling) on the shell walls and may be the cause of poor heat transfer in the reactor. (author). 2 refs., 2 figs

  19. Radio-isotope production using laser Wakefield accelerators

    International Nuclear Information System (INIS)

    Leemans, W.P.; Rodgers, D.; Catravas, P.E.; Geddes, C.G.R.; Fubiani, G.; Toth, C.; Esarey, E.; Shadwick, B.A.; Donahue, R.; Smith, A.; Reitsma, A.

    2001-01-01

    A 10 Hz, 10 TW solid state laser system has been used to produce electron beams suitable for radio-isotope production. The laser beam was focused using a 30 cm focal length f/6 off-axis parabola on a gas plume produced by a high pressure pulsed gas jet. Electrons were trapped and accelerated by high gradient wakefields excited in the ionized gas through the self-modulated laser wakefield instability. The electron beam was measured to contain excesses of 5 nC/bunch. A composite Pb/Cu target was used to convert the electron beam into gamma rays which subsequently produced radio-isotopes through (gamma, n) reactions. Isotope identification through gamma-ray spectroscopy and half-life time measurements demonstrated that Cu 61 was produced which indicates that 20-25 MeV gamma rays were produced, and hence electrons with energies greater than 25-30 MeV. The production of high energy electrons was independently confirmed using a bending magnet spectrometer. The measured spectra had an exponential distribution with a 3 MeV width. The amount of activation was on the order of 2.5 uCi after 3 hours of operation at 1 Hz. Future experiments will aim at increasing this yield by post-accelerating the electron beam using a channel guided laser wakefield accelerator

  20. Spallation production of neutron deficient radioisotopes in North America

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  1. Radioisotope production and distribution in Australia

    International Nuclear Information System (INIS)

    Brough, J.

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    Corahua, A.

    1996-01-01

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

  3. Research reactor production of radioisotopes for medical use

    International Nuclear Information System (INIS)

    Mani, R.S.

    1985-01-01

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

  4. 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)

  5. Study on application of radiation and radioisotopes -Development of the radioisotope production facilities for the HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ji Bok; Woo, Jong Sub; Kang, Byung Woi; Baek, Sam Tae; Jeong, Un Soo; Park, Yong Chul; Jeon, Young Keon; Chang, Chun Ik; Lee, Bong Jae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-08-01

    Development and construction of the lead hot cell for radioisotope production and related facility. 1. Fabrication and installation of the lead H/C system. 2. Development and installation of the hydraulic transfer system. 3. Development of the radiation monitoring system. 4. Fabrication and installation of the fire extinguishing system in the H/C. 5. Fabrication and installation of the fume hood. 4 tabs.,10 figs. (Author).

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    Fox, C.J.

    1996-01-01

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

  8. Activity calculation of radioisotopes in HFETR

    International Nuclear Information System (INIS)

    Liu Shuiqing

    1996-12-01

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

  9. Radioisotopes In Animal Production Research

    International Nuclear Information System (INIS)

    Eduvie, L.O.

    1994-05-01

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

  10. Nuclear Medicine at Berkeley Lab: From Pioneering Beginnings to Today (LBNL Summer Lecture Series)

    International Nuclear Information System (INIS)

    Budinger, Thomas

    2006-01-01

    Summer Lecture Series 2006: Thomas Budinger, head of Berkeley Lab's Center for Functional Imaging, discusses Berkeley Lab's rich history pioneering the field of nuclear medicine, from radioisotopes to medical imaging.

  11. Theory of Radioisotope Scanning; Theorie de l'Exploration au Moyen d'un Radioisotope; Matematicheskaya osnova radioizotopnogo skennirovaniya; Teoria de la Exploracion Radioisotopica

    Energy Technology Data Exchange (ETDEWEB)

    Brownell, G. L. [Massachusetts General Hospital, Boston, MA (United States)

    1964-10-15

    All scanning techniques, whether utilizing focusing collimators, positron detectors or the newer camera techniques, have certain basic problems. The success of these techniques depends in large measure upon the correct choice of various parameters of the collimating system, of which the most important is the resolution. In this paper the relationship of optimum resolution to radioisotope content and distribution are discussed. Radioisotope scanning may be considered as a process of information extraction and presentation. The primary information lies in the original radioisotope distribution. The collimator and detecting system provide the information transfer mechanism and the final scan presents the resultant information. As with all such techniques, only a small fraction of the information is retained in the final scan. It can be shown that for focusing collimator and scintillation camera systems, the number of counts per resolution area varies as the fourth power of the resolution distance. For certain radioisotope distributions it is possible to derive analytically an optimum value of resolution distance. However, for most systems the optimum resolution must be determined by trial and error. The problems here are similar to those of pattern recognition in other fields. A computer programme has been prepared to aid in determining the optimum resolution for various types of patterns. This computer is unique in having intermediate disc storage and CRT read-out. The results have general applicability to the design of many scanning systems. (author) [French] Toutes les methodes d'exploration au moyen d'un radioisotope, celles qui font appel aux collimateurs a focalisation, aux detecteurs de positons ou les techniques plus recentes utilisant des cameras a scintillation, posent certains problemes fondamentaux. Le succes de ces techniques depend beaucoup du choix des differents parametres du dispositif de collimation, dont le plus important est la resolution. L

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

    CERN Document Server

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

    2017-01-01

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

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

    International Nuclear Information System (INIS)

    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

  14. Occupational radioprotection in the cyclotron laboratory radioisotope production at IEN

    International Nuclear Information System (INIS)

    Fajardo, P.W.; Teixeira, M.V.; Santos, I.H.T.; Pujol Filho, S.V.

    1990-07-01

    The Cyclotron of the Instituto de Engenharia Nuclear is operated mainly for radioisotope production, neutron production studies and irradiation damage analysis. The risks associated to the activities developed in these laboratories are exposition to beta, neutron and gama radiation and contamination. The radioprotection program adapted are presented briefly and the results of the air and surface contamination analysis, liquid efluents and dose equivalent of the workers in 1988 are shown. (author) [pt

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

    International Nuclear Information System (INIS)

    Muenze, R.

    1988-01-01

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

  16. Radioisotope applications in industry and environment: Indian scenario

    International Nuclear Information System (INIS)

    Pant, H.J.

    2016-01-01

    Applications of radioisotopes and radiation technology in industry, medicine and agriculture form an important part of India's programme of using nuclear technology for societal benefits. Radioisotope production in India started on a modest scale soon after 1 MW APSARA reactor at Trombay, Mumbai became critical in 1956. The scope of activities expanded thereafter. With the commissioning of 40 MW CIRUS reactor in 1960, the setting up of modern radioisotope processing laboratories in late sixties and the production of cobalt-60 in power reactors in megacurie quantities in late seventies made India self-sufficient in radioisotope production. The radioisotope production received a major boost in 1985 with the commissioning of high flux 100 MW DHRUVA reactor, which provided opportunity to extend the range of radioisotopes available in the country both in quantity as well in specific activity. The CIRUS reactor has been shutdown in year 2010 and 1 MW APSARA reactor is presently being upgraded to 5 MW. Today, The DHRUVA reactor operating at its full capacity is being used for production of 100 different radioisotopes those are used in industry, agriculture and medicine. (author)

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

    International Nuclear Information System (INIS)

    Richards, M.P.

    1983-08-01

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

  18. Novel production techniques of radioisotopes using electron accelerators

    Science.gov (United States)

    Lowe, Daniel Robert

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

  19. The MAPLE-X concept dedicated to the production of radio-isotopes

    International Nuclear Information System (INIS)

    Heeds, W.

    1985-06-01

    MAPLE is a versatile new Canadian multi-purpose research reactor concept that meets the nuclear aspirations of developing countries. It is planned to convert the NRX reactor at Chalk River Nuclear Laboratories into MAPLE-X as a demonstration prototype of this concept and thereafter to dedicate its operation to the production of radio-isotopes. A description of MAPLE-X and details of molybdenum-99 production are given

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  1. First commissioning results with the Grenoble test electron cyclotron resonance ion source at iThemba LABS

    Energy Technology Data Exchange (ETDEWEB)

    Thomae, R.; Conradie, J.; Delsink, H.; Du Plessis, H.; Fourie, D.; Klopp, M.; Kohler, I.; Lussi, C.; McAlister, R.; Ntshangase, S.; Sakildien, M. [iThemba LABS, P.O Box 722, Somerset West 7130 (South Africa); Hitz, D. [CEA/DRFMC, 17 Av. Des Martyrs, 38054, Grenoble Cedex 9 (France); Kuechler, D. [CERN, BE/ABP/HSL, 1211 Geneva 23 (Switzerland)

    2012-02-15

    iThemba Laboratory for Accelerator Based Science (iThemba LABS) is a multi-disciplinary accelerator facility. One of its main activities is the operation of a separated-sector cyclotron with a K-value of 200, which provides beams of various ion species. These beams are used for fundamental nuclear physics research in the intermediate energy region, radioisotope production, and medical physics applications. Due to the requirements of nuclear physics for new ion species and higher energies, the decision was made to install a copy of the so-called Grenoble test source (GTS) at iThemba LABS. In this paper, we will report on the experimental setup and the first results obtained with the GTS2 at iThemba LABS.

  2. First commissioning results with the Grenoble test electron cyclotron resonance ion source at iThemba LABS

    International Nuclear Information System (INIS)

    Thomae, R.; Conradie, J.; Delsink, H.; Du Plessis, H.; Fourie, D.; Klopp, M.; Kohler, I.; Lussi, C.; McAlister, R.; Ntshangase, S.; Sakildien, M.; Hitz, D.; Kuechler, D.

    2012-01-01

    iThemba Laboratory for Accelerator Based Science (iThemba LABS) is a multi-disciplinary accelerator facility. One of its main activities is the operation of a separated-sector cyclotron with a K-value of 200, which provides beams of various ion species. These beams are used for fundamental nuclear physics research in the intermediate energy region, radioisotope production, and medical physics applications. Due to the requirements of nuclear physics for new ion species and higher energies, the decision was made to install a copy of the so-called Grenoble test source (GTS) at iThemba LABS. In this paper, we will report on the experimental setup and the first results obtained with the GTS2 at iThemba LABS.

  3. Spallation production of neutron deficient radioisotopes in North America

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  4. Linear accelerator for radioisotope production

    International Nuclear Information System (INIS)

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

    1982-02-01

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

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    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

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    1982-09-01

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

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    1981-08-01

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

  8. 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.

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

    International Nuclear Information System (INIS)

    Mohamad Awang; Zulkifli Mohamad Hashim; Yusof Azuddin Ali

    1986-01-01

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

  10. A prototype on-line work procedure system for radioisotope thermoelectric generator production

    International Nuclear Information System (INIS)

    Kiebel, G.R.

    1991-09-01

    An on-line system to manage work procedures is being developed to support radioisotope thermoelectric generator (RTG) assembly and testing in a new production facility. This system implements production work procedures as interactive electronic documents executed at the work site with no intermediate printed form. It provides good control of the creation and application of work procedures and provides active assistance to the worker in performing them and in documenting the results. An extensive prototype of this system is being evaluated to ensure that it will have all the necessary features and that it will fit the user's needs and expectations. This effort has involved the Radioisotope Power Systems Facility (RPSF) operations organization and technology transfer between Westinghouse Hanford Company (Westinghouse Hanford) and EG ampersand G Mound Applied Technologies Inc. (Mound) at the US Department of Energy (DOE) Mound Site. 1 ref

  11. Revisiting homogeneous suspension reactors for production of radioisotopes

    International Nuclear Information System (INIS)

    Pasqualini, E.E.

    2010-01-01

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

  12. Economic Feasibility Study for the Utilization of Egyptian Reactor (ETRR-2) in Radioisotope Production

    International Nuclear Information System (INIS)

    El-Kolaly, M; El-Gameel, E.A.

    2011-01-01

    The present study was carried out to discus the economic feasibility study of local radioisotope production in Egyptian Atomic Energy Authority. This study was divided into three sections; the first section included the marketing study which based on the expectation of the local demand and surplus production to export from 99 Mo production. The second section discussed the financial analysis and provided a model for calculating the cost per operation hour and per curie from production. The financial analysis discussed the profitable analysis and project sensitivity to change in cost and revenue. The third section discussed the effect of this project on the national return as the national income, employment, social rate of return and trade balance. This study was carried out according to the method adopted by the International Bank for Development taking into consideration the impact of applying radioisotope production technology on the society.

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

    International Nuclear Information System (INIS)

    Ounalli, Leila

    2013-01-01

    radioisotopes production are much sought worldwide. There is a universal lack of these specialists. Regarding this situation, there is an urgency to collect the right conditions which allow the organization of a Master's degree in radio-pharmacy, radio-biology and radiochemistry. The projects of complementarities between Arab countries via the Arabic Agency of the Atomic Energy, the collaboration with the International Atomic Energy Agency and the Technical French Cooperation of the Atomic Energy Commission are useful to combine efforts for better training of the staff. (Author)

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

    International Nuclear Information System (INIS)

    Lemos Junior, O.F.

    1992-05-01

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

  15. Application of radioisotopes in pharmaceutical research

    International Nuclear Information System (INIS)

    Khujaev, S.

    2004-01-01

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

  16. Radioisotope research and development at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Peterson, E.J.

    1993-01-01

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

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  18. 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)

  19. Radioisotope conveyor ash meter

    International Nuclear Information System (INIS)

    Savelov, V.D.

    1994-01-01

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

  20. An INVAP perspective on the production of medical radioisotopes: past and present

    International Nuclear Information System (INIS)

    Salvatore, M.

    2009-01-01

    This presentation gives a perspective on medical radionuclide production methods from INVAP, Argentina. INVAP is a company headquartered in Argentina and is involved amongst other activities in nuclear, medical and scientific equipment. It describes INVAP's involvement in research reactor projects in a number of countries around the world. The paper describes a number of turn-key facilities for the production of radioisotopes for medicine, industry and research activities.

  1. Aspects of occupational radioprotection in laboratories for radioisotopes production

    International Nuclear Information System (INIS)

    Fajardo, Patricia Wieland; Santos, Ilka Helena Taam.

    1990-10-01

    Some aspects of the radiation protection program implemented in the radioisotope production laboratories at the Nuclear Engineering Institute (IEN), are presented. This program evolves external and internal monitoring, radiation level measurements, and surface and air contamination monitoring. Comparing the results obtained in 1987, 1988 and 1989 with the corresponding limits established by Brazilian National Nuclear Energy Commission, it can be seen that the radiation protection program is suitable for those places with high risks of radiation contamination. (author). 2 refs., 2 figs., 2 tabs

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

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  3. Material science as basis for nuclear medicine: Holmium irradiation for radioisotopes production

    Science.gov (United States)

    Usman, Ahmed Rufai; Khandaker, Mayeen Uddin; Haba, Hiromitsu; Otuka, Naohiko

    2018-05-01

    Material Science, being an interdisciplinary field, plays important roles in nuclear science. These applications are seen in weaponry, armoured vehicles, accelerator structure and development, semiconductor detectors, nuclear medicine and many more. Present study presents the applications of some metals in nuclear medicine (radioisotope production). The charged-particle-induced nuclear reactions by using cyclotrons or accelerators have become a very vital feature of the modern nuclear medicine. Realising the importance of excitation functions for the efficient production of medical radionuclides, some very high purity holmium metals are generally prepared or purchased for bombardment in nuclear accelerators. In the present work, various methods to obtain pure holmium for radioisotope production have been discussed while also presenting details of our present studies. From the experimental work of the present studies, some very high purity holmium foils have been used in the work for a comprehensive study of residual radionuclides production cross-sections. The study was performed using a stacked-foil activation technique combined with γ-ray spectrometry. The stack was bombarded with 50.4 MeV alpha particle beam from AVF cyclotron of RI Beam Factory, Nishina Centre for Accelerator-Based Science, RIKEN, Japan. The work produced thulium radionuclides useful in nuclear medicine.

  4. 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.

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  6. Radioisotopes and radiopharmaceuticals catalogue

    International Nuclear Information System (INIS)

    2002-01-01

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

  7. Investigation of the radionuclide inventory and the production yields of the target stacks at the PEFP radioisotope production facility

    International Nuclear Information System (INIS)

    Yoon, Sang-Pil; Hong, In-Seok; Cho, Yong-Sub

    2010-01-01

    The Proton Engineering Frontier Project (PEFP) will construct a radioisotope production facility by using the nuclear reaction between the 100-MeV proton beam and the solid target. For investigating the radionuclide inventory and the production yield of the radioisotope production facility, we have optimized the thickness of the prototype target stacks by using a SRIM calculation. The target stacks consist of RbCl encapsulated in inconel alloy, Zn metal, and Ga metal encapsulated in niobium. Typical beam parameters were 300 μA and 95 hours. An inventory of all generated radionuclide activities is mandatory in order to prepare the operation scenario and design the hot cell. The Monte Carlo code MCNPX was used to investigate what radionuclide is generated. The obtained radionuclide inventory indicated that about 100 radionuclides were generated and that the total radioactivity of the irradiated target stacks was 1324.1 Ci at the end of the bombardment. The production yields of Sr-82, Cu-67, and Ge-68 were 3.79 Ci, 2.74 Ci, and 1.23 Ci at the end of the bombardment.

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

    International Nuclear Information System (INIS)

    Simmons, J.L.

    1977-03-01

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

  9. Modernization of the Radioisotopes Production Laboratory of the La Reina Nuclear Center in Chile: Incorporating advanced concepts of safety and good manufacturing practices

    International Nuclear Information System (INIS)

    Lagos Espinoza, Silvia

    2014-01-01

    A radioisotopes and radiopharmaceuticals production laboratory was established in Chile in the 1960s for research activities. From 1967 until January 2012, it was dedicated to the manufacturing of radioisotopes and radiopharmaceuticals for medical diagnosis and treatment purposes. In 2012, modernization of the facility’s design and technology began as part of the IAEA technical cooperation project, Modernizing the Radioisotopes Production Laboratory of La Reina Nuclear Centre by Incorporating Advanced Concepts of Safety and Good Manufacturing Practices, (CHI4022)

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  11. Impact of chemistry on production and utilization of radioisotopes and related products

    International Nuclear Information System (INIS)

    Ramamoorthy, N.

    2011-01-01

    The year 2011, declared as the International Year of Chemistry (IYC), commemorates the centenary of the award of Nobel Prize in Chemistry to Madam Curie for her pioneering work on the discovery of Radium and Polonium. Her invaluable discovery and her other research pursuits, as well as other subsequent discoveries in nuclear sciences, including by her daughter and son-in-law - Irene Curie and Frederic Joliot - who in 1935 discovered the phenomenon of artificially induced radioactivity (that later bagged the Nobel Prize), led to several noteworthy applications. The author, as a member of 'Indian radioisotope family' and the DAE programmes on radioisotopes and related radiation technology since August 1972, narrates in this article a series of select chemistry-related milestones that enabled vital developments in the production of isotope products and their applications. Ingenious and often simple chemistry-based solutions instituted by the researchers stand out in the enormous progress achieved over the years and highly significant practical applications rendered a reality. Appropriate examples can be cited from both the Indian scenario and international developments over the past nearly four decades. The long list will include inter alia the following: change of eluent from dilute nitric acid to normal saline to obtain medical-grade pertechnetate from molybdate adsorbed an acidic alumina (ushering in 99m Tc generators for (radio)pharmacy use); premixing a reducing agent like stannous chloride with ligand and freeze-drying the mixture - 'lyophilised kit' - (providing an easy access to 99m Tc radiopharmaceuticals); introduction of an iodine atom in place of an aryl hydrogen as a non-isotopic label in organic compound of interest (birth of radioiodinated compounds for biomedical use); bifunctional chelates designed to link radiometals with biological or pharmaceutical compound (radiolabeled biological analogues for medical use); nucleophilic substitution by fluoride

  12. Design of radioisotope power systems facility

    International Nuclear Information System (INIS)

    Eschenbaum, R.C.; Wiemers, M.J.

    1991-01-01

    Radioisotope power systems currently produced for the U.S. Department of Energy Office of Special Applications by the Mound Laboratory at Miamisburg, Ohio, have been used in a variety of configurations by the Department of Defense and the National Aeronautics and Space Administration. A forecast of fugure radioisotope power systems requirements showed a need for an increased production rate beyond the capability of the existing Mound Laboratory. Westinghouse Hanford Company is modifying the Fuels and Materials Examination Facility on the Hanford Site near Richland, Washington, to install the new Radioisotope Power Systems Facility for assembling future radioisotope power systems. The facility is currently being prepared to assemble the radioisotope thermoelectric generators required by the National Aeronautics and Space Administration missions for Comet Rendezvous Asteroid Flyby in 1995 and Cassini, an investigation of Saturn and its moons, in 1996

  13. Radioisotope Power Sources; Sources d'energie utilisant les radiobotopes; Radioizotopnye istochniki ehnergii; Fuentes radio isotopicas de energia

    Energy Technology Data Exchange (ETDEWEB)

    Culwell, J. P. [USAEC, Washington, D.C (United States)

    1963-11-15

    hazards. (author) [French] Le programme de production d'energie au moyen des radioisotopes, execute par la Commission de l'energie atomique des Etats-Unis, a donne naissance a toute une technologie nouvelle de l'emploi des radioisotopes comme source d'energie dans des generateurs. Les sources d'energie utilisant des radioisotopes conviennent particulierement pour les applications a distance, qui exigent des alimentations de longue duree, de faibles dimensions et de fonctionnement sur. Ces ''batteries nucleaires'', qui peuvent fonctionner de maniere satisfaisante dans des conditions extremes de temperature et d'exposition aux rayons solaires et aux rayonnements electromagnetiques, constituent des sources d'energie interessantes pour differents types d'engins telecommandes tels que ceux qui sont destines a recueillir des renseignements ou a assurer une surveillance ainsi que les satellites et autres vehicules spatiaux. Les radioisotopes utilises comme sources d'energie sont generalement des emetteuis alpha ou beta. Les emetteurs alpha sont preferables, mais ils sont plus couteux et plus rares et on les reserve generalement pour les applications spatiales. A l'heure actuelle les emetteurs beta, obtenus par separation des dechets de la fission nucleaire, sont utilises exclusivement dans les engins terrestres et marins. On peut neanmoins prevoir que des emetteurs beta, comme le strontium-90, seront eventuellement utilises dans l'espace. On fait actuellement des recherches sur des generateurs qui utiliseront comme sources des melanges de produits de fission. Ces sources seront d'un prix de revient moins eleve qile les radioisotopes purs car les couts de la separation et de la purification seront supprimes. Des prototypes de generateurs thermoelectriques, utilisant le strontium-90 et le cesium-137 comme sources, fonctionnent actuellement ou sont mis au point dans des stations meteorologiques, des engins de balisage et des appareils pour la survellance des profondeurs marines. Le

  14. Fed-batch CHO cell culture for lab-scale antibody production

    DEFF Research Database (Denmark)

    Fan, Yuzhou; Ley, Daniel; Andersen, Mikael Rørdam

    2017-01-01

    Fed-batch culture is the most commonly used upstream process in industry today for recombinant monoclonal antibody production using Chinese hamster ovary cells. Developing and optimizing this process in the lab is crucial for establishing process knowledge, which enable rapid and predictable tech......-transfer to manufacturing scale. In this chapter, we will describe stepwise how to carry out fed-batch CHO cell culture for lab-scale antibody production....

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

    International Nuclear Information System (INIS)

    2008-09-01

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

  16. Simulation and sensitivity analysis for heavy linear paraffins production in LAB production Plant

    Directory of Open Access Journals (Sweden)

    Karimi Hajir

    2014-12-01

    Full Text Available Linear alkyl benzene (LAB is vastly utilized for the production of biodegradable detergents and emulsifiers. Predistillation unit is a part of LAB production plant in which that produced heavy linear paraffins (nC10-nC13. In this study, a mathematical model has been developed for heavy linear paraffins production in distillation columns, which has been solved using a commercial code. The models have been validated by the actual data. The effects of process parameters such as reflux rate, and reflux temperature using Gradient Search technique has been investigated. The sensitivity analysis shows that optimum reflux in columns are achieved.

  17. Radioisotopes for therapy: an overview

    International Nuclear Information System (INIS)

    Venkatesh, Meera

    2006-01-01

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

  18. Advanced HVAC modeling with FemLab/Simulink/MatLab

    NARCIS (Netherlands)

    Schijndel, van A.W.M.

    2003-01-01

    The combined MatLab toolboxes FemLab and Simulink are evaluated as solvers for HVAC problems based on partial differential equations (PDEs). The FemLab software is designed to simulate systems of coupled PDEs, 1-D, 2-D or 3-D, nonlinear and time dependent. In order to show how the program works, a

  19. 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

  20. VPPD Lab - The Chemical Product Simulator

    DEFF Research Database (Denmark)

    Kalakul, Sawitree; Hussain, Rehan; Elbashir, Nimir

    2015-01-01

    , detergent, etc.). It has interface to identify workflow/data-flow for the inter-related activities between knowledge-based system and model-based calculation procedures to systematically, efficiently and robustly solve various types of product design-analysis problems. The application of the software......In this paper, the development of a systematic model-based framework for product design, implemented in the new product design software called VPPD-Lab is presented. This framework employs its in-house knowledge-based system to design and evaluate chemical products. The built-in libraries...... of product performance models and product-chemical property models are used to evaluate different classes of product. The product classes are single molecular structure chemicals (lipids, solvents, aroma, etc.), blended products (gasoline, jet-fuels, lubricants, etc.), and emulsified product (hand wash...

  1. Evaluation of Radioisotope Production Process of 153Sm and 153Sm-EDTMP Radiopharmaceuticals

    International Nuclear Information System (INIS)

    Kadarisman; Sri Hastini; Yayan Tahyan; Abidin; Dadang Hafid; Enny Lestari

    2007-01-01

    Experiments on the process of 153 Sm radioisotope and labeling of 153 Sm-EDTMP radiopharmaceuticals were carried out. This experiments included preparation of Sm 2 O 3 target, dissolution of post irradiation, determination of radioactivity concentration of 153 Sm radioisotope, radionuclide purity, EDTMP labeling, determination of radiochemical purity and pH. In these experiments the total radioactivity 153 Sm product is round about 2845.83 mCi to 36963.31 mCi, or with the radioactivity concentration between 474 mCi/ml to 6160.55 mCi/ml in the SmCl 3 solution form, each its volume is 6.0 ml, and the samarium content is 5.76 mg/ml, and the radionuclide purity of 153 Sm is 100 %. All of the 153 Sm- EDTMP radiopharmaceuticals product are fulfilled requirements the radioactivity concentration, Sm content, radiochemical purity and pH. The radioactivity concentration of 153 Sm-EDTMP radiopharmaceuticals is 37.50 mCi/ml (minimum) to 283.50 mCi/ml (highest). The pH 7.5 were 8 products, and the rest are pH 8.5. Radiochemical purity of 153 Sm-EDTMP are round about 90.00 % to 99.44 %. (author)

  2. Bus.py: A GridLAB-D Communication Interface for Smart Distribution Grid Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, Timothy M.; Palmintier, Bryan; Suryanarayanan, Siddharth; Maciejewski, Anthony A.; Siegel, Howard Jay

    2015-07-03

    As more Smart Grid technologies (e.g., distributed photovoltaic, spatially distributed electric vehicle charging) are integrated into distribution grids, static distribution simulations are no longer sufficient for performing modeling and analysis. GridLAB-D is an agent-based distribution system simulation environment that allows fine-grained end-user models, including geospatial and network topology detail. A problem exists in that, without outside intervention, once the GridLAB-D simulation begins execution, it will run to completion without allowing the real-time interaction of Smart Grid controls, such as home energy management systems and aggregator control. We address this lack of runtime interaction by designing a flexible communication interface, Bus.py (pronounced bus-dot-pie), that uses Python to pass messages between one or more GridLAB-D instances and a Smart Grid simulator. This work describes the design and implementation of Bus.py, discusses its usefulness in terms of some Smart Grid scenarios, and provides an example of an aggregator-based residential demand response system interacting with GridLAB-D through Bus.py. The small scale example demonstrates the validity of the interface and shows that an aggregator using said interface is able to control residential loads in GridLAB-D during runtime to cause a reduction in the peak load on the distribution system in (a) peak reduction and (b) time-of-use pricing cases.

  3. Production of radioisotopes at the Boris Kidric Institute of Nuclear Sciences at Vinca, Yugoslavia

    International Nuclear Information System (INIS)

    Teofilovski, C.

    1969-01-01

    The investigations in order to master the production of radioisotopes were commenced simultaneously with the beginning of RA nuclear reactor construction at Vinca, in 1956. A new organization division - Laboratory for chemistry of high activity accepting beside other problems also the programme for mastering the regular production of radioactive material was formed in 1959. Various problems during the realization of this programme have been solved, starting with the staff training for work with radioactive material on the high level activity (to 7500 Ci/source), construction and equipment of the laboratory area for safe work, up to development of the whole series of chemical-technological procedures and techniques for regular production of various radioactive products, as well as the methods for their chemical, radiometric and pharmaceutical control. Owing to the successful realization of this programme, the Institute 'Boris Kidric' supplies to-day regularly 110 organizations in the country with various radioactive products, applied in medicine, industry and research. The annual product of the radioactive solutions of radioisotopes J-131, Au-198, P-32, S-35 etc., amounts to about 75 Ci, radiographic sources Ir-192 and Co-60 to 2000 Ci and Co-60 sources for teletherapy and the other applications to many thousand curies (author) [sr

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  5. Chapter 3 – VPPD-Lab: The Chemical Product Simulator

    DEFF Research Database (Denmark)

    Kalakul, Sawitree; Cignitti, Stefano; Zhang, L.

    2017-01-01

    for computer-aided chemical product design and evaluation, implemented in the software called VPPD-Lab, is presented. In the same way a typical process simulator works, the VPPD-Lab allows users to: (1) analyze chemical-based products by performing virtual experiments (product property and performance......Computer-aided methods and tools for current and future product–process design and development need to manage problems requiring efficient handling of models, data, and knowledge from different sources and at different times and size scales. In this chapter, a systematic model-based framework...... lotion design. Through these case studies, the use of design templates, associated workflows (methods), data flows (software integration), and solution strategies (database and tools) are highlighted....

  6. Cyclotron for industrial production of radioisotopes: relevants characteristics

    International Nuclear Information System (INIS)

    Lima, Wanderley de

    1997-01-01

    The industrial production of radioisotopes requests cyclotrons with easy maintenance services, high productivity and low operation costs. To obtain this performance the experts on the have achieved excellent results, taking advantage of modern resources in calculation and modeling. Only by the maximum exploitation of the azimutal variation of the magnetic field, a physical concept introduced in 1967 with the isocronous cyclotrons, it was possible to construct cyclotrons with only 30% of the electrical consumption required by the former cyclotrons. On the other hand, the acceleration of negative ions enable the 100% accelerated beam utilization, without internal energy dissipation, obtaining beam intensities up to 1mA in continuous running which represents an increased factor of 15. Other construction parameters were optimized aiming at reliability and reduction in the components activation. Concerning energy consumption and the beam intensity supplied, a present cyclotron with 30 MeV and 300μA of protons current is 15 times more efficient than its precedent. (author). 6 refs., 1 fig., 2 tabs

  7. Radioisotope techniques in oil wells

    International Nuclear Information System (INIS)

    Jain, Prabuddha

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    2002-10-01

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

  9. Radioisotope Power Sources

    International Nuclear Information System (INIS)

    Culwell, J. P.

    1963-01-01

    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

  10. Radioisotopes and their applications in highway testings

    International Nuclear Information System (INIS)

    Saxena, S.C.

    1974-01-01

    Applications of radioisotopes in highway testing are described. Radioisotopic methods have been used to determine : (1) moisture and density of soil and base materials for compaction control, (2) magnesium oxide content of cement, (3) permeability of bituminous coverings and (4) field density of freshly laid hot bituminous concrete surface. Possible uses of nuclear explosives for production of aggregates and of radioisotopes for determination of deflection in the design of flexible pavements are indicated. (M.G.B.)

  11. Markets for reactor-produced non-fission radioisotopes

    International Nuclear Information System (INIS)

    Bennett, R.G.

    1995-01-01

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

  12. 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)

  13. RSG-Gas Based Radioisotopes And Sharing Program For Regional Back Up Supply

    International Nuclear Information System (INIS)

    Soenardjo, Sunarhadijoso; Tamat, Swasono R.; Suparman, Ibon; Purwadi, Bambang

    2003-01-01

    As the owner of the reactors used for radioisotope production, BATAN needs to increase the effectiveness of the reactor operation cost that can be achieved by simultaneously exploiting all the existing irradiation facility, supported by full utilization of the radioisotopes produced. On the other hand, the domestic demand of radioisotopes is much lower than the production capability but sometimes the request is compulsory to be suspended due to reactor operation schedule. As this condition is mostly similar to that of several countries of RCA Member States, a sharing program for regional back up supply seems to be a positive thought to support expectation on the effectiveness of reactor operation cost and the continuity of radioisotope product services as well as the utilization of radioisotopes produced. Based on radioactivity achieved in each production batch at the present, 131 I, 99 Mo, 153 Sm, 125 I and 32 p radioisotopes may be offered for back up supply program. Due to consideration on conformity of user demands with reactor operation and radiochemical processing costs, the concept of back up supply program should performed first by means of full utilization of the available products and not by increasing reactor operation frequency. An information and communication network system, therefore, is absolutely needed to support information exchange between the radioisotope producer, members of back up supply program and radioisotope customers

  14. Radiation protection at radioisotope processing facilities

    International Nuclear Information System (INIS)

    Hillier, L.R.; Decaire, R.

    2002-01-01

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

  15. Production and chemical separation of 48 V radioisotope

    International Nuclear Information System (INIS)

    Szucs, Z.; Dudu, D.; Cimpeanu, C.; Luca, A.; Duta, E.; Sahagia, M.

    2003-01-01

    The positron emitter 48 V isotope (T 1/2 =16 d, γ-lines: 511 keV (100%), 983.5 (100%), 1312 (97.6%)) is of interest in several fields of science. This is valid for transmitting scans in the validation process of PET-camera by positron emission. It can be used as an industrial monitoring isotope by its γ-photons having high energy and intensity. Also, it is suitable for biological study since it is the only radioisotope of the biological trace element vanadium which can be a radiotracer due to its longer half-life. The 48 V was produced by nat Ti (d,xn) 48 V nuclear reaction in the U-120 cyclotron with activity of 6 mCi. The energy of irradiating beam was 13 MeV, its intensity was 5 μA and the metallic Ti target dimensions were 16 x 11 x 2 mm. For target cooling, the water circulation in the back side was used. After 3 cooling days, only 48 V, and some 46 Sc (T 1/2 = 84 d), produced by the side nuclear reaction 48 Ti (d,α) 46 Sc were found in the target. For the preparation of 48 V source, the Ti target was dissolved in HF and sulfuric acid. The ion exchange separation was developed for both dissolving methods. The dissolution of the chemically resistant Ti target is so violent in concentrated (3.5 % m/m) HF, that it is necessary to be carried out in polyethylene tube in order to avoid the splash of the dissolved target. An anion exchange column, Dowex 1-8 (size 100-200 mesh, length 12 cm, ID 10 mm, treated 1 day earlier, prepared fresh), was used for separation in HF media. The reduced ionic form of Ti bonds to resin, therefore the dissolved target was saturated with sulfur-dioxide produced in the Kipp-equipment by the following chemical reaction: Na 2 SO 3 + 2 HCl → 2 NaCl + H 2 SO 3 . The treated solution was diluted to a concentration of 2 mol/l of HF and the same concentration of the HF was used as an eluent for separation. Flow rate of the elution was 1 ml/min. The eluate was cooled fractionally. The fractions were measured by γ-spectrometry, which

  16. Medical radioisotopes production at the isochronous cyclotron in Alma-Ata

    International Nuclear Information System (INIS)

    Arzumanov, A.A.; Batischev, V.N.; Gladun, V.K.; Kochetkov, V.L.

    1988-01-01

    High efficiency cyclotron operations (up to 5200 hours of beam time a year) considerably increased the possibility to perform both fundamental and applied scientific work. There appeared possibility to accelerate protons in a wide energy range from 6 to 30 MeV and realize correspondingly the nuclear reactions up to (A, 3n). This paper reports that among different applied tasks performed at the cyclotron the special program of cyclotron production of short-lived medical radioisotopes iodine-123, thallium-201, cadmium-109 in the first place and some others to satisfy clinic needs of Alma-Ata and its region has special importance. In accordance with this program the preparation to produce iodine-123 is being held and regular production of Thallium chloride, thallium-201 pharmaceptical is started

  17. 76 FR 63668 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2011-10-13

    ..., Research and Test Reactors Projects Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor... NUCLEAR REGULATORY COMMISSION [NRC-2011-0135] Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-10-01

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

  19. Studies on application of radiation and radioisotopes

    International Nuclear Information System (INIS)

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

    1993-05-01

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

  20. The radioisotopes and radiations program

    International Nuclear Information System (INIS)

    1982-01-01

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

  1. Development and application of industrial radioisotope instruments in China

    International Nuclear Information System (INIS)

    Lu Yanxiao

    1994-09-01

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

  2. Twenty years of Korea radioisotope association history

    International Nuclear Information System (INIS)

    2005-09-01

    This contents has two parts. The first part describes the present and post of Korea radioisotope association which are about the foundation of the association, organization, main projects and vision of the association. The second part is about the use and the prospect of radiation and radioisotope in Korea, which shows the plan of expansion of use of radiation and radioisotope, the prospect and present condition in fields such as medical, industry and farming, product and distribution, research and development of human resources, system and management of safety of radiation.

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  5. 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)

  6. Radioisotopic control and automation of food mills

    International Nuclear Information System (INIS)

    Pertsovskij, E.S.; Sakharov, Eh.V.; Dolinin, V.A.

    1980-01-01

    Domestic and foreign experience in application of radioisotope devices to process control in fool industry, is described. The diagrams of devices to block and account the production in systems of process monitoring and control are considered. The methods of determining chemical composition of substances are discussed, as sell as the devices used for those purposes and based on recording β-and γ-radiation absorption by substance. The methods for determining dust and smoke content in premises using radioisotope devices. Level indicators, moisture gages and densitimeters usedf ctol level humidity, density and concentration of food products in the process of production are described [ru

  7. Transport of radioisotopes

    International Nuclear Information System (INIS)

    Aoki, Shigefumi

    1978-01-01

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

  8. Radioisotope production with a medical cyclotron

    International Nuclear Information System (INIS)

    Silvester, D.J.

    1974-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-08-01

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

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

    International Nuclear Information System (INIS)

    1963-01-01

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

  11. 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...

  12. Preliminary definition of the design of a nuclear reactor for research and radioisotope production using natural uranium and heavy water

    International Nuclear Information System (INIS)

    Llagostera Beltran, J.I.

    1982-01-01

    A study was conducted about the evolution of the Brazilian importations of radioisotopes, from the beginning of the 70's since they have been increasingly used in the Country. In view of the limited production capacity of radioactive isotopes now existing in Brazil, a nuclear reactor type (natural uranium and heavy water) was defined, for research and production of radioisotopes, wich, besides providing, at least partially, the Brazilian needs of said isotopes, permits a large national participation in its project, construction and operating maintenance. The processes for heavy water production have been analyzed and it could be detected what is the best alternative for the production thereof, in low scale, in Brazil. The options concerning the definition of the main components of the reactor were justified and its most important features were determined, in relation to the neutronic and thermal aspects, being so defined its most significant parameters. The annual quantities were estimated, in terms of total and specific activity, for the radioisotopes that could be obtained by means of the proposed reactor, which, by now, are participating, to a large extent, in the total of Brazilian importation of radioactive isotopes. (Author) [pt

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

    Science.gov (United States)

    2012-04-10

    ... Licensing of Non-Power Reactors: Format and Content,'' for the production of radioisotopes and NUREG-1537, Part 2, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors... by searching on http://www.regulations.gov under Docket ID NRC-2011-0135. You may submit comments by...

  14. 3D Reconstruction of NMR Images by LabVIEW

    Directory of Open Access Journals (Sweden)

    Peter IZAK

    2007-01-01

    Full Text Available This paper introduces the experiment of 3D reconstruction NMR images via virtual instrumentation - LabVIEW. The main idea is based on marching cubes algorithm and image processing implemented by module of Vision assistant. The two dimensional images shot by the magnetic resonance device provide information about the surface properties of human body. There is implemented algorithm which can be used for 3D reconstruction of magnetic resonance images in biomedical application.

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

    International Nuclear Information System (INIS)

    Van Houten, N.C.

    1989-06-01

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

  16. 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.

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

    International Nuclear Information System (INIS)

    Sunarhadijoso-Soenarjo

    2003-01-01

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

  18. Cost-benefit aspects of radioisotope methods

    International Nuclear Information System (INIS)

    Jankowski, L.

    1986-01-01

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

  19. Packaging and transport of radioisotopes

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1976-01-01

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

  20. 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)

    1963-01-01

    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

  1. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-03-15

    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

  2. Radiation protection in cyclotron and radioisotope production laboratories of IEN - (Instituto de Engenharia Nuclear - CNEN)

    International Nuclear Information System (INIS)

    Fajardo, P.W.; Silva, J.J.G.

    1988-01-01

    The Cyclotron at Instituto de Engenharia Nuclear is used for the radioisotope production, neutron production and irradiation damages analysis, etc. The risks associated with the operation and maintenance of cyclotron and the neutron radiation of wide energy spectrum, external and internal contamination. A summary of the radioprotection program for these areas are show and the results obtained from the air and surface analysis, liquid efluents and equivalentes doses of workers of the several activities are given. (Author) [pt

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

    International Nuclear Information System (INIS)

    Louw, P.A.

    2001-01-01

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

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

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1986-01-01

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

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

    International Nuclear Information System (INIS)

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

    1979-05-01

    The purpose of the document is to list DOE's radioisotopes production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboratory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Savannah River Laboratory; and UNC Nuclear Industries, Inc

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

    International Nuclear Information System (INIS)

    Lamar, D.A.

    1988-01-01

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

  7. PD Lab

    NARCIS (Netherlands)

    Bilow, Marcel; Entrop, Alexis Gerardus; Lichtenberg, Jos; Stoutjesdijk, Pieter

    2015-01-01

    PD Lab explores the applications of building sector related product development. PD lab investigates and tests digital production technologies like CNC milled wood connections. It will also act as a platform in its wider meaning to investigate the effects and influences of file to factory

  8. Design study and heat transfer analysis of a neutron converter target for medical radioisotope production

    International Nuclear Information System (INIS)

    Masoud Behzad; Sang-In Bak; Seung-Woo Hong; Jong-Seo Chai; Yacine Kadi; Claudio Tenreiro; University of Talca, Talca

    2014-01-01

    A worldwide challenge in the near future will be to find a way of producing radioisotopes in sufficient quantity without relying on research reactors. The motivation for this innovative work on targets lies in the accelerator-based production of radioisotopes using a neutron converter target as in the transmutation by adiabatic resonance crossing concept. Thermal analysis of a multi-channel helium cooled device is performed with the computational fluid dynamics code CFX. Different boundary conditions are taken into account in the simulation process and many important parameters such as maximum allowable solid target temperature as well as uniform inlet velocity and outlet pressure changes in the channels are investigated. The results confirm that the cooling configuration works well; hence such a solid target could be operated safely and may be considered for a prototype target. (author)

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

    International Nuclear Information System (INIS)

    Niu Fang

    1987-01-01

    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 57 Co, 109 Cd, 68 Ge- 68 Ga, and 167 Tm are given respectively. (author)

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

    Indian Academy of Sciences (India)

    Unknown

    lity of high purity target materials, natural or enriched, are crucial for any successful radioisotope pro- gramme. Selection ... and blockages detection in buried pipelines are rendered ..... from reputed international suppliers with analysis report.

  11. Proton linac for hospital-based fast neutron therapy and radioisotope production

    International Nuclear Information System (INIS)

    Lennox, A.J.; Hendrickson, F.R.; Swenson, D.A.; Winje, R.A.; Young, D.E.

    1989-09-01

    Recent developments in linac technology have led to the design of a hospital-based proton linac for fast neutron therapy. The 180 microamp average current allows beam to be diverted for radioisotope production during treatments while maintaining an acceptable dose rate. During dedicated operation, dose rates greater than 280 neutron rads per minute are achievable at depth, DMAX = 1.6 cm with source to axis distance, SAD = 190 cm. Maximum machine energy is 70 MeV and several intermediate energies are available for optimizing production of isotopes for Positron Emission Tomography and other medical applications. The linac can be used to produce a horizontal or a gantry can be added to the downstream end of the linac for conventional patient positioning. The 70 MeV protons can also be used for proton therapy for ocular melanomas. 17 refs., 1 fig., 1 tab

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  13. 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.

  14. Radioisotope thermoelectric generators for implanted pacemakers

    Energy Technology Data Exchange (ETDEWEB)

    Pustovalov, A.A.; Bovin, A.V.; Fedorets, V.I.; Shapovalov, V.P.

    1986-08-01

    This paper discusses the development and application of long-life lithium batteries and the problems associated with miniature radioisotope thermoelectric generators (RITEG) with service lives of 10 years or longer. On eof the main problems encountered when devising a radioisotope heat source (RHS) for an RITEG is to obtain biomedical /sup 238/PuO/sub 2/ with a specific neutron yield of 3.10/sup 3/-4.10/sup 3/ (g /SUP ./ sec)/sup -1/, equivalent to metallic Pu 238, and with a content of gamma impurities sufficient to ensure a permissible exposure a permissible exposure does rate (EDR) of a mixture of neutron and gamma radiation. After carrying out the isotope exchange and purifying the initial sample of its gamma impurity elements, the authors obtain biomedical Pu 238 satisfying the indicated requirements king suitable for use in the power packs of medical devices. Taking the indicated specifications into account, the Ritm-1o and gamma radioisotope heat sources were designed, built, tested in models and under natural conditions, and then into production as radioisotope thermoelectric generators designed to power the electronic circuits of implanted pacemakers. The Ritm-MT and Gemma radioisotope thermoelectric generators described are basic units, which can be used as self-contained power supplies for electronic equipment with power requirements in the micromilliwatt range.

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

    International Nuclear Information System (INIS)

    Akabani, Gamal

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-08-31

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

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

    International Nuclear Information System (INIS)

    Akabani, Gamal

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-28

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

  19. Actual and future situations of the use of radioisotopes

    International Nuclear Information System (INIS)

    Paredes G, L.C.

    2005-01-01

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

  20. Industrial radioisotope economics. Findings of the study group

    International Nuclear Information System (INIS)

    1965-01-01

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

  1. Measurement cross sections for radioisotopes production

    International Nuclear Information System (INIS)

    Garrido, E.

    2011-01-01

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

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

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  3. Cosmogenic radioisotopes in Gebel Kamil meteorite

    Science.gov (United States)

    Taricco, C.; Colombetti, P.; Bhandari, N.; Sinha, N.; Di Martino, M.; Vivaldo, G.

    2012-04-01

    Recently a small (45 m in diameter) and very young (radioisotope activity generated by cosmic rays in the meteoroids as they travel through the interplanetary space before falling on the Earth. From the 26Al activity measurement and its depth production profiles, we infer (i) that the radius of the meteoroid should be about 1 m, constraining to 30-40 ton the range of pre-atmospheric mass previously proposed and (ii) that the fragment should have been located deeply inside the meteoroid, at a depth > 0.7 m. The 44Ti activity is under the detection threshold of the apparatus; using the depth production profiles of this radioisotope and its half-life T1/2 = 59.2 y, we deduce an upper limit to the date of fall.

  4. Practical applications of short-lived radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-01-15

    The advantages of the use of short-lived radioisotopes in agriculture, food industry and medicine as well as some industrial uses are discussed. Methods for isotope production in small research reactors and laboratories are presented

  5. Validation of FLUKA calculated cross-sections for radioisotope production in proton-on-target collisions at proton energies around 1 GeV

    CERN Document Server

    Felcini, M

    2006-01-01

    The production cross-sections of several radioisotopes induced by 1 GeV protons impinging on different target materials have been calculated using the FLUKA Monte Carlo and compared to measured cross-sections. The emphasis of this study is on the production of alpha and beta/gamma emitters of interest for activation evaluations at a research complex, such as the EURISOL complex, using several MW power proton driver at an energy of 1 GeV. The comparisons show that in most of the cases of interest for such evaluations, the FLUKA Monte Carlo reproduces radioisotope production cross-sections within less than a factor of two with respect to the measured values. This result implies that the FLUKA calculations are adequately accurate for proton induced activation estimates at a 1 GeV high power proton driver complex.

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

    International Nuclear Information System (INIS)

    Zainus-Salimin; Gunandjar; Dedy-Harsono; Hendro; Sugeng-Purnomo; Mohammad-Faruq; Zulfakhri

    2000-01-01

    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 Cr 3+ , and coagulation-flocculation process for step II using BaCI 2 coagulant for precipitation of chrome Cr 6+ 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 BaCI 2 for supernatant from coagulation of step I. (author)

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  8. 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.

  9. Development of radioisotope preparation and application technology

    International Nuclear Information System (INIS)

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

    2000-04-01

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

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

    International Nuclear Information System (INIS)

    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

  11. 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.

  12. Radioisotope detection with accelerators

    International Nuclear Information System (INIS)

    Mast, T.S.; Muller, R.A.; Tans, P.P.

    1979-12-01

    High energy mass spectrometry is a new and very sensitive technique of measuring rare radioisotopes. This paper describes the techniques used to select and identify the individual radioisotope atoms in a sample and the status of the radioisotope measurements and their applications

  13. PD Lab

    Directory of Open Access Journals (Sweden)

    Marcel Bilow

    2015-08-01

    Full Text Available PD Lab explores the applications of building sector related product development.  PD lab investigates and tests digital production technologies like CNC milled wood connections. It will also act as a platform in its wider meaning to investigate the effects and influences of file to factory production, to explore the potential in the field of sustainability, material use, logistics and the interaction of stakeholders within the chain of the building process.

  14. Radioisotopes as Political Instruments, 1946-1953.

    Science.gov (United States)

    Creager, Angela N H

    2009-01-01

    The development of nuclear "piles," soon called reactors, in the Manhattan Project provided a new technology for manufacturing radioactive isotopes. Radioisotopes, unstable variants of chemical elements that give off detectable radiation upon decay, were available in small amounts for use in research and therapy before World War II. In 1946, the U.S. government began utilizing one of its first reactors, dubbed X-10 at Oak Ridge, as a production facility for radioisotopes available for purchase to civilian institutions. This program of the U.S. Atomic Energy Commission was meant to exemplify the peacetime dividends of atomic energy. The numerous requests from scientists outside the United States, however, sparked a political debate about whether the Commission should or even could export radioisotopes. This controversy manifested the tension in U.S. politics between scientific internationalism as a tool of diplomacy, associated with the aims of the Marshall Plan, and the desire to safeguard the country's atomic monopoly at all costs, linked to American anti-Communism. This essay examines the various ways in which radioisotopes were used as political instruments-both by the U.S. federal government in world affairs, and by critics of the civilian control of atomic energy-in the early Cold War.

  15. 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.

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

    International Nuclear Information System (INIS)

    Baker, D.A.

    1986-08-01

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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-07-01

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

  19. Application of radioisotopes in entomology

    International Nuclear Information System (INIS)

    Saour, G.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    Lamar, D.A.

    1987-10-01

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

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

    International Nuclear Information System (INIS)

    1964-01-01

    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

  2. Evaluation of the OSCAR-4/MCNP calculation methodology for radioisotope production in the SAFARI-1 reactor

    International Nuclear Information System (INIS)

    Karriem, Z.; Zamonsky, O.M.

    2014-01-01

    The South African Nuclear Energy Corporation SOC Ltd (Necsa) is a state owned nuclear facility which owns and operates SAFARI-1, a 20 MW material testing reactor. SAFARI-1 is a multi-purpose reactor and is used for the production of radioisotopes through in-core sample irradiation. The Radiation and Reactor Theory (RRT) Section of Necsa supports SAFARI-1 operations with nuclear engineering analyses which include core-reload design, core-follow and radiation transport analyses. The primary computer codes that are used for the analyses are the OSCAR-4 nodal diffusion core simulator and the Monte Carlo transport code MCNP. RRT has developed a calculation methodology based on OSCAR-4 and MCNP to simulate the diverse in-core irradiation conditions in SAFARI-1, for the purpose of radioisotope production. In this paper we present the OSCAR-4/MCNP calculation methodology and the software tools that were developed for rapid and reliable construction of MCNP analysis models. The paper will present the application and accuracy of the methodology for the production of yttrium-90 ( 90 Y) and will include comparisons between calculation results and experimental measurements. The paper will also present sensitivity analyses that were performed to determine the effects of control rod bank position, representation of core depletion state and sample loading configuration, on the calculated 90 Y sample activity. (author)

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

    International Nuclear Information System (INIS)

    Trevena, I.

    1994-01-01

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

  4. Production of D-tagatose, a low caloric sweetener during milk fermentation using L-arabinose isomerase.

    Science.gov (United States)

    Rhimi, Moez; Chouayekh, Hichem; Gouillouard, Isabelle; Maguin, Emmanuelle; Bejar, Samir

    2011-02-01

    Lactobacillusdelbrueckii subsp. bulgaricus and Streptococcus thermophilus are used for the biotransformation of milk in yoghurt. During milk fermentation, these lactic acid bacteria (LAB) hydrolyze lactose producing a glucose moiety that is further metabolized and a galactose moiety that they are enable to metabolize. We investigated the ability of L. bulgaricus and S. thermophilus strains expressing a heterologous L-arabinose isomerase to convert residual D-galactose to D-tagatose. The Bacillus stearothermophilus US100l-arabinose isomerase (US100l-AI) was expressed in both LAB, using a new shuttle vector where the araA US100 gene is under the control of the strong and constitutive promoter of the L. bulgaricus ATCC 11842 hlbA gene. The production of L-AI by these LAB allowed the bioconversion of D-galactose to D-tagatose during fermentation in laboratory media and milk. We also established that the addition of L-AI to milk also allowed the conversion of D-galactose into D-tagatose during the fermentation process. Copyright © 2010 Elsevier Ltd. All rights reserved.

  5. Application of radioisotopes in entomology

    Energy Technology Data Exchange (ETDEWEB)

    Saour, G [Atomic Energy Commission, Damascus (Syrian Arab Republic). Dept. of Radiation Agriculture

    1995-10-01

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

  6. Universal lab-on-a-chip platform for complex, perfused 3D cell cultures

    Science.gov (United States)

    Sonntag, F.; Schmieder, F.; Ströbel, J.; Grünzner, S.; Busek, M.; Günther, K.; Steege, T.; Polk, C.; Klotzbach, U.

    2016-03-01

    The miniaturization, rapid prototyping and automation of lab-on-a-chip technology play nowadays a very important role. Lab-on-a-chip technology is successfully implemented not only for environmental analysis and medical diagnostics, but also as replacement of animals used for the testing of substances in the pharmaceutical and cosmetics industries. For that purpose the Fraunhofer IWS and partners developed a lab-on-a-chip platform for perfused cell-based assays in the last years, which includes different micropumps, valves, channels, reservoirs and customized cell culture modules. This technology is already implemented for the characterization of different human cell cultures and organoids, like skin, liver, endothelium, hair follicle and nephron. The advanced universal lab-on-a-chip platform for complex, perfused 3D cell cultures is divided into a multilayer basic chip with integrated micropump and application-specific 3D printed cell culture modules. Moreover a technology for surface modification of the printed cell culture modules by laser micro structuring and a complex and flexibly programmable controlling device based on an embedded Linux system was developed. A universal lab-on-a-chip platform with an optional oxygenator and a cell culture module for cubic scaffolds as well as first cell culture experiments within the cell culture device will be presented. The module is designed for direct interaction with robotic dispenser systems. This offers the opportunity to combine direct organ printing of cells and scaffolds with the microfluidic cell culture module. The characterization of the developed system was done by means of Micro-Particle Image Velocimetry (μPIV) and an optical oxygen measuring system.

  7. Applications of radioisotopes in medicine

    International Nuclear Information System (INIS)

    Sivaprasad, N.

    2012-01-01

    The application of radioisotopes in medicine is many folds. They can be classified into two main groups. (a) The radioisotope tagged labeled compounds suitable for safe administration in the body for diagnosis of various diseases of vital organs such as brain, kidney, thyroid etc and for treatment known as radiotherapy (b) The sealed source of radioisotopes for utilizing the radiation emitted from the radioisotope for treatment, particularly for radiation therapy of cancer. The former application of radioisotope in the field of medicine has led to the formation of special branch of medicine termed Nuclear Medicine - the branch of medicine deals with the use of radioisotope in the from of radiopharmaceuticals for investigation, diagnosis and treatment of diseases. Radioisotopes in the form of radiolabelled compound and bio-chemicals that are pharmaceutically and radiologically safe for administration in the body for diagnosis and treatment are called radiopharmaceuticals. The radiopharmaceuticals are the results of world-wide effort to bring nuclear energy in a tangible form for diagnosis and treatment. Radioisotopes as radiopharmaceuticals thus constitute one of the key requirements for nuclear medicine investigation and radiotherapy. In the case of sealed radioisotope source the radiation emitted by the radioactive source is utilized for the treatment and this mode of treatment is called radiation therapy where no radioactive substance is administrated into the body. This does not form the part of nuclear medicine

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

    International Nuclear Information System (INIS)

    Kramer, H.H.

    1985-01-01

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

  9. Lessons Learned from the Jefferson Lab - SNS Cryomodule Production Run

    International Nuclear Information System (INIS)

    John Hogan; Edward Daly; John Fischer; Joseph Preble

    2005-01-01

    In light of the recent developments with the International Linear Collider (ILC), and the recommendation to utilize ''Cold'' technology for this future particle accelerator, this paper will present the lessons learned from the recently concluded Spallation Neutron Source (SNS) superconducting radio frequency (SRF) cryomodule production run at the Thomas Jefferson National Accelerator Facility (Jefferson Lab). Over the past twenty years Jefferson Lab has worked with industry to successfully design, manufacture, test and commission more SRF cryomodules than any other entity in the United States. The knowledge gained from the design and fabrication of the SNS prototype, eleven - 0.61 (medium) beta and the twelve - 0.81 (high) beta cryomodules, will prove to be an effective asset to the ILC project. After delivery of the final production cryomodule in March 2005, design and fabrication data will be collected, evaluated and presented to make this information beneficial for future particle accelerator projects. Recommendations with respect to these findings will also be presented as an integral part of this paper

  10. Application of radiation and radioisotopes in life science

    International Nuclear Information System (INIS)

    Nakanishi, Tomoko M.

    2005-01-01

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

  11. Lab-on-a-Chip Device for Rapid Measurement of Vitamin D Levels.

    Science.gov (United States)

    Peter, Harald; Bistolas, Nikitas; Schumacher, Soeren; Laurisch, Cecilia; Guest, Paul C; Höller, Ulrich; Bier, Frank F

    2018-01-01

    Lab-on-a-chip assays allow rapid analysis of one or more molecular analytes on an automated user-friendly platform. Here we describe a fully automated assay and readout for measurement of vitamin D levels in less than 15 min using the Fraunhofer in vitro diagnostics platform. Vitamin D (25-hydroxyvitamin D 3 [25(OH)D 3 ]) dilution series in buffer were successfully tested down to 2 ng/mL. This could be applied in the future as an inexpensive point-of-care analysis for patients suffering from a variety of conditions marked by vitamin D deficiencies.

  12. In vivo evaluation of biosensors volumetric bio-distribution for measurement of metabolic activity by X-ray correlation, fluorescence, Cerenkov image and radioisotope

    International Nuclear Information System (INIS)

    Ramirez N, G. J.

    2016-01-01

    The aim of this study was to characterize the in vivo volumetric distribution of three folate based biosensors by different imaging modalities (X-ray, fluorescence, Cerenkov luminescence and radioisotopic imaging) through the development of a tri dimensional (3D) image reconstruction algorithm. The preclinical and multimodal Xtreme imaging system, with a Multimodal Animal Rotation System (Mars), was used to acquire bidimensional (2D) images, which were processed to obtain the 3D reconstruction. Images of mice at different times (biosensor distribution) were simultaneously obtained from the four imaging modalities. The filtered backprojection and inverse Radon transformation were used as main image-processing techniques. In the first instance, the algorithm developed in Mat lab was able to reconstruct in the 3D form the skeleton of the mice under study. Subsequently, the algorithm was able to get the volumetric profiles of "9"9"mTc-Folate-Bombesin (radioisotopic image), "1"7"7Lu-Folate-Bombesin (Cerenkov image), and FolateRSense 680 (fluorescence image) in the tumors and kidneys of the mice. No significant differences were detected between the volumetric quantifications using the standard measurement techniques and the quantifications obtained with the proposal made in this study, nor between the volumetric uptakes in the structures of interest. With the structures reconstructed in the 3D form, the fusion of anatomical (as the skeleton) and functional structures derived from the images of the biosensors uptake was achieved The imaging 3D reconstruction algorithm can be easily extrapolated to different 2D acquisition-type images. This characteristic flexibility of the algorithm developed in this study is an advantage in comparison to similar reconstruction methods. (Author)

  13. Development of indigenous technology at CNEN in the fields of nuclear medicine, nuclear detectors, instrumentation, radioisotope production and application of nuclear techniques

    International Nuclear Information System (INIS)

    Mafra, O.

    1990-01-01

    The main objectives of the program developed at CNEN in the field of nuclear medicine, nuclear detectors, instrumentation, radioisotope production and application of nuclear technique are described. (E.G.) [pt

  14. Utilization of the Dalat Research Reactor for Radioisotope Production, Neutron Activation Analysis, Research and Training

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Duong Van Dong; Cao Dong Vu; Nguyen Xuan Hai

    2013-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool type reactor loaded with a mixed core of HEU (36% enrichment) and LEU (19.75% enrichment) fuel assemblies. The reactor is used as a neutron source for the purposes of radioisotopes production, neutron activation analysis, basic and applied research and training. The reactor is operated mainly in continuous runs of 108 hours for cycles of 3–4 weeks for the above mentioned purposes. The current status of safety, operation and utilization of the reactor is given and some aspects for improvement of commercial products and services of the DNRR are also discussed in this paper. (author)

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

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

    Science.gov (United States)

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

    2015-07-01

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

  17. Radioisotope battery for particular application

    International Nuclear Information System (INIS)

    Shen Tianjian; Liang Daihua; Cai Jianhua; Dai Zhimin; Xia Huihao; Wang Jianhua; Sun Sen; Yu Guojun; Wang Xiao; Wang Dongxing; Liu Xin

    2010-01-01

    Radioisotope battery, as a new type of power source, was developed in 1960s. It is advantageous in terms of long working life, high reliability, flexibility to rugged environment, maintenance free, and high capacity rate, hence its unique applications in space, isolated terrestrial or ocean spots, deep waters, and medicine. In this paper, we analysz the primary performances and classification of radioisotope thermoelectric generator, as well as characteristic, basic principle,and structure of radioisotope thermoelectric generator (RTG), which is the most popular in application of radioisotope battery in space, undersea, terrestrial and medicine. A prospect for development and application of radioisotope battery in the 21 st century is given, too. (authors)

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

    International Nuclear Information System (INIS)

    Mondt, J.F.; Underwood, M.L.; Nesmith, B.J.

    1997-01-01

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

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

    International Nuclear Information System (INIS)

    Kohli, A.K.

    2012-01-01

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

  20. Radioisotope measurement system

    International Nuclear Information System (INIS)

    Villanueva Ruibal, Jose

    2007-01-01

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

  1. Modular 3D printed lab-on-a-chip bio-reactor for the biochemical energy cascade of microorganisms

    Science.gov (United States)

    Podwin, Agnieszka; Dziuban, Jan A.

    2017-10-01

    The paper presents the sandwiched polymer 3D printed lab-on-a-chip bio-reactor for the biochemical energy cascade of microorganisms. Euglenas and yeast were separately and simultaneously cultured for 10 d in the chip. As a result of the experiments, euglenas, light-initialized and nourished by CO2—a product of ethanol fermentation handled by yeast—generated oxygen, based on the photosynthesis process. The presence of oxygen in the bio-reactor was confirmed by the colorimetric method—a bicarbonate (pH) indicator. Preliminary studies towards the obtainment of an effective source of oxygen are promising and further research should be done to enable the utility of the bio-reactor in, for instance, microbial fuel cells.

  2. Modular 3D printed lab-on-a-chip bio-reactor for the biochemical energy cascade of microorganisms

    International Nuclear Information System (INIS)

    Podwin, Agnieszka; Dziuban, Jan A

    2017-01-01

    The paper presents the sandwiched polymer 3D printed lab-on-a-chip bio-reactor for the biochemical energy cascade of microorganisms. Euglenas and yeast were separately and simultaneously cultured for 10 d in the chip. As a result of the experiments, euglenas, light-initialized and nourished by CO 2 —a product of ethanol fermentation handled by yeast—generated oxygen, based on the photosynthesis process. The presence of oxygen in the bio-reactor was confirmed by the colorimetric method—a bicarbonate (pH) indicator. Preliminary studies towards the obtainment of an effective source of oxygen are promising and further research should be done to enable the utility of the bio-reactor in, for instance, microbial fuel cells. (paper)

  3. The future of medical radioisotope supply

    International Nuclear Information System (INIS)

    Peykov, Pavel

    2014-01-01

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

  4. Treatment of Radioactive Waste Generated from the Production of Molybdenum-99 Radioisotope

    International Nuclear Information System (INIS)

    Aisyah; Herlan Martono

    2007-01-01

    The 99 Mo is produced as the parent radionuclide for 99m Tc radioisotope which is used as medical radiodiagnostic for certain disease. In Indonesia 99 Mo is produced by irradiating target of high enriched U in the reactor. The characteristics of radioactive waste from the production of 99 Mo depend on the U enrichment of the target and the irradiation time. The characteristic of the radioactive waste can be directly determined by laboratory analysis or by ORIGEN 2 code. Producing 99 Mo from high enriched uranium target will produce radioactive waste containing 235 U, 238 U and fission product, while from low enriched uranium target will produce radioactive waste containing large amount of 239 Pu. Plutonium-239 is a long half life actinide that need to be separated from the fission product due to a different treatment is required. The fission product, after it is allowed to decay then needs to be categorized as low or medium level waste, while 239 Pu are categorized as transuranic waste. The disposal of low and medium level waste are stored in near surface disposal, while the disposal of transuranic waste is stored in a geologic formation. (author)

  5. A facility to remotely assemble radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Engstrom, J.W.; Goldmann, L.H.; Truitt, R.W.

    1992-07-01

    Radioisotope Thermoelectric Generators (RTGs) are electrical power sources that use heat from decaying radioisotopes to directly generate electrical power. The RTG assembly process is performed in an inert atmosphere inside a large glovebox, which is surrounded by radiation shielding to reduce exposure to neutron and gamma radiation from the radioisotope heat source. In the past, allowable dose rate limits have allowed direct, manual assembly methods; however, current dose rate limits require a thicker radiation shielding that makes direct, manual assembly infeasible. To minimize RTG assembly process modifications, telerobotic systems are being investigated to perform remote assembly tasks. Telerobotic systems duplicate human arm motion and incorporate force feedback sensitivity to handle objects and tools in a human-like manner. A telerobotic system with two arms and a three-dimensional (3-D) vision system can be used to perform remote RTG assembly tasks inside gloveboxes and cells using unmodified, normal hand tools

  6. Continuous D-lactic acid production by a novel thermotolerant Lactobacillus delbrueckii subsp. lactis QU 41.

    Science.gov (United States)

    Tashiro, Yukihiro; Kaneko, Wataru; Sun, Yanqi; Shibata, Keisuke; Inokuma, Kentaro; Zendo, Takeshi; Sonomoto, Kenji

    2011-03-01

    We isolated and characterized a D-lactic acid-producing lactic acid bacterium (D-LAB), identified as Lactobacillus delbrueckii subsp. lactis QU 41. When compared to Lactobacillus coryniformis subsp. torquens JCM 1166 (T) and L. delbrueckii subsp. lactis JCM 1248 (T), which are also known as D-LAB, the QU 41 strain exhibited a high thermotolerance and produced D-lactic acid at temperatures of 50 °C and higher. In order to optimize the culture conditions of the QU 41 strain, we examined the effects of pH control, temperature, neutralizing reagent, and initial glucose concentration on D-lactic acid production in batch cultures. It was found that the optimal production of 20.1 g/l D-lactic acid was acquired with high optical purity (>99.9% of D-lactic acid) in a pH 6.0-controlled batch culture, by adding ammonium hydroxide as a neutralizing reagent, at 43 °C in MRS medium containing 20 g/l glucose. As a result of product inhibition and low cell density, continuous cultures were investigated using a microfiltration membrane module to recycle flow-through cells in order to improve D-lactic acid productivity. At a dilution rate of 0.87 h(-1), the high cell density continuous culture exhibited the highest D-lactic acid productivity of 18.0 g/l/h with a high yield (ca. 1.0 g/g consumed glucose) and a low residual glucose (<0.1 g/l) in comparison with systems published to date.

  7. Radioisotopes as Political Instruments, 1946–1953

    Science.gov (United States)

    Creager, Angela N. H.

    2009-01-01

    The development of nuclear “piles,” soon called reactors, in the Manhattan Project provided a new technology for manufacturing radioactive isotopes. Radioisotopes, unstable variants of chemical elements that give off detectable radiation upon decay, were available in small amounts for use in research and therapy before World War II. In 1946, the U.S. government began utilizing one of its first reactors, dubbed X-10 at Oak Ridge, as a production facility for radioisotopes available for purchase to civilian institutions. This program of the U.S. Atomic Energy Commission was meant to exemplify the peacetime dividends of atomic energy. The numerous requests from scientists outside the United States, however, sparked a political debate about whether the Commission should or even could export radioisotopes. This controversy manifested the tension in U.S. politics between scientific internationalism as a tool of diplomacy, associated with the aims of the Marshall Plan, and the desire to safeguard the country’s atomic monopoly at all costs, linked to American anti-Communism. This essay examines the various ways in which radioisotopes were used as political instruments—both by the U.S. federal government in world affairs, and by critics of the civilian control of atomic energy—in the early Cold War. PMID:20725612

  8. 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.

  9. Determination of lactic acid bacteria viability in the small intestine of catfish (Pangasius Djambal) by using the 32P radioisotope

    International Nuclear Information System (INIS)

    Sugoro, I.; Citraresmini, A.; Murni, A.P.; Fairuz, D.

    2015-01-01

    The viability of probiotics is important to be determined, as is its probiotics potency in the small intestine of fish. The result can be used as a basis to determine the feeding frequency of the probiotics to the fish. The aim of this study is to gain information about the viability of lactic acid bacteria (LAB) in the small intestine of fish by using the 32 P isotope technique. Catfish (Pangasius djambal) was used as a test fish, and the LAB with the code of P2.1 PTB was the subject of the experiment. Before its viability was tested, the LAB had been labelled with radioisotope 32 P, then mixed into catfish feed. Its viability could be determined by counting the activity of 32 P. The results showed that the percentage of LAB viability in the small intestine of catfish declined until day 7. The percentage of LAB viability was decreased at an amount of 30% at day 3. Based on this result, the feeding frequency of LAB P2.1 PTB is every 3 days. (author)

  10. Determination of Lactic Acid Bacteria Viability in the Small Intestine of Catfish (Pangasius djambal by Using the 32P Radioisotope

    Directory of Open Access Journals (Sweden)

    I. Sugoro

    2015-04-01

    Full Text Available The viability of probiotics is important to be determined, as is its probiotic potency in the small instestine of fish. The result can be used as a basis to determine the feeding frequency of the probiotics to the fish.The aim of this study is to gain information about the viability of lactic acid bacteria (LAB in the small intestine of fish by using the 32P isotope technique. Catfish (Pangasius djambal was used as a test fish, and the LAB with the code of P2.1 PTB was the subject of the experiment. Before its viability was tested, the LAB had been labelled with radioisotope 32P, then mixed into catfish feed. Its viability could be determined by counting the activity of 32P. The results showed that the percentage of LAB viability in the small intestine of catfish declined until day 7. The percentage of LAB viability was decreased at an amount of 30% at day 3. Based on this result, the feeding frequency of LAB P2.1 PTB is every 3 days.

  11. Procedures for determining stream flowrate using radioisotope method in Pesanggrahan River, Indonesia. Prosedur untuk mengukur kadar-alir sungai menggunakan kaedah radioisotop di Sungai Pesanggrahan, Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    1983-08-01

    River flow measurements either by a current meter or a tracer dilution are established elsewhere. This report describes the experimental method, calibrations of NaI detector, preparation of radioisotopes and equipment, and safety aspect considerations as well as results interpretation in determining stream flowrate of Pesanggrahan River, Indonesia in which radioisotopes /sup 82/Br and /sup 51/Cr complexed with EDTA were used as tracers. The total count technique of stream flow D=AF/N, developed by Hull, was simplified for the ease of field work purposes and adopted in this study. Discharge results at different water levels during low flows gauged using both radioisotope tracers are comparable. The relationship between water level and discharge value is also plotted although the available data is insufficient.

  12. Neutron generators at Purnima Lab

    International Nuclear Information System (INIS)

    Patel, Tarun; Sinha, Amar

    2015-01-01

    Neutron sources are in a great demand in many area like research, nuclear waste management, industrial process control, medical and also security. Major sources of neutrons are nuclear reactors, radioisotopes and accelerator based neutron generators. For many field applications, reactors cannot be used due to its large size, complicated system, high cost and also safety issues. Radioisotopes like Pu-Be, Am-Be, Cf, are extensively used for many industrial applications. But they are limited in their use due to their low source strength and also handling difficulties due to radioactivity. They are also not suitable for pulsed neutron applications. In contrast, compact size, pulsed operation, on/off operation etc.of accelerator based neutron generators make them very popular for many applications. Particle accelerators based on different types of neutron generators have been developed around the world. Among these deuteron accelerator based D-D and D-T neutron generators are widely used as they produce mono-energetic fast neutrons and in particular high yield of D-T neutron can be obtained with less than 300 KV of accelerating voltage

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

    International Nuclear Information System (INIS)

    Bougharouat, B.

    1981-01-01

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

  14. Inclusive J / $\\psi$ Production at D0

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, Christopher R. [Indiana U.

    1995-04-01

    We present results on inclusive $J/\\psi$ and b-quark production in $p\\bar{p}$ collisions at $\\sqrt{s}$ = 1.8 TeV. The results are based on data collected at the D0 experiment during the 1992-1993 FermiLab collider run. There is excellent agreement between the differential $J/\\psi$ cross section measured at D0 and that measured at the CDF detector. A measurement of the fraction of $J/\\psi$ events due to b-quark decays is presented and we extract from this a measurement of the integrated b-quark cross section. The radiative decays of $_{Xc}$ charmonium states into the $J/\\psi$ is discussed and we present results on the fraction of $J/\\psi$ mesons that are due to $_{Xc}$ decays. We also observe that a fraction of promptly produced $J/\\psi$ mesons is larger than the measured fraction of $J/\\psi$ due to $_{Xc}$ decays and is not accounted for by existing charmonium. production models.

  15. The analysis of pilot-plant products for copper, zinc, and lead with the telsec lab-x-250 analyser

    International Nuclear Information System (INIS)

    Domel, G.

    1977-01-01

    Suites of sulphide material representative of copper, zinc, and lead concentrates, as well as 'intermediate' products, low-grade material, and tailing samples, were analysed with the Telsec Lab-X-250 Analyser, which is a radio-isotope x-rayfluorescence instrument using 'balanced' filters for energy selection. A brief description of the instrument is given, stress being laid on the principle of 'balanced' filters. The determination of optimum instrumental parameters is described, and diagrams are provided to demonstrate the efficacy of energy selection. Correlation diagrams are given for all three elements in each of the materials analysed. The scatter of data points encountered is examined in terms of possible spectral interference and matrix variation. It was found that, within specified limits of acceptability, all three elements could be determined satisfactorily in copper and lead concentrates and in low-grade material. Zinc concentrates could be analysed only for zinc. The mechanisms of the spectral interference effects peculiar to the use of balanced filters are discussed, and a correction procedure is described and applied to improve the correlation for copper in the presence of a high zinc content. It is shown that the poor correlation found for 'intermediate' products and for lead in zinc concentrates is mainly due to matrix variations. The concentration range covered, the sensitivity, the precision, and, where applicable, the detectionlimits are tabulated for all three elements and all types of material analysed. A comparison of the results obtained with the Analyser and those obtained by atomic-absorption spectrophotometry is provided [af

  16. A new radioisotope facility for Thailand

    International Nuclear Information System (INIS)

    Horlock, K.

    1997-01-01

    The Thai Office of Atomic Energy for Peace (OAEP) is planning a new Nuclear Research Centre which will be located at Ongkharak, a greenfield site some 100 km North of Bangkok. General Atomics (GA) has submitted a bid for a turnkey contract for the core facilities comprising a Reactor to be supplied by GA, an Isotope Production Facility supplied by ANSTO and a Waste Processing and Storage Facility to be supplied by Hitachi through Marubeni. The buildings for these facilities will be provided by Raytheon, the largest constructor of nuclear facilities in the USA. The proposed Isotope Facility will consist of a 3000 m 2 building adjacent to the reactor with a pneumatic radioisotope transfer system. Hot cells, process equipment and clean rooms will be provided, as well as the usual maintenance and support services required for processing radiopharmaceutical and industrial products. To ensure the highest standards of product purity the processing areas will be supplied with clean air and operated at slightly positive pressure. The radioisotopes to be manufactured include Phosphorus 32 (S-32 [n,p]P-32), I-131(Te-130 [n,g]Te-131[p]I-131) for bulk, diagnostic capsules and therapeutic capsules, Iridium 192 (Ir-191[n,g]Ir-192) wire for radiotherapy and discs for industrial radiography sources and bulk Iodine 125 (Xe-124[n,g]Xe-125[β]I-125 for radioimmunoassay. The bid includes proposals for training OAEP staff during design and development at ANSTO's radioisotope facilities, and during construction and commissioning in Thailand. The entire project is planned to take four years with commencement anticipated in early 1997. The paper will describe the development of the design of the hot-cells, process equipment, building layout and ventilation and other services

  17. Control of the technological processes at ''Azovstal'' plant using radioisotope devices

    Energy Technology Data Exchange (ETDEWEB)

    Nosochenko, O V; Overchenko, Z V; Karpov, O I; Deryabina, G N

    1980-05-01

    Considered is the state of radioisotope control of the technological process at 'Azovstal' plant which has permitted to increase the quality of metal and of metal production. With the help of radioisotope densimeter PR-1024 carried out is the control of the density of the lime solution used for hearth spraying at pig iron casting. A system of automatic correction of skip coke supply according to indications of moisture gauges ''Neutron 3-1'' is implemented at blast furnaces. A radioisotope thickness gauge of hot rolling is positioned on the section of finishing stand of thick-sheet plant, its operation is based on the ..gamma.. radiation weakening in dependence on sheet thickness. The introduction of thickness gauges in the automatized system of rolling control is planned. A radioisotope device ''Paza 2'' for measuring of continuous ingot skin thickness is tested successively at the plant. Gamma-relay devices are used to control the level of loose materials in bunkers. Noted is the prospects of using radioisotopic means of control and automatization of technological processes in ferrous matallurgy.

  18. Applications of radioisotopes in industry and healthcare in Vietnam

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  19. 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

  20. Comparison between Radioisotopic and Non-radioisotopic Polymerase Chain Reaction-Single Strand Conformation Polymorphism (PCR-SSCP) Procedures in the Detection of Mutations at the rpoB Gene Associated with Rifampicin Resistance in Mycobacterium tuberculosis

    International Nuclear Information System (INIS)

    Lee, H.; Bang, H.E.; Johnson, R.; Jordaan, A.M.; Victor, T.C. . E-mail : tv@sun.ac.za; Dar, L.; Khan, B.K.; Cho, S.N. . E-mail : raycho@yonsei.ac.kr

    2006-01-01

    Rapid and sensitive detection of mutations at the rpoB gene of Mycobacterium tuberculosis would be of great importance for proper management of tuberculosis (TB) patients and control of multi-drug resistant TB. Polymerase chain reaction-single strand conformation polymorphism (PCR-SSCP) using both radioisotopic and non-radioisotopic methods have been widely used for detecting such mutations. However, the silver staining method, which is the most frequently employed in PCR-SSCP, has been reported to be producing results of varying sensitivity. Radioisotope-based methods have shown greater sensitivity in detecting the rpoB mutations than the silver staining method. The primary objective of this study was therefore to compare the radioisotopic method with the silver staining method detection of mutations of rpoB gene by PCR-SSCP in the same laboratory. Purified DNAs from M. tuberculosis H37Rv were serially diluted and used for PCR amplification with and without radionuclides. The PCR products were then detected by silver staining and autoradiography methods. In addition, clinical isolates were analyzed by PCR-SSCP. The radioisotopic method showed about four-fold increase in the detection of PCR products over ethidium bromide staining in agarose gel. When compared with silver staining, the radioisotopic method gave a sensitivity of more than 10-fold in detecting PCR products and about 8-fold in PCR-SSCP. Radioisotope-based detection methods provided a clearer resolution in PCR-SSCP than the silver staining method when applied to clinical isolates of M. tuberculosis. Radioisotope-based detection method was shown to be more sensitive than non-isotope-based method in detecting PCR products and mutations at the rpoB gene of M. tuberculosis by PCR-SSCP. It may be noted that mutations in the rpoB gene as a marker have significant clinical importance because of the increasing number of MDR-TB cases in the world. It is especially relevant to MDR and Extreme Drug Resistance TB

  1. Rhenium radioisotopes for therapeutic radiopharmaceutical development

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  2. VirtualToxLab — A platform for estimating the toxic potential of drugs, chemicals and natural products

    International Nuclear Information System (INIS)

    Vedani, Angelo; Dobler, Max; Smieško, Martin

    2012-01-01

    The VirtualToxLab is an in silico technology for estimating the toxic potential (endocrine and metabolic disruption, some aspects of carcinogenicity and cardiotoxicity) of drugs, chemicals and natural products. The technology is based on an automated protocol that simulates and quantifies the binding of small molecules towards a series of proteins, known or suspected to trigger adverse effects. The toxic potential, a non-linear function ranging from 0.0 (none) to 1.0 (extreme), is derived from the individual binding affinities of a compound towards currently 16 target proteins: 10 nuclear receptors (androgen, estrogen α, estrogen β, glucocorticoid, liver X, mineralocorticoid, peroxisome proliferator-activated receptor γ, progesterone, thyroid α, and thyroid β), four members of the cytochrome P450 enzyme family (1A2, 2C9, 2D6, and 3A4), a cytosolic transcription factor (aryl hydrocarbon receptor) and a potassium ion channel (hERG). The interface to the technology allows building and uploading molecular structures, viewing and downloading results and, most importantly, rationalizing any prediction at the atomic level by interactively analyzing the binding mode of a compound with its target protein(s) in real-time 3D. The VirtualToxLab has been used to predict the toxic potential for over 2500 compounds: the results are posted on (http://www.virtualtoxlab.org). The free platform — the OpenVirtualToxLab — is accessible (in client–server mode) over the Internet. It is free of charge for universities, governmental agencies, regulatory bodies and non-profit organizations. -- Highlights: ► In silico technology for estimating the toxic potential of drugs and chemicals. ► Simulation of binding towards 16 proteins suspected to trigger adverse effects. ► Mechanistic interpretation and real-time 3D visualization. ► Accessible over the Internet. ► Free of charge for universities, governmental agencies, regulatory bodies and NPOs.

  3. VirtualToxLab — A platform for estimating the toxic potential of drugs, chemicals and natural products

    Energy Technology Data Exchange (ETDEWEB)

    Vedani, Angelo, E-mail: angelo.vedani@unibas.ch [Biographics Laboratory 3R, Klingelbergstrasse 50, 4056 Basel (Switzerland); Department of Pharmaceutical Sciences, University of Basel, Klingelbergstrasse 50, 4056 Basel (Switzerland); Dobler, Max [Biographics Laboratory 3R, Klingelbergstrasse 50, 4056 Basel (Switzerland); Smieško, Martin [Department of Pharmaceutical Sciences, University of Basel, Klingelbergstrasse 50, 4056 Basel (Switzerland)

    2012-06-01

    The VirtualToxLab is an in silico technology for estimating the toxic potential (endocrine and metabolic disruption, some aspects of carcinogenicity and cardiotoxicity) of drugs, chemicals and natural products. The technology is based on an automated protocol that simulates and quantifies the binding of small molecules towards a series of proteins, known or suspected to trigger adverse effects. The toxic potential, a non-linear function ranging from 0.0 (none) to 1.0 (extreme), is derived from the individual binding affinities of a compound towards currently 16 target proteins: 10 nuclear receptors (androgen, estrogen α, estrogen β, glucocorticoid, liver X, mineralocorticoid, peroxisome proliferator-activated receptor γ, progesterone, thyroid α, and thyroid β), four members of the cytochrome P450 enzyme family (1A2, 2C9, 2D6, and 3A4), a cytosolic transcription factor (aryl hydrocarbon receptor) and a potassium ion channel (hERG). The interface to the technology allows building and uploading molecular structures, viewing and downloading results and, most importantly, rationalizing any prediction at the atomic level by interactively analyzing the binding mode of a compound with its target protein(s) in real-time 3D. The VirtualToxLab has been used to predict the toxic potential for over 2500 compounds: the results are posted on (http://www.virtualtoxlab.org). The free platform — the OpenVirtualToxLab — is accessible (in client–server mode) over the Internet. It is free of charge for universities, governmental agencies, regulatory bodies and non-profit organizations. -- Highlights: ► In silico technology for estimating the toxic potential of drugs and chemicals. ► Simulation of binding towards 16 proteins suspected to trigger adverse effects. ► Mechanistic interpretation and real-time 3D visualization. ► Accessible over the Internet. ► Free of charge for universities, governmental agencies, regulatory bodies and NPOs.

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

    International Nuclear Information System (INIS)

    Zhou, Yong-Tian

    1986-01-01

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

  5. Out of lab calibration of a rotating 2D scanner for 3D mapping

    Science.gov (United States)

    Koch, Rainer; Böttcher, Lena; Jahrsdörfer, Maximilian; Maier, Johannes; Trommer, Malte; May, Stefan; Nüchter, Andreas

    2017-06-01

    Mapping is an essential task in mobile robotics. To fulfil advanced navigation and manipulation tasks a 3D representation of the environment is required. Applying stereo cameras or Time-of-flight cameras (TOF cameras) are one way to archive this requirement. Unfortunately, they suffer from drawbacks which makes it difficult to map properly. Therefore, costly 3D laser scanners are applied. An inexpensive way to build a 3D representation is to use a 2D laser scanner and rotate the scan plane around an additional axis. A 3D point cloud acquired with such a custom device consists of multiple 2D line scans. Therefore the scanner pose of each line scan need to be determined as well as parameters resulting from a calibration to generate a 3D point cloud. Using external sensor systems are a common method to determine these calibration parameters. This is costly and difficult when the robot needs to be calibrated outside the lab. Thus, this work presents a calibration method applied on a rotating 2D laser scanner. It uses a hardware setup to identify the required parameters for calibration. This hardware setup is light, small, and easy to transport. Hence, an out of lab calibration is possible. Additional a theoretical model was created to test the algorithm and analyse impact of the scanner accuracy. The hardware components of the 3D scanner system are an HOKUYO UTM-30LX-EW 2D laser scanner, a Dynamixel servo-motor, and a control unit. The calibration system consists of an hemisphere. In the inner of the hemisphere a circular plate is mounted. The algorithm needs to be provided with a dataset of a single rotation from the laser scanner. To achieve a proper calibration result the scanner needs to be located in the middle of the hemisphere. By means of geometric formulas the algorithms determine the individual deviations of the placed laser scanner. In order to minimize errors, the algorithm solves the formulas in an iterative process. First, the calibration algorithm was

  6. Determination of Lactic Acid Bacteria Viability in the Small Intestine of Catfish (Pangasius djambal by Using the 32P Radioisotope

    Directory of Open Access Journals (Sweden)

    I. Sugoro

    2015-10-01

    Full Text Available The viability of probiotics is important to be determined, as is its probiotic potency in the small instestine of fish. The result can be used as a basis to determine the feeding frequency of the probiotics to the fish.The aim of this study is to gain information about the viability of lactic acid bacteria (LAB in the small intestine of fish by using the 32P isotope technique. Catfish (Pangasius djambal was used as a test fish, and the LAB with the code of P2.1 PTB was the subject of the experiment. Before its viability was tested, the LAB had been labelled with radioisotope 32P, then mixed into catfish feed. Its viability could be determined by counting the activity of 32P. The results showed that the percentage of LAB viability in the small intestine of catfish declined until day 7. The percentage of LAB viability was decreased at an amount of 30% at day 3. Based on this result, the feeding frequency of LAB P2.1 PTB is every 3 days. Received: 04 October 2014 Revised: 26 March 2015; Accepted: 05 April 2015

  7. Small radioisotope powered batteries

    International Nuclear Information System (INIS)

    Myatt, J.

    1975-06-01

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

  8. Symposium on isotope production and applications

    International Nuclear Information System (INIS)

    1981-01-01

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

  9. Radioisotope application to studies of copper electrolytic refining

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  10. Exploring linear algebra labs and projects with Mathematica

    CERN Document Server

    Arangala, Crista

    2014-01-01

    Matrix Operations Lab 0: An Introduction to Mathematica Lab 1: Matrix Basics and Operations Lab 2: A Matrix Representation of Linear Systems Lab 3: Powers, Inverses, and Special Matrices Lab 4: Graph Theory and Adjacency Matrices Lab 5: Permutations and Determinants Lab 6: 4 x 4 Determinants and Beyond Project Set 1 Invertibility Lab 7: Singular or Nonsingular? Why Singularity Matters Lab 8: Mod It Out, Matrices with Entries in ZpLab 9: It's a Complex World Lab 10: Declaring Independence: Is It Linear? Project Set 2 Vector Spaces Lab 11: Vector Spaces and SubspacesLab 12: Basing It All on Just a Few Vectors Lab 13: Linear Transformations Lab 14: Eigenvalues and Eigenspaces Lab 15: Markov Chains, An Application of Eigenvalues Project Set 3 Orthogonality Lab 16: Inner Product Spaces Lab 17: The Geometry of Vector and Inner Product SpacesLab 18: Orthogonal Matrices, QR Decomposition, and Least Squares Regression Lab 19: Symmetric Matrices and Quadratic Forms Project Set 4 Matrix Decomposition with Applications L...

  11. A Role-Playing Game for a Software Engineering Lab: Developing a Product Line

    Science.gov (United States)

    Zuppiroli, Sara; Ciancarini, Paolo; Gabbrielli, Maurizio

    2012-01-01

    Software product line development refers to software engineering practices and techniques for creating families of similar software systems from a basic set of reusable components, called shared assets. Teaching how to deal with software product lines in a university lab course is a challenging task, because there are several practical issues that…

  12. Radioisotope Sources of Electric Power

    Science.gov (United States)

    1973-09-20

    u) watt/cm-3 O) specific activity f) curia/watt (curie/a) a) half-life c) specific power output h) years (capacity) 1) days d) watt/p Polonium - 210 ...AD/A-001 210 RADIOISOTOPE SOURCES OF ELECTRIC POWER G. M. Fradkin, et al Army Foreign Science and Technology Center Charlottesville, Virginia 20...narticularlv for nurninn and irocess~ino of wastg.Sheatinc food , conversion of liruld oxtoner to des, and also for removal of imnurities and reula:tion

  13. Measurement of Scientific Productivity in R&D Sector: Changing paradigm.

    Science.gov (United States)

    Kumar, Abhishek; Srivastava, Alpana; Kumar, R P Jeevan; Tiwari, Rajesh K

    2017-01-01

    Scientific Productivity is a demand of policy makers for a judicious utilization of massive R&D budget allocated and utilized. A huge mass of intellectual assets is employed, which after investing manpower, infrastructure and lab consumables demand for a major outcome which contributes towards building nation's economy. Scientific productivity was only measured through publications or patents. Patents, earmarked as a strong parameter for innovation generation, where, Word Intellectual Property Organisation generated a data on applications for the top 20 offices for patents, where Australia, Brazil and Canada occupied top 3 positions. India ranked 9th with the total patent applications rising from 39762 (2010) to 42854 (2014) i.e. 15%, whereas, it contributes around 2% Patents (innovative productivity) on global scale. Many studies have come forward interestingly within scientific and academic domains in the form of measurement of scientific performance, however, development of productivity indicators and calculation of Scientific Productivity (SP) as a holistic evaluation system is a significant demand. SP, a herculean task is envisaged for productivity analysis and would submit significant factors towards fabricating an effective measurement engine in a holistic manner viable for an individual and organization, being supplementary to each other. This review projects the significance of performance measurement system in R&D through identification and standardization of key parameters. It also includes emphasis on inclusion of standardized parameters, effective for performance measurement which is applicable for scientists, technical staff as well as lab as a facility. This review aims at providing an insight to the evaluators, policy makers, and high level scientific panels to stimulate the scientific intellects on identified indicators so that their work proceeds to generate productive outcome contributing to the economic growth. Copyright© Bentham Science

  14. New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Butler, T A; Lamb, E; Rupp, A F [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-01-15

    Recent developments in the radioisotope production programme at Oak Ridge National Laboratory include new processes and process improvements for the production of cerium-144, promethium-147, technetium-99 and strontium-90. Cerium-144 has been produced in kc quantities in a test run. A product recovery of more than 98% with a product purity of more than 99% was attained. The cerium was further processed to obtain pure cerium-144 oxide powder having an activity concentration of 235 c/g. The powder was pressed into pellets which were sintered to a dense ceramic form. Promethium-147 has been produced in kc quantities by a combination of precipitation and ion exchange techniques. A solvent extraction system for separating promethium- 147 from other rare earths has been tested on a tracer scale. Gram quantities of technetium-99 have been recovered from fission-product waste streams by a combination of precipitation and solvent extraction processes. The technetium product was produced with a chemical purity of more than 99.9% and radiochemical purity of more than 99.99%. The separation and purification of strontium-90 from gross contaminants by a continuous solvent-extraction flowsheet has been demonstrated on a tracer scale. Product quality of 98% strontium has been achieved from feed containing 95% inert calcium contaminant. The strontium-90 is further processed to form strontium titanate ceramic elements. (author) [French] Les faits recents a noter dans le programme de production de radioisotopes du laboratoire national d'Oak Ridge sont l'introduction de nouvelles methodes et l'amelioration des techniques existantes pour la production du eerium-144, du prometheum-147, du technetium-99 et du strontium-90. Le cerium-144 a ete obtenu en quantites de l'ordre du kilocurie, lors d'une experience. On a obtenu un taux d'extraction de plus de 98% et un produit d'une purete superieure a 99%. On a ensuite traite le cerium pour avoir de l'oxyde de cerium-144 pur en poudre ayant

  15. Medical radioisotopes for the next century

    International Nuclear Information System (INIS)

    Carr, S.W.

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

    2002-04-01

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

  17. Radioisotopes in industry

    International Nuclear Information System (INIS)

    Popple, B.N.

    1977-01-01

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

  18. Radioisotope requirements and usage in the radiopharmaceutical industry

    International Nuclear Information System (INIS)

    Langton, M.A.

    1995-01-01

    Radioisotopes are used extensively in many different productive and beneficial human endeavors. Amersham International, a U.K.-based company originating in the British Scientific Civil Service during World War II, has been actively involved in many of these activities for more than 50 yr. Today they are one of the world's largest suppliers of radioactive compounds and scaled radiation sources for use in industrial quality and safety assurance, life science research, and medicine. This paper outlines one of these applications: the use of radioisotopes as radiopharmaceuticals. Radiopharmaceuticals are radioactive nuclides and labeled compounds that have been developed for the diagnosis and treatment of (human) disease. They are manufactured via highly controlled processes and have gone through regulatory scrutiny and approval far in excess of other radioisotopes used in other applications. Radiopharmaceuticals can be conveniently split into two categories. One type is simply an active analog that mimics the physiological behavior of its inactive counterpart in the body. The other involves an actual pharmacological compound that exhibits the desired physiological behavior, which is then labeled with a radionuclide suitable for either imaging or the delivery of a therapeutic radiation dose as appropriate but which plays no part in the mechanism of action of the drug. The latter type, which is the more common of the two, can be supplied either as an active compounded product or as a open-quotes cold kit,close quotes which is then labeled with the appropriate radiopharmaceutical-grade radionuclide to yield the final product

  19. Radioisotope applications on fluidized catalytic cracking units

    International Nuclear Information System (INIS)

    Charlton, J.S.

    1997-01-01

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

  20. Americium-241 radioisotope thermoelectric generator development for space applications

    International Nuclear Information System (INIS)

    Ambrosi, Richard; Williams, Hugo; Samara-Ratna, Piyal

    2013-01-01

    Space nuclear power systems are under development in the UK in collaboration with European partners as part of a European Space Agency (ESA) programme. Radioisotope thermoelectric generators (RTG) are an important element of this new capability in Europe. RTG systems being developed in Europe are targeting the 10 W electric to 50 W electric power generation range adopting a modular scalable approach to the design. Radiogenic decay heat from radioisotopes can be converted to electrical power by using appropriate semiconductor based thermoelectric materials. The plan for Europe is to develop radioisotope space nuclear power systems based on both thermoelectric and Stirling power conversion systems. Although primarily focused on delivering up to 50 W of electrical power, the European radioisotope thermoelectric system development programme is targeting americium-241 as a fuel source and is maximizing the use of commercially available thermoelectric manufacturing processes in order to accelerate the development of power conversion systems. The use of americium provides an economic solution at high isotopic purity and is product of a separation process from stored plutonium produced during the reprocessing of civil nuclear fuel. A laboratory prototype that uses electrical heating as a substitute for the radioisotope was developed to validate the designs. This prototype has now been tested. This paper outlines the requirements for a European americium-241 fuelled RTG, describes the most recent updates in system design and provides further insight into recent laboratory prototype test campaigns. (author)

  1. Americium-241 radioisotope thermoelectric generator development for space applications

    Energy Technology Data Exchange (ETDEWEB)

    Ambrosi, Richard; Williams, Hugo; Samara-Ratna, Piyal, E-mail: rma8@le.ac.uk [University of Leicester, (United Kingdom); and others

    2013-07-01

    Space nuclear power systems are under development in the UK in collaboration with European partners as part of a European Space Agency (ESA) programme. Radioisotope thermoelectric generators (RTG) are an important element of this new capability in Europe. RTG systems being developed in Europe are targeting the 10 W electric to 50 W electric power generation range adopting a modular scalable approach to the design. Radiogenic decay heat from radioisotopes can be converted to electrical power by using appropriate semiconductor based thermoelectric materials. The plan for Europe is to develop radioisotope space nuclear power systems based on both thermoelectric and Stirling power conversion systems. Although primarily focused on delivering up to 50 W of electrical power, the European radioisotope thermoelectric system development programme is targeting americium-241 as a fuel source and is maximizing the use of commercially available thermoelectric manufacturing processes in order to accelerate the development of power conversion systems. The use of americium provides an economic solution at high isotopic purity and is product of a separation process from stored plutonium produced during the reprocessing of civil nuclear fuel. A laboratory prototype that uses electrical heating as a substitute for the radioisotope was developed to validate the designs. This prototype has now been tested. This paper outlines the requirements for a European americium-241 fuelled RTG, describes the most recent updates in system design and provides further insight into recent laboratory prototype test campaigns. (author)

  2. 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.

  3. 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.

  4. 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.

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

    International Nuclear Information System (INIS)

    Sivaramakrishnan, S.; Seetharama, N.; Kannan, Seetha

    2001-01-01

    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)

  6. Stabilization and shutdown of Oak Ridge National Laboratory's Radioisotopes Production Facility

    International Nuclear Information System (INIS)

    Eversole, R.E.

    1992-01-01

    The Oak Ridge National Laboratory (ORNL) has been involved in the production and distribution of a variety of radioisotopes for medical, scientific and industrial applications since the late 1940s. Production of these materials was concentrated in a number of facilities primarily built in the 1950s and 1960s. Due to the age and deteriorating condition of these facilities, it was determined in 1989 that it would not be cost effective to upgrade these facilities to bring them into compliance with contemporary environmental, safety and health standards. The US Department of Energy (DOE) instructed ORNL to halt the production of isotopes in these facilities and maintain the facilities in safe standby condition while preparing a stabilization and shutdown plan. The goal was to place the former isotope production facilities in a radiologically and industrially safe condition to allow a 5-year deferral of the initiation of environmental restoration (ER) activities. In response to DOE's instructions, ORNL identified 17 facilities for shutdown, addressed the shutdown requirements for each facility, and prepared and implemented a three-phase, 4-year plan for shutdown of the facilities. The Isotopes Facilities Shutdown Program (IFSP) office was created to execute the stabilization and shutdown plan. The program is entering its third year in which the actual shutdown of the facilities is initiated. Accomplishments to date have included consolidation of all isotopes inventory into one facility, DOE approval of the IFSP Environmental Assessment (EA), and implementation of a detailed management plan for the shutdown of the facilities

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

    International Nuclear Information System (INIS)

    Forughi, Sh.; Hamidi, S.; Khalafi, H.; Sheibani, Sh.; Shahidi, A.

    2013-01-01

    Highlights: ► Production of 153 Sm 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 153 Sm 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 153 Sm by irradiation of 152 Sm in 5 MW TRR was studied via TRR core simulation. In this study the cross-section of 152 Sm (n,γ) 153 Sm reaction from ENDF/B library was used. The effective activation cross section for production of 153 Sm 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 (K f ) was obtained, which is helpful in production procedure of the 153 Sm 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 Sm 2 O 3 is acceptable for the labeling, therefore this study led to nearly 60% decrease in the amount of material used in the production process

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

    International Nuclear Information System (INIS)

    Simmons, J.L.; Mandell, S.

    1974-01-01

    The eleventh edition of the AEC radioisotope customer list has been prepared at the request of the Division of Biomedical and Environmental Research. The purpose of this document is to list the FY 1974 commercial radioisotope production and distribution activities of USAEC facilities at Argonne National Laboratory, Battelle, Pacific Northwest Laboratories, Brookhaven National Laboratory, United Nuclear Inc., Idaho Operations Office, Hanford Engineering Development Laboratory, Mound Laboratory, Oak Ridge National Laboratory, and Savannah River Plant. The information is divided into four sections. Section I is an alphabetical list of domestic and foreign customers and their addresses. Each customer has been designated a number according to its alphabetical position which provides a means of cross-referencing in the following sections. The isotopes purchased are listed after the address of the customer and the laboratory supplying each isotope is indicated by a letter set off by parentheses. Section II is an alphabetical list of isotopes, cross-referenced to customer numbers and again divided into the domestic and foreign categories. This section provides a quick idea of the amount of companies purchasing a particular isotope. If more information is needed, the reader can locate the customer by number and determine the laboratory supplying the isotope. The third section is an alphabetical list of states and countries, also cross-referenced to customer numbers, indicating geographical concentrations of isotope users. Section IV summarizes the FY 1974 radioisotope shipment activities of USAEC laboratories in a comprehensive table providing an alphabetical listing of the isotopes and their suppliers. The shipments, quantities and dollars are broken down for each isotope under the Domestic, Foreign, and Project (AEC facilities) categories, and the total figures for each isotope are also provided. (U.S.)

  9. Radioisotope techniques for process optimisation and control in the offshore oil and gas industries

    International Nuclear Information System (INIS)

    Charlton, J.S.

    2002-01-01

    For over fifty years, radioisotope technology has been used by the oil industry to solve problems and to help optimise process operations. The widespread development of offshore oil and gas fields has brought, and continues to bring, new challenges and, in response, new or modified applications of radioisotope technology have been introduced. This paper presents case studies, which illustrate the use of radioisotopes, both in the sub-sea environment and on the offshore production platforms. On the platform, radioisotope techniques applied singly or in combination, have been applied to the performance assessment of oil/gas separation and gas dehydration units. Novel nucleonic instrumentation has been developed for the control of three-phase separators. Sub-sea, radioactive tracers and/or sealed sources have been used to investigate the integrity of submerged structures and to troubleshoot pipeline problems. The continuing expansion in the use of this technology stems from industry increasing awareness of its versatility and from the fact that the benefits it confers can be obtained at a relatively modest cost. Examples of economic benefit described in the paper are associated with production enhancements derived from the ability of radioisotope technology to measure performance and diagnose problems on line, without disrupting process operations in any way. (Author)

  10. Radioactive wastes from Angra-1 plant and radioisotope production to medical and industrial uses

    International Nuclear Information System (INIS)

    Meldonian, Nelson L.; Mattos, Luis A.T. de

    1997-01-01

    Based on false premises, critics point of view have frequently lead part of Brazilian public opinion to impeach the validity of nuclear energy applications.The critics allege that social implications discredit those applications. In this context, treated as if not known theirs diverse characteristics, great noise has been created about radioactive wastes related to diverse nuclear industry processes. Due to the great misunderstanding on the subject, this paper presents the characteristics and destinations of radioactive wastes related to nucleoelectric generation and to radioisotopes production in Brazil. Even so someone could point out that those characteristics are diverse, we discuss in a comparative way the benefits of those two kinds of nuclear applications. (author). 5 refs., 6 tabs

  11. Appraisal of within- and between-laboratory reproducibility of non-radioisotopic local lymph node assay using flow cytometry, LLNA:BrdU-FCM: comparison of OECD TG429 performance standard and statistical evaluation.

    Science.gov (United States)

    Yang, Hyeri; Na, Jihye; Jang, Won-Hee; Jung, Mi-Sook; Jeon, Jun-Young; Heo, Yong; Yeo, Kyung-Wook; Jo, Ji-Hoon; Lim, Kyung-Min; Bae, SeungJin

    2015-05-05

    Mouse local lymph node assay (LLNA, OECD TG429) is an alternative test replacing conventional guinea pig tests (OECD TG406) for the skin sensitization test but the use of a radioisotopic agent, (3)H-thymidine, deters its active dissemination. New non-radioisotopic LLNA, LLNA:BrdU-FCM employs a non-radioisotopic analog, 5-bromo-2'-deoxyuridine (BrdU) and flow cytometry. For an analogous method, OECD TG429 performance standard (PS) advises that two reference compounds be tested repeatedly and ECt(threshold) values obtained must fall within acceptable ranges to prove within- and between-laboratory reproducibility. However, this criteria is somewhat arbitrary and sample size of ECt is less than 5, raising concerns about insufficient reliability. Here, we explored various statistical methods to evaluate the reproducibility of LLNA:BrdU-FCM with stimulation index (SI), the raw data for ECt calculation, produced from 3 laboratories. Descriptive statistics along with graphical representation of SI was presented. For inferential statistics, parametric and non-parametric methods were applied to test the reproducibility of SI of a concurrent positive control and the robustness of results were investigated. Descriptive statistics and graphical representation of SI alone could illustrate the within- and between-laboratory reproducibility. Inferential statistics employing parametric and nonparametric methods drew similar conclusion. While all labs passed within- and between-laboratory reproducibility criteria given by OECD TG429 PS based on ECt values, statistical evaluation based on SI values showed that only two labs succeeded in achieving within-laboratory reproducibility. For those two labs that satisfied the within-lab reproducibility, between-laboratory reproducibility could be also attained based on inferential as well as descriptive statistics. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

  12. Role of radioisotopes in the study of insect pests

    International Nuclear Information System (INIS)

    Mansour, M.

    2013-01-01

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

  13. OpenLabNotes

    DEFF Research Database (Denmark)

    List, Markus; Franz, Michael; Tan, Qihua

    2015-01-01

    be advantageous if an ELN was Integrated with a laboratory information management system to allow for a comprehensive documentation of experimental work including the location of samples that were used in a particular experiment. Here, we present OpenLabNotes, which adds state-of-the-art ELN capabilities to Open......LabFramework, a powerful and flexible laboratory information management system. In contrast to comparable solutions, it allows to protect the intellectual property of its users by offering data protection with digital signatures. OpenLabNotes effectively Closes the gap between research documentation and sample management......, thus making Open-Lab Framework more attractive for laboratories that seek to increase productivity through electronic data management....

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  15. Recent developments in radiation equipment and radioisotopes

    International Nuclear Information System (INIS)

    Beddoes, J.M.

    1978-09-01

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

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

    International Nuclear Information System (INIS)

    Ibrahim Ijang; Zakaria Ibrahim; Bohari Yaacob

    2013-01-01

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

  17. Radioisotope Power Supply, Phase I

    Data.gov (United States)

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

  18. Medical research with radioisotopes in Greece

    Energy Technology Data Exchange (ETDEWEB)

    Belcher, E H [Post-graduate Medical School, Hammersmith, London (United Kingdom)

    1961-07-15

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

  19. Survey of industrial radioisotope savings

    International Nuclear Information System (INIS)

    1965-01-01

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

  20. Radioisotope detection and dating with accelerators

    Energy Technology Data Exchange (ETDEWEB)

    Mast, T S; Muller, R A [California Univ., Berkeley (USA). Lawrence Berkeley Lab.

    1980-07-01

    The status of the new technique of high energy mass spectrometry is reviewed. This sensitive method of measuring isotope concentrations has been applied to the detection of rare radioisotopes used for age estimation. The techniques used to select and identify the individual radioisotope atoms in a sample are described and then the status of the radioisotope measurements and their applications is reviewed.

  1. B cell increases and ex vivo IL-2 production as secondary endpoints for the detection of sensitizers in non-radioisotopic local lymph node assay using flow cytometry.

    Science.gov (United States)

    Jung, Kyoung-Mi; Jang, Won-Hee; Lee, Yong-Kyoung; Yum, Young Na; Sohn, Soojung; Kim, Bae-Hwan; Chung, Jin-Ho; Park, Young-Ho; Lim, Kyung-Min

    2012-03-25

    Non-radioisotopic local lymph node assay (LLNA) using 5-bromo-2'-deoxyuridine (BrdU) with flow cytometry (FCM) is gaining attention since it is free from the regulatory issues in traditional LLNA (tLLNA) accompanying in vivo uses of radioisotope, (3)H-thymidine. However, there is also concern over compromised performance of non-radioisotopic LLNA, raising needs for additional endpoints to improve the accuracy. With the full 22 reference substances enlisted in OECD Test Guideline No. 429, we evaluated the performance of LLNA:BrdU-FCM along with the concomitant measurements of B/T cell ratio and ex vivo cytokine production from isolated lymph node cells (LNCs) to examine the utility of these markers as secondary endpoints. Mice (Balb/c, female) were topically treated with substances on both ears for 3 days and then, BrdU was intraperitoneally injected on day 5. After a day, lymph nodes were isolated and undergone FCM to determine BrdU incorporation and B/T cell sub-typing with B220+ and CD3e+. Ex vivo cytokine production by LNCs was measured such as IL-2, IL-4, IL-6, IL-12, IFN-γ, MCP-1, GM-CSF and TNFα. Mice treated with sensitizers showed preferential increases in B cell population and the selective production of IL-2, which matched well with the increases in BrdU incorporation. When compared with guinea pig or human data, BrdU incorporation, B cell increase and IL-2 production ex vivo could successfully identify sensitizers with the accuracy comparable to tLLNA, suggesting that these markers may be useful for improving the accuracy of LLNA:BrdU-FCM or as stand-alone non-radioisotopic endpoints. Copyright © 2012 Elsevier Ireland Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

    2012-01-01

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

  3. Licensing of digital Instrumentation and Control in Radioisotope Production Facility

    International Nuclear Information System (INIS)

    Abdel-Aziz, L.Kh.; Lashin, R.; Mostafa, W.

    2012-01-01

    In spite of the rapid development of digital I and C systems in all major industries, it has for several reasons been slower in nuclear power plants. The most important reason is that only a few new plants have been ordered worldwide during the last ten years. A second reason is connected to the efforts needed in providing adequate evidence that the digital I and C system can be used in safety and safety related applications. This issue is connected to the effort needed in obtaining adequate assurance that the digital I and C will fulfill its intended function and contain no unintended function in all possible operational states during its entire life cycle. This paper presents an acceptance criteria for licensing a digital instrumentation and control system in a Radioisotope Production Facility(1), which is under commissioning. The acceptance criteria ensure that the I and C systems are designed to reach the highest degree of reliability with respect to the function they perform, operators will have clear and accessible availability to data on every plant parameter, and also ensure that the safety objectives have been covered

  4. Relating lab to life: Decrements in attention over time predict math productivity among children with ADHD.

    Science.gov (United States)

    Fosco, Whitney D; Hawk, Larry W

    2017-02-01

    A child's ability to sustain attention over time (AOT) is critical in attention-deficit/hyperactivity disorder (ADHD), yet no prior work has examined the extent to which a child's decrement in AOT on laboratory tasks relates to clinically-relevant behavior. The goal of this study is to provide initial evidence for the criterion validity of laboratory assessments of AOT. A total of 20 children with ADHD (7-12 years of age) who were enrolled in a summer treatment program completed two lab attention tasks (a continuous performance task and a self-paced choice discrimination task) and math seatwork. Analyses focused on relations between attention task parameters and math productivity. Individual differences in overall attention (OA) measures (averaged across time) accounted for 23% of the variance in math productivity, supporting the criterion validity of lab measures of attention. The criterion validity was enhanced by consideration of changes in AOT. Performance on all laboratory attention measures deteriorated as time-on-task increased, and individual differences in the decrement in AOT accounted for 40% of the variance in math productivity. The only variable to uniquely predict math productivity was from the self-paced choice discrimination task. This study suggests that attention tasks in the lab do predict a clinically-relevant target behavior in children with ADHD, supporting their use as a means to study attention processes in a controlled environment. Furthermore, this prediction is improved when attention is examined as a function of time-on-task and when the attentional demands are consistent between lab and life contexts.

  5. Exploring the Potential of a German Living Lab Research Infrastructure for the Development of Low Resource Products and Services

    Directory of Open Access Journals (Sweden)

    Justus von Geibler

    2014-09-01

    Full Text Available Living Labs for Sustainable Development aim to integrate users and actors for the successful generation of low-resource innovations in production-consumption systems. This paper investigates potentials of and measures towards the realization of a German Living Lab infrastructure to support actor-integrated sustainability research and innovations in Germany. Information was primarily derived from extensive dialog with experts from the fields of innovation, sustainable development and the Living Lab community (operators, users, etc., which was facilitated through interviews and workshops. A status quo analysis revealed that, generally, the sustainability and Living Lab communities are hardly intertwined. Twelve Living Labs that explicitly consider sustainability aspects were identified. The application fields “Living and Working”, “Town, Region and Mobility”, and “Retail and Gastronomy” were identified as particularly suitable for investigation in Living Labs and highly relevant in terms of resource efficiency. Based on the analyses of drivers and barriers and SWOT, keystones for the development of a research infrastructure for user integrated development of sustainable products and services were formulated. Suggested strategies and measures include targeted funding programs for actor-integrated, socio-technical research based on a Living Lab network, a communication campaign, and programs to foster networking and the inclusion of SMEs.

  6. Characterization of contaminated nuclear sites, facilities and materials: radioisotope and radiopharmaceutical manufacturers and suppliers. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    The Environmental Protection Agency (EPA) is developing environmental protection standards for evaluating the risks and characterizing problems associated with disposal of radioactive wastes arising from decontamination and decommissioning DandD operations. Information on operations conducted at sites authorized to possess radioactive materials for the production and/or distribution of radioisotopes and radiopharmaceuticals was compiled and evaluated. This information was used to project the types, nature, and volumes of wastes which are likely to be generated during decontamination and decommissioning at representative facilities and identifying special problems that may occur. Radioisotope and radiopharmaceutical manufacturers have been grouped together because decommissioning operations will be similar. Nuclear pharmacies were also evaluated because of their increasing numbers and their role as middlemen between manufacturers and users of radiopharmaceuticals. The majority of the radioactive waste will arise from the decontamination of the laboratories, rather than the disposal of components

  7. Support housing for radioisotope generation

    International Nuclear Information System (INIS)

    Fries, B.A.

    1976-01-01

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

  8. FameLab Switzerland: a CERN PhD student triumphs

    CERN Multimedia

    Alexander Brown

    2013-01-01

    Would you be able to explain your work to a non-specialist in just three minutes? On Friday 24 May, the Swiss national final of FameLab saw six young researchers from CERN attempt just that. FameLab is an international competition in the style of a TV talent show, seeking out the next generation of talent in science communication.   Participants in the Swiss national final of FameLab alongside Deni Subasic, presenter of the event (far left), on Friday 24 May. Having qualified from the Geneva heat held in the Globe in March, the six CERN representatives took to the stage in Moods bar in Zurich. As well as particle physics, from the fundamental building blocks (literally) of the Standard Model to medical applications, the line-up featured immunology, neurology and genetics. Although slideshows are strictly banned from FameLab, other visual props are strongly encouraged. For instance, Piotr Traczyk (CMS) represented the apparent chaos of particle collisions by throwing together two decks of ca...

  9. Modular Stirling Radioisotope Generator

    Science.gov (United States)

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

    2016-01-01

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

  10. Cassandra - WP400 - final report of living lab 2

    NARCIS (Netherlands)

    Engler, M.; Klievink, A.J.

    2014-01-01

    This CASSANDRA LL2 final deliverable contains all information regarding the CASSANDRA Living Lab Europe – USA via Bremerhaven including information from two intermediate reports (CASSANDRA D4.21 and D4.22) about the very same Living Lab handed in during runtime of the Living Lab. CASSANDRA Living

  11. INSA Virtual Labs: a new R+D framework for innovative space science and technology

    Science.gov (United States)

    Cardesin Moinelo, Alejandro; Sanchez Portal, Miguel

    2012-10-01

    The company INSA (Ingeniería y Servicios Aeroespaciales) has given support to ESA Scientific missions for more than 20 years and is one of the main companies present in the European Space Astronomy Centre (ESAC) in Madrid since its creation. INSA personnel at ESAC provide high level technical and scientific support to ESA for all Astronomy and Solar System missions. In order to improve and maintain the scientific and technical competences among the employees, a research group has been created with the name "INSA Virtual Labs". This group coordinates all the R+D activities carried out by INSA personnel at ESAC and aims to establish collaborations and improve synergies with other research groups, institutes and universities. This represents a great means to improve the visibility of these activities towards the scientific community and serves as breeding ground for new innovative ideas and future commercial products.

  12. Analysis of status of radiation/radioisotopes utilization

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-15

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

  13. Analysis of status of radiation/radioisotopes utilization

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  14. 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)

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

    Science.gov (United States)

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

    1990-11-01

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

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

    International Nuclear Information System (INIS)

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

    1990-11-01

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

  17. 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.

  18. Management of radioactive wastes arising from the use of Australian radioisotopes

    International Nuclear Information System (INIS)

    Costello, J.M.

    1986-01-01

    The medical, industrial and research use of radioisotopes in Australia has given rise to approximately 30 m 3 of solid radioactive waste containing about 5 TBq of radioactivity. This waste is stored at State hospitals, universities and research centres. A further 10 m 3 of waste containing 300 GBq of radioactivity is stored by the Commonwealth at the St Mary's Munitions Filling factory. About 700 m 3 of waste containing 1.5 PBq of radioactivity resulting from operation of the HIFAR nuclear reactor and the production of radioisotopes is in storage at the Lucas Heights Research Establishment. The source, nature and rate of arising of these wastes is reviewed, together with national developments in waste classification, storage procedures and eventual disposal. Some research at Lucas Heights on the conditioning of radioisotope waste to facilitate disposal is briefly noted

  19. Radioisotopes in the treatment of cancer

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-01-15

    Radiation treatment of malignant growths is not, of course, a novel procedure; both radium implants and X-rays generated at medium voltages (up to 250 kV) have been used all over the world for many years. However, large scale production of radioisotopes in atomic reactors has made radiotherapy available for the first time in less developed areas of the world. Moreover, the treatment has been simplified and, in many cases, made more effective

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

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the regulation for the execution of the law on the prevention of radiation injuries by radioisotopes. Terms are used in this rule for the same meanings as in the regulation. The concentration of radioisotopes to which the technical standards for transport outside enterprises are not applied is 0.002 micro-curie per gram. The radioisotopes which can be transported as L type transported goods are defined in detail, excluding explosive or spontaneously igniting radioisotopes. The quantity limit of radioisotopes which can be transported as A type transported goods is the values A 1 and A 2 defined in this rule. The permissible surface density defined by the Director General of the Science and Technology Agency are 1/100,000 micro-curie per cm 2 for the radioisotopes emitting alpha-ray, and 1/10,000 micro-curie per cm 2 for the radioisotopes which do not emit alpha-ray. The leak quantity of radioisotopes specified by the Director General is 1/1,000,000 of A 2 value for BM type transported goods and 1/1,000 of A 2 value for BU type goods. The test conditions for each type of transported goods, dangerous goods, the limit of the number of transported goods and signs are stipulated, respectively. Permissible exposure dose is 1.5 rem a year for persons other than radiation workers. (Okada, K.)

  1. Designing Viable Business Models for Living Labs

    Directory of Open Access Journals (Sweden)

    Bernhard R. Katzy

    2012-09-01

    Full Text Available Over 300 regions have integrated the concept of living labs into their economic development strategy since 2006, when the former Finnish Prime Minister Esko Aho launched the living lab innovation policy initiative during his term of European presidency. Despite motivating initial results, however, success cases of turning research into usable new products and services remain few and uncertainty remains on what living labs actually do and contribute. This practitioner-oriented article presents a business excellence model that shows processes of idea creation and team mobilization, new product development, user involvement, and entrepreneurship through which living labs deliver high-potential investment opportunities. Customers of living labs are identified as investors such as venture capitalists or industrial firms because living labs can generate revenue from them to create their own sustainable business model. The article concludes that living labs provide extensive support “lab” infrastructure and that it remains a formidable challenge to finance it, which calls for a more intensive debate.

  2. The safe handling of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-12-31

    A narrative account of a minor contamination accident in a laboratory is used to demonstrate the important role of radiation protection measures in radioisotope work and the necessity of giving proper regard to such measures. It is primarily directed towards the research scientists and medical workers using radioisotopes on a relatively small scale

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  4. Interactive reconstructions of cranial 3D implants under MeVisLab as an alternative to commercial planning software.

    Directory of Open Access Journals (Sweden)

    Jan Egger

    Full Text Available In this publication, the interactive planning and reconstruction of cranial 3D Implants under the medical prototyping platform MeVisLab as alternative to commercial planning software is introduced. In doing so, a MeVisLab prototype consisting of a customized data-flow network and an own C++ module was set up. As a result, the Computer-Aided Design (CAD software prototype guides a user through the whole workflow to generate an implant. Therefore, the workflow begins with loading and mirroring the patients head for an initial curvature of the implant. Then, the user can perform an additional Laplacian smoothing, followed by a Delaunay triangulation. The result is an aesthetic looking and well-fitting 3D implant, which can be stored in a CAD file format, e.g. STereoLithography (STL, for 3D printing. The 3D printed implant can finally be used for an in-depth pre-surgical evaluation or even as a real implant for the patient. In a nutshell, our research and development shows that a customized MeVisLab software prototype can be used as an alternative to complex commercial planning software, which may also not be available in every clinic. Finally, not to conform ourselves directly to available commercial software and look for other options that might improve the workflow.

  5. Interactive reconstructions of cranial 3D implants under MeVisLab as an alternative to commercial planning software

    Science.gov (United States)

    Egger, Jan; Gall, Markus; Tax, Alois; Ücal, Muammer; Zefferer, Ulrike; Li, Xing; von Campe, Gord; Schäfer, Ute; Schmalstieg, Dieter; Chen, Xiaojun

    2017-01-01

    In this publication, the interactive planning and reconstruction of cranial 3D Implants under the medical prototyping platform MeVisLab as alternative to commercial planning software is introduced. In doing so, a MeVisLab prototype consisting of a customized data-flow network and an own C++ module was set up. As a result, the Computer-Aided Design (CAD) software prototype guides a user through the whole workflow to generate an implant. Therefore, the workflow begins with loading and mirroring the patients head for an initial curvature of the implant. Then, the user can perform an additional Laplacian smoothing, followed by a Delaunay triangulation. The result is an aesthetic looking and well-fitting 3D implant, which can be stored in a CAD file format, e.g. STereoLithography (STL), for 3D printing. The 3D printed implant can finally be used for an in-depth pre-surgical evaluation or even as a real implant for the patient. In a nutshell, our research and development shows that a customized MeVisLab software prototype can be used as an alternative to complex commercial planning software, which may also not be available in every clinic. Finally, not to conform ourselves directly to available commercial software and look for other options that might improve the workflow. PMID:28264062

  6. MatLab Script and Functional Programming

    Science.gov (United States)

    Shaykhian, Gholam Ali

    2007-01-01

    MatLab Script and Functional Programming: MatLab is one of the most widely used very high level programming languages for scientific and engineering computations. It is very user-friendly and needs practically no formal programming knowledge. Presented here are MatLab programming aspects and not just the MatLab commands for scientists and engineers who do not have formal programming training and also have no significant time to spare for learning programming to solve their real world problems. Specifically provided are programs for visualization. The MatLab seminar covers the functional and script programming aspect of MatLab language. Specific expectations are: a) Recognize MatLab commands, script and function. b) Create, and run a MatLab function. c) Read, recognize, and describe MatLab syntax. d) Recognize decisions, loops and matrix operators. e) Evaluate scope among multiple files, and multiple functions within a file. f) Declare, define and use scalar variables, vectors and matrices.

  7. IEA-R1 Nuclear Research Reactor: 58 Years of Operating Experience and Utilization for Research, Teaching and Radioisotopes Production

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas, Jose Patricio Nahuel; Filho, Tufic Madi; Saxena, Rajendra; Filho, Walter Ricci [Nuclear and Energy Research Institute, IPEN-CNEN/SP, Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242 Cid Universitaria CEP: 05508-000- Sao Paulo-SP (Brazil)

    2015-07-01

    IEA-R1 research reactor at the Instituto de Pesquisas Energeticas e Nucleares (Nuclear and Energy Research Institute) 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 4.5 MWth with a 60-hour cycle per week. In the early sixties, IPEN produced {sup 131}I, {sup 32}P, {sup 198}Au, {sup 24}Na, {sup 35}S, {sup 51}Cr and labeled compounds for medical use. 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 {sup 99}Mo 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 several more years, to produce important primary radioisotopes {sup 99}Mo, {sup 125}I, {sup 131}I, {sup 153}Sm and {sup 192}Ir. Currently, all aspects of dealing with fuel element fabrication, fuel transportation, isotope processing, and spent fuel storage are handled by IPEN at the site. The reactor modernization program is slated for completion by 2015. This paper describes 58 years of operating experience and utilization of the IEA-R1 research reactor for research, teaching and radioisotopes production. (authors)

  8. Advanced LabVIEW Labs

    International Nuclear Information System (INIS)

    Jones, Eric D.

    1999-01-01

    In the world of computer-based data acquisition and control, the graphical interface program LabVIEW from National Instruments is so ubiquitous that in many ways it has almost become the laboratory standard. To date, there have been approximately fifteen books concerning LabVIEW, but Professor Essick's treatise takes on a completely different tack than all of the previous discussions. In the more standard treatments of the ways and wherefores of LabVIEW such as LabVIEW Graphical Programming: Practical Applications in Instrumentation and Control by Gary W. Johnson (McGraw Hill, NY 1997), the emphasis has been instructing the reader how to program LabVIEW to create a Virtual Instrument (VI) on the computer for interfacing to a particular instruments. LabVIEW is written in ''G'' a graphical programming language developed by National Instruments. In the past the emphasis has been on training the experimenter to learn ''G''. Without going into details here, ''G'' incorporates the usual loops, arithmetic expressions, etc., found in many programming languages, but in an icon (graphical) environment. The net result being that LabVIEW contains all of the standard methods needed for interfacing to instruments, data acquisition, data analysis, graphics, and also methodology to incorporate programs written in other languages into LabVIEW. Historically, according to Professor Essick, he developed a series of experiments for an upper division laboratory course for computer-based instrumentation. His observation was that while many students had the necessary background in computer programming languages, there were students who had virtually no concept about writing a computer program let alone a computer- based interfacing program. Thus the beginnings of a concept for not only teaching computer- based instrumentation techniques, but aiso a method for the beginner to experience writing a com- puter program. Professor Essick saw LabVIEW as the ''perfect environment in which to

  9. Research trends in radioisotopes: a scientometric analysis

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  10. OpenLabNotes--An Electronic Laboratory Notebook Extension for OpenLabFramework.

    Science.gov (United States)

    List, Markus; Franz, Michael; Tan, Qihua; Mollenhauer, Jan; Baumbach, Jan

    2015-10-06

    Electronic laboratory notebooks (ELNs) are more accessible and reliable than their paper based alternatives and thus find widespread adoption. While a large number of commercial products is available, small- to mid-sized laboratories can often not afford the costs or are concerned about the longevity of the providers. Turning towards free alternatives, however, raises questions about data protection, which are not sufficiently addressed by available solutions. To serve as legal documents, ELNs must prevent scientific fraud through technical means such as digital signatures. It would also be advantageous if an ELN was integrated with a laboratory information management system to allow for a comprehensive documentation of experimental work including the location of samples that were used in a particular experiment. Here, we present OpenLabNotes, which adds state-of-the-art ELN capabilities to OpenLabFramework, a powerful and flexible laboratory information management system. In contrast to comparable solutions, it allows to protect the intellectual property of its users by offering data protection with digital signatures. OpenLabNotes effectively closes the gap between research documentation and sample management, thus making Open-LabFramework more attractive for laboratories that seek to increase productivity through electronic data management.

  11. OpenLabNotes - An Electronic Laboratory Notebook Extension for OpenLabFramework.

    Science.gov (United States)

    List, Markus; Franz, Michael; Tan, Qihua; Mollenhauer, Jan; Baumbach, Jan

    2015-09-01

    Electronic laboratory notebooks (ELNs) are more accessible and reliable than their paper based alternatives and thus find widespread adoption. While a large number of commercial products is available, small- to mid-sized laboratories can often not afford the costs or are concerned about the longevity of the providers. Turning towards free alternatives, however, raises questions about data protection, which are not sufficiently addressed by available solutions. To serve as legal documents, ELNs must prevent scientific fraud through technical means such as digital signatures. It would also be advantageous if an ELN was integrated with a laboratory information management system to allow for a comprehensive documentation of experimental work including the location of samples that were used in a particular experiment. Here, we present OpenLabNotes, which adds state-of-the-art ELN capabilities to OpenLabFramework, a powerful and flexible laboratory information management system. In contrast to comparable solutions, it allows to protect the intellectual property of its users by offering data protection with digital signatures. OpenLabNotes effectively closes the gap between research documentation and sample management, thus making Open- LabFramework more attractive for laboratories that seek to increase productivity through electronic data management.

  12. Quarterly Technical Progress Report of Radioisotope Power System Materials Production and Technology Program tasks for January 2000 through March 2000

    International Nuclear Information System (INIS)

    Moore, J.P.

    2000-01-01

    The Office of Space and Defense Power Systems (OSDPS) of the Department of Energy (DOE) provides radioisotope Power Systems (BPS) 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 .I 997 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 OBNL

  13. Non-destructive assay employing 2D and 3D digital radiographic imaging acquired with thermal neutrons and reactor-produced radioisotopes

    International Nuclear Information System (INIS)

    Silvani, Maria Ines; Almeida, Gevaldo Lisboa de; Lopes, Ricardo T.

    2011-01-01

    The inner structure of some objects can only be visualized by using suitable techniques, when safety reasons or expensive costs preclude the application of invasive procedures. The kind of agent rendering an object partially transparent, unveiling thus its features, depends upon the object size and composition. As a rough rule of thumb, light materials are transparent to gamma and X-rays while the heavy ones are transparent to neutrons. When, after traversing an object, they hit a proper 2-D detector, a radiograph is produced representing a convoluted cross section, called projection, of that object. Taking a large number of such projections for different object attitudes, it is possible to obtain a 3-D tomography of the object as a map of attenuation coefficients. This procedure however, besides a time-consuming task, requires specially tailored equipment and software, not always available or affordable. Yet, in some circumstances it is feasible to replace the 3-D tomography by a stereoscopy, allowing one to visualize the spatial configuration of the object under analysis. In this work, 2-D and 3-D radiographic images have been acquired using thermal neutrons and reactor-produced radioisotopes and proper imaging plates as detectors. The stereographic vision has been achieved by taking two radiographs of the same object at different angles, from the detector point of view. After a treatment to render them red-white and green-white they were properly merged to yield a single image capable to be watched with red-green glasses. All the image treatment and rendering has been performed with the software ImageJ. (author)

  14. Radioisotope techniques for problem-solving on refineries

    International Nuclear Information System (INIS)

    Charlton, J.S.; Webb, M.

    1994-01-01

    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

  15. Modeling of GE Appliances in GridLAB-D: Peak Demand Reduction

    Energy Technology Data Exchange (ETDEWEB)

    Fuller, Jason C.; Vyakaranam, Bharat GNVSR; Prakash Kumar, Nirupama; Leistritz, Sean M.; Parker, Graham B.

    2012-04-29

    The widespread adoption of demand response enabled appliances and thermostats can result in significant reduction to peak electrical demand and provide potential grid stabilization benefits. GE has developed a line of appliances that will have the capability of offering several levels of demand reduction actions based on information from the utility grid, often in the form of price. However due to a number of factors, including the number of demand response enabled appliances available at any given time, the reduction of diversity factor due to the synchronizing control signal, and the percentage of consumers who may override the utility signal, it can be difficult to predict the aggregate response of a large number of residences. The effects of these behaviors can be modeled and simulated in open-source software, GridLAB-D, including evaluation of appliance controls, improvement to current algorithms, and development of aggregate control methodologies. This report is the first in a series of three reports describing the potential of GE's demand response enabled appliances to provide benefits to the utility grid. The first report will describe the modeling methodology used to represent the GE appliances in the GridLAB-D simulation environment and the estimated potential for peak demand reduction at various deployment levels. The second and third reports will explore the potential of aggregated group actions to positively impact grid stability, including frequency and voltage regulation and spinning reserves, and the impacts on distribution feeder voltage regulation, including mitigation of fluctuations caused by high penetration of photovoltaic distributed generation and the effects on volt-var control schemes.

  16. Advanced Radioisotope Power Conversion Technology Research and Development

    Science.gov (United States)

    Wong, Wayne A.

    2004-01-01

    NASA's Radioisotope Power Conversion Technology program is developing next generation power conversion technologies that will enable future missions that have requirements that cannot be met by either the ubiquitous photovoltaic systems or by current Radioisotope Power System (RPS) technology. Performance goals of advanced radioisotope power systems include improvement over the state-of-practice General Purpose Heat Source/Radioisotope Thermoelectric Generator by providing significantly higher efficiency to reduce the number of radioisotope fuel modules, and increase specific power (watts/kilogram). Other Advanced RPS goals include safety, long-life, reliability, scalability, multi-mission capability, resistance to radiation, and minimal interference with the scientific payload. NASA has awarded ten contracts in the technology areas of Brayton, Stirling, Thermoelectric, and Thermophotovoltaic power conversion including five development contracts that deal with more mature technologies and five research contracts. The Advanced RPS Systems Assessment Team includes members from NASA GRC, JPL, DOE and Orbital Sciences whose function is to review the technologies being developed under the ten Radioisotope Power Conversion Technology contracts and assess their relevance to NASA's future missions. Presented is an overview of the ten radioisotope power conversion technology contracts and NASA's Advanced RPS Systems Assessment Team.

  17. Regulations concerning the radionuclides uses in France; Reglementation de l'utilisation des radioisotopes en France

    Energy Technology Data Exchange (ETDEWEB)

    Vergne, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Bugnard, L [Institut national d' Hygiene (France)

    1955-07-01

    The progress in the uses of radioisotopes has been conditioned by increasing the number of trained workers and researchers and developing theoretical teaching in universities since 1950 in France as well as developing a national control of the distribution and uses of radioisotopes. With the large diffusion and development of radioisotopes uses and applications, new rules and regulations came to control the importation, exportation, transport and utilization of radioisotopes. In the first part, it described the different French laws since 1934 and their successive modifications which ruled on the production, manipulation and utilization of radioisotopes. An inter-ministerial committee was created in 1952 to advise and inform of all the questions related to the preparation, importation, exportation, possession and distribution of radioisotopes. The transport regulations are in constant evolution and has got to meet with international recommendations. It distinguished three different type of transport: road, river and railway transport, postal transport and finally air transport. All the different transports have their specific packaging, maximum transportable quantity, maximum material intensity and labelling requirements. The regulations about customs duties are specified as well as the administrative formalities for non natural radioisotopes importation. Since 1950, diseases caused by irradiation to natural or artificial radioactive materials are recognised as professional diseases and a table of the actual regulations is presented. (M.P.)

  18. Discrete radioisotopic relays of a cyclic action

    International Nuclear Information System (INIS)

    Klempner, K.S.; Vasil'ev, A.G.

    1975-01-01

    A functional diagram of discrete radioisotopic relay equipment (RRP) with cyclic action was examined. An analysis of its rapid action and reliability under stationary conditions and transition regimes is presented. A structural diagram of radioisotopic relay equipment shows three radiation detectors, a pulse standardizer, an integrator and a power amplifier with a threshold cut-off device. It was established that the basic properties of the RRP - rapid action and reliability - are determined entirely by the counting rate of the average frequency of pulses from the radiation detector, n 0 and n 1 , in the 0 and 1 states (absence of current in the electromagnetic relay winding and activation of the winding of the output relay), capacities N 1 and N 2 of the dual counters, and the frequency of the transition threshold, f, of the generator. Formulas are presented which allow making engineering calculations for determining the optimum RRP parameters. High speed and reliability are shown, which are determined by the production purposes of the relay

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

    International Nuclear Information System (INIS)

    Zhang Jiahua

    1987-01-01

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

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

    International Nuclear Information System (INIS)

    Gordon, Ana Maria P.L.

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-03-15

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

  3. Present status of application of radiation and radioisotopes in Bangladesh

    International Nuclear Information System (INIS)

    Hossain, Anwar

    1984-01-01

    Bangladesh has proceeded with the atomic energy programme in three phases: (1) research and development using radiation and radioisotopes and application of the results, (2) building the infrastructure in nuclear technology and (3) production of electricity from nuclear sources and development of associated facilities. It has entered the second phase of the programme. The following main areas of research and application were referred to: agriculture, food preservation, medical sterilization and radiation biology, medicine, non-destructive testing, isotope hydrology, elemental analysis, particle-induced x-ray emission (PIXE) methods, radioisotope-induced x-ray fluorescence (RIXFA) methods, flame atomic absorption spectrophotometric (AAS) methods, molecular absorption and fluorescence spectroscopy, health physics, and future programme with research reactor. (Namekawa, K.)

  4. Radiation and radioisotopes in fruits and vegetable production and preservation

    International Nuclear Information System (INIS)

    Chapke, V.G.

    1975-01-01

    Use of radioisotopes is being made in the mutation breeding in obtaining the varieties resistant to certain diseases and pests. Nirale and Gour (1973) found that there is an average 50 percent increase in yield of chilli, onion and lettuse, with low doses of x-ray irradiation. radiotracers show that P and K are more rapidly absorbed through leaves than roots. This technique is useful in deciding economic use of fertilizers and micronutrients. The ultraviolet light inactivates some viruses in plants. The radiation processing of foods minimises the packing costs. (author)

  5. Radioisotope clocks in archaeology

    Energy Technology Data Exchange (ETDEWEB)

    Hedges, R E.M. [Oxford Univ. (UK). Research Lab. for Archaeology

    1979-09-06

    Methods of absolute dating which use the rate of disintegration of a radioactive nucleus as the clock, are reviewed. The use of the abundant radioisotopes (/sup 40/K, Th and U) and of the rare radioisotopes (/sup 14/C, /sup 10/Be, /sup 26/Al, /sup 32/Si, /sup 36/Cl, /sup 41/Ca, /sup 53/Mn) is discussed and radiation integration techniques (fission track dating, thermoluminescence and related techniques) are considered. Specific fields of use of the various methods and their accuracy are examined.

  6. Uses of radioisotopes in Sudan

    International Nuclear Information System (INIS)

    Elradi, E. A. M.

    2013-07-01

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

  7. Utilization of radioisotopes in France, present and future

    International Nuclear Information System (INIS)

    Gauvenet, A.J.

    1976-01-01

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

  8. 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)

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

    International Nuclear Information System (INIS)

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

    1986-07-01

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

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  11. Novel Radioisotope Applications in Industry Promoted by the IAEA

    International Nuclear Information System (INIS)

    Thereska, J.

    2001-01-01

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

  12. Facilities for Research and Development of Medical Radioisotopes

    International Nuclear Information System (INIS)

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

    2003-03-01

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

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

    International Nuclear Information System (INIS)

    Benjamin, R.W.; Frey, G.D.; McLean, D.C., Jr; Spicer, K.M.; Davis, S.E.; Baron, S.; Frysinger, J.R.; Blanpied, G.; Adcock, D.

    1997-01-01

    The accelerator production of tritium (APT) facility, with its high beam current and high beam energy, would be an ideal supplier of radioisotopes for medical research, imaging, and therapy. By-product radioisotopes will be produced in the APT window and target cooling systems and in the tungsten target through spallation, neutron, and proton interactions. High intensity proton fluxes are potentially available at three different energies for the production of proton- rich radioisotopes. Isotope production targets can be inserted into the blanket for production of neutron-rich isotopes. Currently, the major production sources of radioisotopes are either aging or abroad, or both. The use of radionuclides in nuclear medicine is growing and changing, both in terms of the number of nuclear medicine procedures being performed and in the rapidly expanding range of procedures and radioisotopes used. A large and varied demand is forecast, and the APT would be an ideal facility to satisfy that demand

  14. Radioisotopes in soil science

    International Nuclear Information System (INIS)

    Kotur, S.C.

    2004-01-01

    Soils form a thin veneer of the Earth that sustain the entire flora and fauna of the terra firma. To that extent the soil as a natural resource is very precious and needs to be managed in a sustainable manner. The fate of degradation of pesticides in soil and build-up of heavy metals in the overall biosafety scenario is also studied gainfully using radioisotopes. Radioisotopes are a very potent tool in the hands of the Soil Scientists, perhaps, the most important among the peaceful applications in service of the mankind

  15. Radioisotopic diagnosis in pediatrics. Radioizotopnaya diagnostika v pediatrii

    Energy Technology Data Exchange (ETDEWEB)

    Zubovskij, G A

    1983-01-01

    The material concerning the possibilities of modern radiodiagnostic methods in the practice of pediatric cardiology, pulmonology, uronephrology, gastroentorology, osteology, endocrinology and perinatology is presented. The data on techniques for production of radiopharmaceuticals, radiation loads on child and personnel and the rules of radiation safety are given. The value and the place of radioisotopic diagnosis in the complex of clinicoroentgenologic and instrumental investigations in pediatrics are based.

  16. Economical Radioisotope Power

    Data.gov (United States)

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

  17. Regulations concerning the radionuclides uses in France; Reglementation de l'utilisation des radioisotopes en France

    Energy Technology Data Exchange (ETDEWEB)

    Vergne, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Bugnard, L. [Institut national d' Hygiene (France)

    1955-07-01

    The progress in the uses of radioisotopes has been conditioned by increasing the number of trained workers and researchers and developing theoretical teaching in universities since 1950 in France as well as developing a national control of the distribution and uses of radioisotopes. With the large diffusion and development of radioisotopes uses and applications, new rules and regulations came to control the importation, exportation, transport and utilization of radioisotopes. In the first part, it described the different French laws since 1934 and their successive modifications which ruled on the production, manipulation and utilization of radioisotopes. An inter-ministerial committee was created in 1952 to advise and inform of all the questions related to the preparation, importation, exportation, possession and distribution of radioisotopes. The transport regulations are in constant evolution and has got to meet with international recommendations. It distinguished three different type of transport: road, river and railway transport, postal transport and finally air transport. All the different transports have their specific packaging, maximum transportable quantity, maximum material intensity and labelling requirements. The regulations about customs duties are specified as well as the administrative formalities for non natural radioisotopes importation. Since 1950, diseases caused by irradiation to natural or artificial radioactive materials are recognised as professional diseases and a table of the actual regulations is presented. (M.P.)

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

    International Nuclear Information System (INIS)

    Anguis T, C.

    1975-01-01

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

  19. Production of radioisotopes at the Boris Kidric Institute of Nuclear Sciences at Vinca, Yugoslavia; Proizvodnja radioaktivnih izotopa

    Energy Technology Data Exchange (ETDEWEB)

    Teofilovski, C [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    The investigations in order to master the production of radioisotopes were commenced simultaneously with the beginning of RA nuclear reactor construction at Vinca, in 1956. A new organization division - Laboratory for chemistry of high activity accepting beside other problems also the programme for mastering the regular production of radioactive material was formed in 1959. Various problems during the realization of this programme have been solved, starting with the staff training for work with radioactive material on the high level activity (to 7500 Ci/source), construction and equipment of the laboratory area for safe work, up to development of the whole series of chemical-technological procedures and techniques for regular production of various radioactive products, as well as the methods for their chemical, radiometric and pharmaceutical control. Owing to the successful realization of this programme, the Institute 'Boris Kidric' supplies to-day regularly 110 organizations in the country with various radioactive products, applied in medicine, industry and research. The annual product of the radioactive solutions of radioisotopes J-131, Au-198, P-32, S-35 etc., amounts to about 75 Ci, radiographic sources Ir-192 and Co-60 to 2000 Ci and Co-60 sources for teletherapy and the other applications to many thousand curies (author) [Serbo-Croat] Paralelno sa pocetkom izgradnje nuklearnog reaktora RA u Vinci 1956. godine zapoceta su istrazivanja u oblasti osvajanja proizvodnje radioizotopa. 1958. god. formirana je nova organizaciona jedinica - Laboratorija za hemiju visoke aktivnosti, koja je, pored ostalog, prihvatila i program osvajanja redovne proizvodnje radioaktivnog materijala. U toku realizacije programa reseni su raznovrsni problemi pocev od pripreme kadrova za rad sa radioaktivnim materijalom na visokom nivou aktivnosti (do 7500 Ci/izvor), izgradnje i opremanja laboratorijskog prostora za bezbedan rad, do razvoja citavog niza hemijsko-tehnoloskih postupaka i

  20. Industrial applications of radioisotope tracers

    International Nuclear Information System (INIS)

    Easey, J.F.

    1985-01-01

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

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

    International Nuclear Information System (INIS)

    Campos, Ana Celia P.P.; Cuperschmid, Ethel Mizrahy; Campos, Tarcisio P. Ribeiro de

    2007-01-01

    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. 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)

  3. Assessment of radioisotope heaters for remote terrestrial applications

    International Nuclear Information System (INIS)

    Uherka, K.L.

    1987-05-01

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

  4. Engineering Novel Lab Devices Using 3D Printing and Microcontrollers.

    Science.gov (United States)

    Courtemanche, Jean; King, Samson; Bouck, David

    2018-03-01

    The application of 3D printing and microcontrollers allows users to rapidly engineer novel hardware solutions useful in a laboratory environment. 3D printing is transformative as it enables the rapid fabrication of adapters, housings, jigs, and small structural elements. Microcontrollers allow for the creation of simple, inexpensive machines that receive input from one or more sensors to trigger a mechanical or electrical output. Bringing these technologies together, we have developed custom solutions that improve capabilities and reduce costs, errors, and human intervention. In this article, we describe three devices: JetLid, TipWaster, and Remote Monitoring Device (REMIND). JetLid employs a microcontroller and presence sensor to trigger a high-speed fan that reliably de-lids microtiter plates on a high-throughput screening system. TipWaster uses a presence sensor to activate an active tip waste chute when tips are ejected from a pipetting head. REMIND is a wireless, networked lab monitoring device. In its current implementation, it monitors the liquid level of waste collection vessels or bulk liquid reagent containers. The modularity of this device makes adaptation to other sensors (temperature, humidity, light/darkness, movement, etc.) relatively simple. These three devices illustrate how 3D printing and microcontrollers have enabled the process of rapidly turning ideas into useful devices.

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

    International Nuclear Information System (INIS)

    Carneiro, Janete C.G.G.; Sanches, Matias P.; Rodrigues, Demerval L.; Campos, Daniela; Nogueira, Paulo R.; Damato, Sandra R.; Pecequilo, Brigitte R.

    2014-01-01

    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 131 I, 99m Tc and 99 Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m 3 ), the activities concentrations also remained below the maximum permissible values, excepting to 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 -1 , below the ICRP 103 recommended limit of 20 mSv.y -1 for workers. (author)

  6. A set of portable radioisotopic control and measuring instruments

    International Nuclear Information System (INIS)

    Pospeev, V.V.; Sidorov, V.N.; Tesnavs, Eh.R.; Uleksin, V.I.

    1979-01-01

    The problems and perspectives are examined of the portable radioisotope instruments application in agriculture, building industry, engeeniring and geological survay and in melioration. Principles are given of creation a series of radioisotopic instruments based on the principle of ganging. The series described consists of radioisotopic densimeters and moisture gages of the portable type, based on the ganging principle. The instruments differ in the measuring converters and have unified information processing and power supply devices. Criteria are stated for the ganging principle estimation, in particular, estimation of the technical means' compatibility. Four different types of compatibility are distinguished: an information compatibility; a metrological compatibility; structural and operational compatibility. Description is given of the unified information processing device - the unified pulse counter of the SIP-1M type and description of a row of radioisotopic measuring converters, which provides a possibility for completing the portable radioisotope densimeter of the RPP-2 type, intended for measuring densities of concrets and soils in the surface layer up to 30 cm and the density range from 1000 to 2500 kg/m 3 ; portable radioisotope densimeter of the RPP-1 type having measuring range from 600 to 1500 kg/m 3 ; surface-depth radioisotopic densimeter of the PPGR-1 type and surface-depth radioisotopic moisture gage of the VPGR-1 type [ru

  7. Radioisotopic indicators in microbiology

    International Nuclear Information System (INIS)

    Isamov, N.N.

    1976-01-01

    The book comprises data obtained by the laboratory of radiobiology (Uzbek Research Veterinary Institute) for 15 years and sums up data of domestic and foreign scientists; it discusses problems of the utilization of radioactive isotopes of sulphur, cadmium, phosphorus and other chemical elements by microorganisms; indicates the specificity of the utilization of radioisotopes in microbiology. The influence is considered of external factors on the inclusion of radioisotopes into microorganisms, methods are discussed of obtaining labelled microorganisms and their antigens, radioactivity of bacteria is considered as affected by the consistency and composition of the nutritive medium and other problems

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  9. Computerized control system for administration of the radioisotope use

    International Nuclear Information System (INIS)

    Sago, Tsutomu; Ito, Shin; Isozumi, Yasuhito; Kurihara, Norio

    1986-01-01

    An on-line computer system for administration of the radioisotope use has been developed. This system consists of a multi-job type host computer and two sets of personal computers with identification card-readers. The personal computers are employed as terminal devices for radioisotope users. By the use of an identification card, entrance and leaving times are recorded automatically. Furthermore, an easy operation of the personal computer permits users to access to the information of their resistered radioisotopes, such as nuclides, chemical forms, updated activities, storage locations, and history of usage. A recording sheet on which those data are printed is provided from the personal computer. After the use of radioisotopes, users can record their data on the recording sheets. These records are used as the input data to this system to update the data of the used radioisotopes. Owing to the concise format of the recording sheet and various sorting programs developed in present work, this system enables us to grasp the exact flow of the radioisotopes from purchase to disposal. Out-put data from high-speed kanji printer can provide many important books which are legally requested to be kept for administration of the radioisotope use. (author)

  10. 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.

  11. 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)

  12. Intergrated approach to quality control procedures of radioisotopes and radiopharmaceuticals

    International Nuclear Information System (INIS)

    Rohani Mohamad

    1986-01-01

    Various aspects of the quality control procedures for radioisotopes and radiopharmaceuticals have been discussed. The paper high lighted those procedures that are important in ensuring the efficacy of the product. It also gives a general idea of the various procedures that are actually carried out by the Quality Control Section. (A.J.)

  13. OpenLabNotes – An Electronic Laboratory Notebook Extension for OpenLabFramework

    Directory of Open Access Journals (Sweden)

    List Markus

    2015-09-01

    Full Text Available Electronic laboratory notebooks (ELNs are more accessible and reliable than their paper based alternatives and thus find widespread adoption. While a large number of commercial products is available, small- to mid-sized laboratories can often not afford the costs or are concerned about the longevity of the providers. Turning towards free alternatives, however, raises questions about data protection, which are not sufficiently addressed by available solutions. To serve as legal documents, ELNs must prevent scientific fraud through technical means such as digital signatures. It would also be advantageous if an ELN was integrated with a laboratory information management system to allow for a comprehensive documentation of experimental work including the location of samples that were used in a particular experiment. Here, we present OpenLabNotes, which adds state-of-the-art ELN capabilities to OpenLabFramework, a powerful and flexible laboratory information management system. In contrast to comparable solutions, it allows to protect the intellectual property of its users by offering data protection with digital signatures. OpenLabNotes effectively closes the gap between research documentation and sample management, thus making Open- LabFramework more attractive for laboratories that seek to increase productivity through electronic data management.

  14. Radioisotope methodology course radioprotection aspects

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  15. Radioisotope thermoelectric generator licensed hardware package and certification tests

    International Nuclear Information System (INIS)

    Goldmann, L.H.; Averette, H.S.

    1994-01-01

    This paper presents the Licensed Hardware package and the Certification Test portions of the Radioisotope Thermoelectric Generator Transportation System. This package has been designed to meet those portions of the Code of Federal Regulations (10 CFR 71) relating to ''Type B'' shipments of radioactive materials. The detailed information for the anticipated license is presented in the safety analysis report for packaging, which is now in process and undergoing necessary reviews. As part of the licensing process, a full-size Certification Test Article unit, which has modifications slightly different than the Licensed Hardware or production shipping units, is used for testing. Dimensional checks of the Certification Test Article were made at the manufacturing facility. Leak testing and drop testing were done at the 300 Area of the US Department of Energy's Hanford Site near Richland, Washington. The hardware includes independent double containments to prevent the environmental spread of 238 Pu, impact limiting devices to protect portions of the package from impacts, and thermal insulation to protect the seal areas from excess heat during accident conditions. The package also features electronic feed-throughs to monitor the Radioisotope Thermoelectric Generator's temperature inside the containment during the shipment cycle. This package is designed to safely dissipate the typical 4500 thermal watts produced in the largest Radioisotope Thermoelectric Generators. The package also contains provisions to ensure leak tightness when radioactive materials, such as a Radioisotope Thermoelectric Generator for the Cassini Mission, planned for 1997 by the National Aeronautics and Space Administration, are being prepared for shipment. These provisions include test ports used in conjunction with helium mass spectrometers to determine seal leakage rates of each containment during the assembly process

  16. LAB/NTAL Facilitates Fungal/PAMP-induced IL-12 and IFN-γ Production by Repressing β-Catenin Activation in Dendritic Cells

    Science.gov (United States)

    Orr, Selinda J.; Burg, Ashley R.; Chan, Tim; Quigley, Laura; Jones, Gareth W.; Ford, Jill W.; Hodge, Deborah; Razzook, Catherine; Sarhan, Joseph; Jones, Yava L.; Whittaker, Gillian C.; Boelte, Kimberly C.; Lyakh, Lyudmila; Cardone, Marco; O'Connor, Geraldine M.; Tan, Cuiyan; Li, Hongchuan; Anderson, Stephen K.; Jones, Simon A.; Zhang, Weiguo; Taylor, Philip R.; Trinchieri, Giorgio; McVicar, Daniel W.

    2013-01-01

    Fungal pathogens elicit cytokine responses downstream of immunoreceptor tyrosine-based activation motif (ITAM)-coupled or hemiITAM-containing receptors and TLRs. The Linker for Activation of B cells/Non-T cell Activating Linker (LAB/NTAL) encoded by Lat2, is a known regulator of ITAM-coupled receptors and TLR-associated cytokine responses. Here we demonstrate that LAB is involved in anti-fungal immunity. We show that Lat2 −/− mice are more susceptible to C. albicans infection than wild type (WT) mice. Dendritic cells (DCs) express LAB and we show that it is basally phosphorylated by the growth factor M-CSF or following engagement of Dectin-2, but not Dectin-1. Our data revealed a unique mechanism whereby LAB controls basal and fungal/pathogen-associated molecular patterns (PAMP)-induced nuclear β-catenin levels. This in turn is important for controlling fungal/PAMP-induced cytokine production in DCs. C. albicans- and LPS-induced IL-12 and IL-23 production was blunted in Lat2−/− DCs. Accordingly, Lat2−/− DCs directed reduced Th1 polarization in vitro and Lat2 −/− mice displayed reduced Natural Killer (NK) and T cell-mediated IFN-γ production in vivo/ex vivo. Thus our data define a novel link between LAB and β-catenin nuclear accumulation in DCs that facilitates IFN-γ responses during anti-fungal immunity. In addition, these findings are likely to be relevant to other infectious diseases that require IL-12 family cytokines and an IFN-γ response for pathogen clearance. PMID:23675302

  17. Elementary concepts of the radioisotopes uses

    International Nuclear Information System (INIS)

    Pisarev, Mario A.

    2004-01-01

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

  18. Study of solid target preparation for developing I-124, Pd-103, Cu-64 radioisotopes based cyclotron

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hong; Park, Hyun; Lee, Ji Sub; Lee, Dong Hoon; Chun, Kwon Soo [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of); Choi, Hee Dong [Seoul National Univ., Seoul (Korea, Republic of)

    2005-07-01

    The decay characteristics of I-124, Pd-103 and Cu-64 radioisotopes produced by cyclotron have considered useful agents for diagnostic imaging or therapy. Numbers of radioisotopes used in medical applications or promised for development are produced with solid targets. The aims of developing solid targets are to obtain large quantities of radionuclides from accelerators. The scope of the study is to develop optimized target system and chemical procedures of these radioisotopes. In order to increase the availability of the radionuclides, the investigation for the design of the solid target and different procedures yielding efficient production of high specific activity will be carrying. In this work, we will present the issue of the primary target design concept.

  19. Radioisotope-powered photovoltaic generator

    International Nuclear Information System (INIS)

    McKlveen, J.W.; Uselman, J.

    1979-01-01

    Disposing of radioactive wastes from nuclear power plants has become one of the most important issues facing the nuclear industry. In a new concept, called a radioisotope photovoltaic generator, a portion of this waste would be used in conjunction with a scintillation material to produce light, with subsequent conversion into electricity via photovoltaic cells. Three types of scintillators and two types of silicon cells were tested in six combinations using 32 P as the radioisotope. The highest system efficiency, determined to be 0.5% when the light intensity was normalized to 100 mW/cm 2 , was obtained using a CsI crystal scintillator and a Helios photovoltaic cell

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

    International Nuclear Information System (INIS)

    1983-01-01

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

  1. RADIOISOTOPE INVENTORY FOR TSPA-SR

    International Nuclear Information System (INIS)

    Leigh, C.; Rechard, R.

    2001-01-01

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

  2. Aspects of radioisotopes utilization in clinical medicine

    International Nuclear Information System (INIS)

    Rocha, A.F.G.; Lima e Forti, C.A. de; Cunha, M. da C.; Souza Maciel, O. de

    1973-01-01

    A revision concerning radioisotope use in Medicine have been dow. Harmless and effeciency of radioisotopes are shown. Techniques and advantages of tracers used for brain scintiscanning, lung scintiscanning, liver scintinscanning, spleen scintiscanning, bone scintiscanning and thyroid scintiscanning are described and images of them are presented [pt

  3. Radioisotopes in non-destructive testing

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1976-12-01

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

  4. Radioisotopes: problems of responsibility arising from medicine

    International Nuclear Information System (INIS)

    Dupon, Michel.

    1978-09-01

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

  5. The production of radioisotopes with a betatron using an internal bombarding technique; Production de radioisotopes par bombardement interne dans un betatron; Proizvodstvo radioizotopov s pomoshch'yu betatrona s ispol'zovaniem metoda vnutrennej bombardirovki; Obtencion de radioisotopos por bombardeo interno en el betatron

    Energy Technology Data Exchange (ETDEWEB)

    Morinaga, H [Department of Physics, Tohoku University, Sendai (Japan)

    1962-01-15

    A new technique for producing radioisotopes of high specific activity with a betatron has been developed and is being used successfully. Materials to be activated are placed inside the doughnut at the end of a blind cylinder inserted from outside; thus samples are bombarded under one atmosphere just behind the bremsstrahlung target where the radiation intensity is extremely high. The saturation activity of Cu{sup 62} produced on a small piece of copper exceeded 1 mc, and the highest specific activity obtainable was approximately 500 times that produced in a conventional arrangement. So far, this internal-target technique has been used only for nuclear spectroscopy work; eight new species of radioactive isotopes (Co{sup 63}, Ga{sup 75}, As{sup 81}, In{sup 121}, In{sup 123}, Tm{sup 173}, Tm{sup 175} and Ac{sup 231}) have been identified and several new isomers have been found. The feasibility of this bombarding technique opens neiv possibilities, since medical, industrial or research betatrons may now be used, for isotope production. Short-lived isotopes are often more convenient in various applications because of their fast decay and high-energy radiation, and they may be made readily without any special skill. (author) [French] On a mis au point et utilise avec succes line technique nouvelle pour la production de radioisotopes d'activite specifique elevee dans un betatron. Les matieres a activer sont placees a l'interieur d'un tube toroidal, a l'extremite d'un cylindre a ouverture unique introduit de l'exterieur; les echantillons se trouvent ainsi bombardes, sous une atmosphere, juste derriere la cible de rayonnement de freinage, a l'endroit ou l'intensite du rayonnement est extremement elevee. L'activite de saturation du {sup 62}Cu produite sur de petits morceaux de cuivre depassait 1 millicurie et l'activite specifique la plus elevee que l'on ait pu obtenir egalait environ 500 fois l'activite produite dans un dispositif classique. Jusqu'a present, cette technique

  6. Lab-on-fiber technology

    CERN Document Server

    Cusano, Andrea; Crescitelli, Alessio; Ricciardi, Armando

    2014-01-01

    This book focuses on a research field that is rapidly emerging as one of the most promising ones for the global optics and photonics community: the "lab-on-fiber" technology. Inspired by the well-established 'lab on-a-chip' concept, this new technology essentially envisages novel and highly functionalized devices completely integrated into a single optical fiber for both communication and sensing applications.Based on the R&D experience of some of the world's leading authorities in the fields of optics, photonics, nanotechnology, and material science, this book provides a broad and accurate de

  7. Sorption-desorption processes of radioisotopes with solid materials from liquid releases and atmosphere deposits. The distribution coefficient (Ksub(d)), its uses, limitations, and practical applications

    International Nuclear Information System (INIS)

    Saas, Arsene

    1979-03-01

    The various sorption-desorption processes of radionuclides with environmental materials are presented. The parameters governing the distribution coefficient are reviewed in the light of various examples. The factors affecting equilibria between the different phases are: reaction time, concentration of the solid phase, water quality, salinity, competition between ions, concentration of radioisotopes or stable isotopes, pH of the mobile phase, particle diameter, chemical form of the radioisotopes, nature of the solid phase, temperature. The effects of the biological parameters on the distribution coefficient are discussed. Biological processes affect the main chemical transformations: mineralization, insolubilization, oxidation-reduction, complexation, ... The importance of these processes is demonstrated by a number of examples in various media. Finally, the practical use of Ksub(d) in the assessment of the environmental impact of radioactive releases is developed, with special emphasis on the limits of its use in siting studies and its essential interest in specifying pathways and capacity of a river system [fr

  8. Transferring experience labs for production engineering students to universities in newly industrialized countries

    Science.gov (United States)

    Leiden, A.; Posselt, G.; Bhakar, V.; Singh, R.; Sangwan, K. S.; Herrmann, C.

    2018-01-01

    The Indian economy is one of the fastest growing economies in the world and the demand for the skilled engineers is increasing. Subsequently the Indian education sector is growing to provide the necessary number of skilled engineers. Current Indian engineering graduates have broad theoretical background but lack in methodological, soft and practical skills. To bridge this gap, the experience lab ideas from the engineering education at “Die Lernfabrik” (learning factory) of the Technische Universität Braunschweig (TU Braunschweig) is transferred to the Birla Institute of Technology and Science in Pilani (BITS Pilani), India. This Lernfabrik successfully strengthened the methodological, soft and practical skills of the TU Braunschweig production-engineering graduates. The target group is discrete manufacturing education with focusing on energy and resource efficiency as well as cyber physical production systems. As the requirements of industry and academia in India differs from Germany, the transfer of the experience lab to the Indian education system needs special attention to realize a successful transfer project. This publication provides a unique approach to systematically transfer the educational concept in Learning Factory from a specific university environment to a different environment in a newly industrialized country. The help of a bilateral university driven practice partnership between the two universities creates a lighthouse for the Indian university environment.

  9. Use of radioisotopes and nuclear methods in metallurgy

    International Nuclear Information System (INIS)

    Trehber, K.

    1976-01-01

    Some kinds of using radioisotope methods and instruments for regulation and control of metallurgical processes are reviewed. Computized data processing is described as well. The efficiency of industrial application of radioisotopes is remarked

  10. Microbiological quality control practices at Australian Radioisotopes

    International Nuclear Information System (INIS)

    Saunders, M.

    1987-01-01

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

  11. Radio-isotope generator

    International Nuclear Information System (INIS)

    Benjamins, H.M.

    1983-01-01

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

  12. 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.

  13. 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.

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

    International Nuclear Information System (INIS)

    Oranj, Leila Mokhtari; Oh, Joo Hee; Jung, Nam Suk; Bae, O Ryun; Lee, Hee Seock

    2014-01-01

    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 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. 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)

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

    International Nuclear Information System (INIS)

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

    1990-05-01

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

  17. ScalaLab and GroovyLab: Comparing Scala and Groovy for Scientific Computing

    Directory of Open Access Journals (Sweden)

    Stergios Papadimitriou

    2015-01-01

    Full Text Available ScalaLab and GroovyLab are both MATLAB-like environments for the Java Virtual Machine. ScalaLab is based on the Scala programming language and GroovyLab is based on the Groovy programming language. They present similar user interfaces and functionality to the user. They also share the same set of Java scientific libraries and of native code libraries. From the programmer's point of view though, they have significant differences. This paper compares some aspects of the two environments and highlights some of the strengths and weaknesses of Scala versus Groovy for scientific computing. The discussion also examines some aspects of the dilemma of using dynamic typing versus static typing for scientific programming. The performance of the Java platform is continuously improved at a fast pace. Today Java can effectively support demanding high-performance computing and scales well on multicore platforms. Thus, both systems can challenge the performance of the traditional C/C++/Fortran scientific code with an easier to use and more productive programming environment.

  18. Radioisotope laboratory in Turkey

    International Nuclear Information System (INIS)

    1961-01-01

    The Turkish Government formally requested that the Agency provide for one year the services of an expert in the agricultural applications of radioisotopes. Specifically, they wanted this expert first of all to assist in setting up and equipping a pioneer laboratory for the utilization of radioisotopes in agricultural research. Once the laboratory was in operation, the expert was to initiate various research projects using isotope techniques, and to train personnel to carry on this work. The Agency was also asked to supply various specialized equipment for the laboratory, including some radioisotopes. On 10 December 1960 the first phase was complete - the new laboratory was formally opened. It is foreseen that the research projects which will be initiated at the laboratory will include the following: determination of the effect of fertilizers upon yield and quality of field crops and fruit trees, soil fertility studies, studies of mineral element uptake and localization of nutrients in plant body, studies of the folar application of mineral nutrients, especially in fruit trees, investigation of microelements in field crops and fruit trees, investigation of pollination problems, study of the distribution of mineral elements in different fruit seedlings, study of the uptake of nutrients by fruit trees during the rest period, dispersal studies on insects, insecticide studies

  19. Radioisotope laboratory in Turkey

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-04-15

    The Turkish Government formally requested that the Agency provide for one year the services of an expert in the agricultural applications of radioisotopes. Specifically, they wanted this expert first of all to assist in setting up and equipping a pioneer laboratory for the utilization of radioisotopes in agricultural research. Once the laboratory was in operation, the expert was to initiate various research projects using isotope techniques, and to train personnel to carry on this work. The Agency was also asked to supply various specialized equipment for the laboratory, including some radioisotopes. On 10 December 1960 the first phase was complete - the new laboratory was formally opened. It is foreseen that the research projects which will be initiated at the laboratory will include the following: determination of the effect of fertilizers upon yield and quality of field crops and fruit trees, soil fertility studies, studies of mineral element uptake and localization of nutrients in plant body, studies of the folar application of mineral nutrients, especially in fruit trees, investigation of microelements in field crops and fruit trees, investigation of pollination problems, study of the distribution of mineral elements in different fruit seedlings, study of the uptake of nutrients by fruit trees during the rest period, dispersal studies on insects, insecticide studies.

  20. Radioisotopes for medical applications

    International Nuclear Information System (INIS)

    Carr, S.

    1998-01-01

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

  1. Radioisotopes for medical applications

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-03-01

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

  2. Validation of the L.A.L. technique (gel cloth) in radiodiagnosis and radioisotopes

    International Nuclear Information System (INIS)

    Morote, M.; Otero, M.; Chavez, G.

    1999-01-01

    Based on the validation of the LAL technique (gel cloth), real endotoxin limits (EL), expressed in endotoxin units per milliliter (EU/mL), as well as maximum dilution volume (MDV) were determined in seven radiodiagnosis agents (RDA): medronate, pentetate, sulfur colloid, albumin macroaggregated, succimer, disofenin, and pyrophosphates, which showed M.D.V. values of: 1:80; 1:16; 1:128; 1:64; 1:4; 1:128; 1:64 and EL of 20 EU/mL; 4 EU/mL; 32 EU/mL; 16 EU/mL; 1 EU/mL and 16 EU/mL, respectively. Radioisotope Tc-99m presents a MDV of 1:1 and an EL below 0,25 EU/mL. Clear interference in the acidity of sulfur colloid (pH below 2) was also found against pyrotell reaction, even in the sixth dilution of the product. M.D.V. results also showed that dilutions are even 100 times smaller than the theoretical values

  3. Vitrified chemically bonded phosphate ceramics for immobilization of radioisotopes

    Science.gov (United States)

    Wagh, Arun S.

    2016-04-05

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

  4. Radioisotopic determination methods of sulphur dispersion and sulphur blooming in rubber compounds

    International Nuclear Information System (INIS)

    Goraczka, W.; Koczorowska, E.

    1997-01-01

    It is well known that the concentration of sulphur in rubber compounds essentially effects the structure of the vulkanizate network. But there are no efficient and accurate methods to estimate the dispersion and migration (blooming) of curatives in raw rubber. In the work radioisotope methods have been analyzed to study the dispersion of curatives, physical and chemical processes in rubber and to optimize technical conditions of tire production. The radioactivity of the 35 S isotope introduced into rubber compounds has been measured by volumetric and surface methods. It was proved that the radioisotopic methods can be used in the studies. Experimental data of the effect of selected technological factors on these processes are presented. Rubber compounds containing soluble sulphur were made for such investigations. These methods permit detection of concentrations 10 -6 g of the radioactive isotope per 0.1 g of rubber compound. The sensitivity of these methods enables the investigation of radioisotope behaviour in rubber compounds during processing on an industrial scale without any hazards for workers

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

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1996-03-01

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

  6. 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.

  7. Particle-beam accelerators for radiotherapy and radioisotopes

    International Nuclear Information System (INIS)

    Boyd, T.J.; Crandall, K.R.; Hamm, R.W.

    1981-01-01

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

  8. Radioisotopes produced by neutron irradiation of food

    International Nuclear Information System (INIS)

    Albright, S.; Seviour, R.

    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 "2"4Na, based on the isotopes produced in pharmaceuticals and medical devices. For both the total activity and the ingestion dose we show that a variety of isotopes contribute and that "2"4Na is only dominant under certain conditions. The composition of the foods has a strong influence on the resulting activity and ingestion dose suggesting that the pharmaceuticals and medical devices considered initially are not a viable analogue for foodstuffs. There is an energy dependence to the isotopes produced due to the cross-sections of different reactions varying with neutron energy. We show that this results in different isotopes dominating the ingestion dose at different energies, which has not been considered in the previous literature. - Highlights: • We show that neutron interrogation of food can produce many radioisotopes. • We show a strong dependance between food and certain radioisotopes. • Some isotopes are shown to have an energy dependence. • Previous claims that 24Na is the main threat is shown to only apply in special cases.

  9. Feasibility studies on the production of essential radioisotopes (24Na and 32P) using the Ghana Miniature Neutron Source Reactor (GHARR-1)

    International Nuclear Information System (INIS)

    Dotse, S.C.

    2012-01-01

    Feasibility studies on the production of 32 P and 24 Na using a Miniature Neutron Source Reactor named Ghana Research Reactor-1 (GHARR-1) has been conducted. A theoretical model of the cyclic activation technique was developed for the simulation of specific activities under varying parameters. Specific activity values estimated for four cycles of irradiation with activation parameters falling within the specifications of the reactor were experimentally validated. Experimented results were compared to those theoretically estimated for both 24 Na and 32 P. Experimented specific activity values for both radioisotopes generally fell below their theoretical values but recorded activity build-ups from one cycle to the other. The 24 Na nuclide showed a regular pattern for the increase in specific activity from one cycle to the next with an average percentage difference of experimented to theoretical value of 19%. The 32 P nuclide showed an irregular pattern for the increase in specific activity from one cycle to the next with an average percentage difference of experimental to theoretical value of 11%. The specific activities experimentally attained, with reference to activity levels used for various applications in agriculture and industry suggests the cyclic activation technique can be used for the production of radioisotopes of appreciable activities using low power research reactors, which are characterised with limited excess core reactivity and cannot sustain long periods of irradiation. (au)

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

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the regulation for the execution of the law on the prevention of radiation injuries by radioisotopes. Terms are used in this rule for the same meanings as in the regulation. The limit of the concentration of radioisotopes in the goods contaminated by these isotopes which are not required to be sealed in containers defined by the Director General of the Science and Technology Agency is 1/10,000 of the value A 2 under the notification determining the details of technical standards concerning the transport of radioisotopes or the goods contaminated by radioisotopes outside works or enterprises. The application for the permission of transporting the goods which are highly difficult to be sealed in containers shall list names and addresses, the kinds, quantities, shapes and properties of the transported goods contaminated by radioisotopes, etc. The radiation dose rate of transported goods and vehicles under the regulation is 200 milli-rem an hour on the surfaces of these goods, vehicles and containers, and 10 milli-rem an hour at the distance of 1 meter from their surfaces. The permissible exposure dose of the persons engaging in transport is 1.5 rem a year. Dangerous goods, signs, and the application for the approval of special measures are specified, respectively. (Okada, K.)

  11. Seven Things to Know about Radioisotopes

    International Nuclear Information System (INIS)

    Henriques, Sasha

    2014-01-01

    Each atomic element knows exactly how many protons and neutrons it needs at its centre (nucleus) in order to be stable (stay in its elemental form). Radioisotopes are atomic elements that do not have the correct proton to neutron ratio to remain stable. With an unbalanced number of protons and neutrons, energy is given off by the atom in an attempt to become stable. For example, a stable carbon atom has six protons and six neutrons. Whereas its unstable (and therefore radioactive) isotope carbon-14, has six protons and eight neutrons. Carbon-14 and all other unstable elements are called radioisotopes. This movement towards stability, which involves emitting energy from the atom in the form of radiation, is known as radioactive decay. This radiation can be tracked and measured, making radioisotopes very useful in industry, agriculture and medicine

  12. Improving production of Zebra Fish Embryos in the lab

    DEFF Research Database (Denmark)

    Thomsen, Jens Peter; Adu, Robert Ohene

    2011-01-01

    in the laboratory. Culture conditions were maintained in the aquaria as stipulated in the OECD draft proposal for a new guideline on fish embryo tests. Furthermore, a sequence of steps were adopted and followed to improve upon previous work done in the lab in 2006. About 200 eggs were produced in one spawn trap......The utilization of fish embryos in toxicity testing of hazardous chemicals has recently been adopted in order to satisfy stricter rules and regulations related to using adult animals in toxicity testing. This paper presents optimising steps towards improving zebra fish embryo production...... within an hour of onset of light, an improvement over the 50-60 eggs produced in the previous work. This result demonstrates that with the right culture conditions and proper optimisation of procedure the required number of embryos needed for toxicity testing can be obtained....

  13. Irradiation facilities for the production of radioisotopes for medical purposes and for industry at the Rossendorf Research Reactor

    International Nuclear Information System (INIS)

    Hieronymus, W.

    2007-01-01

    In 1955, the Government of the German Democratic Republic initiated radioisotope production. With that decision, the following plants received their go ahead: - Research reactor with its user facilities; - Cyclotron with its specific facilities; - Institute for radiochemistry; - Library, lecture hall, workshops and administration buildings supporting the necessary scientific and administrative environment. The Zentralinstitut fuer Kerntechnik (ZfK), also known as the Central Institute for Nuclear Technology, was founded at Rossendorf near Dresden, Germany, to house all those plants. The Rossendorf Research Reactor (RFR) was constructed in 1956-1957. That endeavour was enabled by the technological support of the former USSR under a bilateral agreement which included the delivery of a 2 MW research reactor of the WWR-S design

  14. Light weight radioisotope heater unit (LWRHU) production for the Cassini mission

    International Nuclear Information System (INIS)

    Rinehart, G.H.

    1997-01-01

    The Light-Weight Radioisotope Heater Unit (LWRHU) is a [sup 238]PuO[sub 2] fueled heat source designed to provide one thermal watt in each of various locations on a spacecraft. The heat sources are required to maintain the temperature of specific components within normal operating ranges. The heat source consists of a hot- pressed [sup 238]PuO[sub 2] fuel pellet, a Pt-3ORh vented capsule, a pyrolytic graphite insulator, and a woven graphite aeroshell assembly. Los Alamos National Laboratory has fabricated 180 heat sources, 157 of which will be used on the Cassini mission

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

    International Nuclear Information System (INIS)

    2011-01-01

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

  16. 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.

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

    International Nuclear Information System (INIS)

    Pejman Rowshanfazad; Amirreza Jalilian; Mahsheed Sabet

    2004-01-01

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

  18. Hydroscoop - Bulletin of the small-scale hydraulic laboratory MHyLab; Hydroscoop - Bulletin d'information MHyLab laboratoire de petite hydraulique

    Energy Technology Data Exchange (ETDEWEB)

    Denis, V.

    2009-07-01

    This is issue Nr. 5 of the news bulletin of MHyLab, the small-scale hydraulic laboratory in Montcherand, Switzerland. The history of MHyLab development is recalled. The objective of the laboratory is given: the laboratory development of efficient and reliable turbines for the entire small-scale hydraulic range (power: 10 to 2000 kW, flow rate: 0.01 to 10 m{sup 3}/s, hydraulic head: 1 m up to more than 700 m). The first period (1997-2001) was devoted to Pelton turbines for high heads (60 to 70 m) and the second (2001-2009) to Kaplan turbines for low and very low heads (1 to 30 m). In the third period (beginning 2008) diagonal turbines for medium heads (25 to 100 m) are being developed. MHyLab designed, modelled and tested all these different types. The small-scale hydraulic market developed unexpectedly quickly. The potential of small-scale hydraulics in the Canton of Vaud, western Switzerland is presented. Three implemented projects are reported on as examples for MHyLab activities on the market place. The MHyLab staff is presented.

  19. A user-friendly nano-CT image alignment and 3D reconstruction platform based on LabVIEW

    International Nuclear Information System (INIS)

    Wang Shenghao; Wang Zhili; Gao Kun; Wu Zhao; Zhang Kai; Zhu Peiping; Wu Ziyu

    2015-01-01

    X-ray computed tomography at the nanometer scale (nano-CT) offers a wide range of applications in scientific and industrial areas. Here we describe a reliable, user-friendly, and fast software package based on LabVIEW that may allow us to perform all procedures after the acquisition of raw projection images in order to obtain the inner structure of the investigated sample. A suitable image alignment process to address misalignment problems among image series due to mechanical manufacturing errors, thermal expansion, and other external factors has been considered, together with a novel fast parallel beam 3D reconstruction procedure that was developed ad hoc to perform the tomographic reconstruction. We have obtained remarkably improved reconstruction results at the Beijing Synchrotron Radiation Facility after the image calibration, the fundamental role of this image alignment procedure was confirmed, which minimizes the unwanted blurs and additional streaking artifacts that are always present in reconstructed slices. Moreover, this nano-CT image alignment and its associated 3D reconstruction procedure are fully based on LabVIEW routines, significantly reducing the data post-processing cycle, thus making the activity of the users faster and easier during experimental runs. (authors)

  20. Crossed beam studies of O-+D2→OD-+D

    International Nuclear Information System (INIS)

    Johnson, S.G.; Kremer, L.N.; Metral, C.J.; Cross, R.J.

    1978-01-01

    Using the crossed-beam machine EVA we have measured the product angular and energy distributions of the reaction O - +D 2 →OD - +D in the relative energy range of 1.2-4.7 eV (5.7-23.1 eV LAB). Below 2.5 eV the product distribution is centered about the center of mass, indicating a long-lived complex. Above 2.5 eV the distribution slowly moves forward. Most of the available energy goes into internal energy of the products

  1. Radioisotope devices at Novo-Krivorozhskij-ore-enrichment plant

    International Nuclear Information System (INIS)

    Levitskij, V.Ya.; Kucher, V.G.; Ministerstvo Chernoj Metallurgii Ukrainskoj SSR, Dnepropetrovsk, Bazovaya Opytno-Konstruktorskaya Izotopnaya lab.)

    1975-01-01

    Use of the ''Ferrite'' analyzers, AZhR and PAZh-1 and the GR-7 gamma relay in different engineering areas of the Novo-Krivorozh ore-enrichment plant is evaluated. The ''Ferrite'' radioisotopic analyzer was designed for rapid roentgeno-radiometric determination of the total iron and iron group element contents in powdered samples of ores and products of their treatment. From the density of the flux of the characteristic radiation it is possible to determine quantitatively the content of the element of interest in the analyzed material. The radioisotpic analyzer AZhR-1 is distinguished by its high efficiency in the analysis for total iron on products of processing of iron ore raw materials. The use of this apparatus allows complete replacement of the chemical method for rapid analysis of concentrates by the roentgeno-radiometric method, which decreases the total analytical work on determination of total iron and speeds up output of information on concentrate quality. The radioisotopic gamma analyzer PAZh-1 is designed for automatic and either continuous or discrete measurement of the total iron content in iron ore materials ground to 50 mm, carried on a conveyor, without selection or preparation of the samples for analysis. The analyzer operates on the principle of measuring the average frequency of impingement on a detector of gamma quanta back-scattered by the analyzed material. This frequency is determined by the percentage content of total iron in the material. The apparatus operates continuously. The mean square deviation of the apparatus values from chemical data is 0.93% Fesub(total). Use of the apparatus greatly increases the operativeness of the control and decreases the laboriousness of raw material sampling in an engineering stream. The radioisotopic data units GR-7 are designed for control of the level of materials in hoppers for recovery and burning of agglomerates. Use of this apparatus showed its great advantage over data units of other types

  2. Shielded radioisotope generator and method for using same

    International Nuclear Information System (INIS)

    Fries, B.A.

    1976-01-01

    A nuclide generator for on-site radioisotope generation is disclosed in which the formation of a short-lived daughter radioisotope from its longer-lived parent features batch flow of eluting reagent interior of the generator in a completely shielded environment

  3. NTP Radioisotopes SOC Ltd

    International Nuclear Information System (INIS)

    Letule, T.

    2017-01-01

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

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

    International Nuclear Information System (INIS)

    1984-01-01

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

  5. Lab architecture

    Science.gov (United States)

    Crease, Robert P.

    2008-04-01

    There are few more dramatic illustrations of the vicissitudes of laboratory architecturethan the contrast between Building 20 at the Massachusetts Institute of Technology (MIT) and its replacement, the Ray and Maria Stata Center. Building 20 was built hurriedly in 1943 as temporary housing for MIT's famous Rad Lab, the site of wartime radar research, and it remained a productive laboratory space for over half a century. A decade ago it was demolished to make way for the Stata Center, an architecturally striking building designed by Frank Gehry to house MIT's computer science and artificial intelligence labs (above). But in 2004 - just two years after the Stata Center officially opened - the building was criticized for being unsuitable for research and became the subject of still ongoing lawsuits alleging design and construction failures.

  6. Advanced Stirling Convertor Development for NASA Radioisotope Power Systems

    Science.gov (United States)

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

    2015-01-01

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

  7. Therapy with high LET Radioisotopes: Can sufficient levels of attractive Auger and alpha emitters be produced to make their use practical?

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Mirzadeh, S.; Stabin, M.; Brill, A.B.

    2005-01-01

    Because of localized energy deposition within a very small volume, cellular targeted therapy with high linear energy transfer (LET) Auger-electron and alpha-particle emitting radioisotopes is of great interest. While the energy deposition from alpha particles usually encompasses several cell diameters, the dose from Auger electrons is confined to a single cell. Two major challenges for broader use of Alpha and Auger emitters are the efficient and cost effective routine production of sufficient levels of these radioisotopes, and the availability of targeting molecules to which the radioisotopes can be attached for cellular delivery of sufficient levels of activity for effective therapy. Examples of several Alpha-and Auger-emitting radioisotopes of current interest are presented. Alpha- and Auger electron-emitting radioisotopes can be produced in accelerators (A) and nuclear reactors (R), and several alpha emitter congeners (i.e. thorium-229) can be obtained from uranium decay products. The challenge for reactor production, is the availability and exploitation of methods - other then the usual radiative (n,γ) production route which will provide no-carrier-added (nca) or the high specific activity radioisotopes of interest. The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes High LET radioisotopes of current interest which are in the initial stages of development and/or which demonstrate practical use in clinical trials include several alpha-emitters, in particular bismuth-213 - and also the actinium-225 parent - astatine-211 and bismuth-212. Extensive experimental studies have been reported with Auger iododeoxyuridine (IdUR) radiolabeled with the iodine-125 emitter-labeled. However, development of production

  8. Radioisotope tracers in industrial flow studies

    International Nuclear Information System (INIS)

    Easey, J.F.

    1987-01-01

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

  9. Effects of different nitrogen sources on the biogas production - a lab-scale investigation.

    Science.gov (United States)

    Wagner, Andreas Otto; Hohlbrugger, Peter; Lins, Philipp; Illmer, Paul

    2012-12-20

    For anaerobic digestion processes nitrogen sources are poorly investigated although they are known as possible process limiting factors (in the hydrolysis phase) but also as a source for fermentations for subsequent methane production by methanogenic archaea. In the present study different complex and defined nitrogen sources were investigated in a lab-scale experiment in order to study their potential to build up methane. The outcome of the study can be summarised as follows: from complex nitrogen sources yeast extract and casamino acids showed the highest methane production with approximately 600 ml methane per mole of nitrogen, whereas by the use of skim milk no methane production could be observed. From defined nitrogen sources L-arginine showed the highest methane production with almost 1400 ml methane per mole of nitrogen. Moreover it could be demonstrated that the carbon content and therefore C/N-ratio has only minor influence for the methane production from the used substrates. Copyright © 2011 Elsevier GmbH. All rights reserved.

  10. Laboratory Accreditation Bureau (L-A-B)

    Science.gov (United States)

    2011-03-28

    to all Technical Advisors. Must agree with code of conduct, confidentiality and our mission DoD ELAP Program  ISO / IEC 17025 :2005 and DoD QSM...Additional DoD QSM requirements fit well in current 17025 process … just much, much more. Sector Specific. Outcome (L-A-B case)  83

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

    Science.gov (United States)

    Wilson, Scott D.; Wong, Wayne A.

    2015-01-01

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

  12. Trends in the development of radioisotope batteries

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  13. Applications of radioisotopes for studying refractory wear-out in Bhilai Steel Plant

    International Nuclear Information System (INIS)

    Dubey, R.S.; Bose, U.P.; Shipstone, A.J.

    1979-01-01

    In Bhilai Steel Plant, investigations were carried out to study the refractory wear-out of (i) hearth bottom of blast furnaces, (ii) roof of open hearth furnaces, and (iii) hot metal mixer lining, by using radioisotope tracer techniques with a view to evaluate the life of the refractory lining at various locations and to help in planning its timely hot and cold repairs. The life of the refractory lining has the effective bearing on the overall production and hence on the economy of the plant. The two radiometric methods employed for studying the erosion of the refractory lining, by using isotope inserted bricks at various positions without damaging the lining are (i) based on recording the penetration of gamma rays emitting from the radioactive isotopes inserted at definite points of the brick lining and, (ii) by detecting the radioactivity of the pig iron or steel arising due to washing away of the respective radioactive isotopes previously inserted in the lining. In hot mixers also radioisotope sources were placed in the critical location of refractory lining and the washing out of radioisotope due to refractory brick wear out was detected by radiogauging at site. It has been found that radiotracer technique with periodic radiogauging is very useful method for tracing the radioisotope source if more than one refractory brick with isotope is placed, as in the case of open hearth furnaces. The results of radioanalysis revealed that radioactivity coming alongwith hot metal steel has been far below the permissible limit of concentration i.e. 20 micro-curie per ton of metal. Further, during dismantling of the residual refractory lining of open hearth furnaces or hot metal mixers, bricks containing radioisotopes have been successfully retrieved for safe disposal. (auth.)

  14. Optimization of periodical interrogation of transducers of radioisotope measuring systems

    International Nuclear Information System (INIS)

    Ivashchenko, A.S.; Kaznakov, V.P.; Korolev, V.M.

    1978-01-01

    Certain methods are examined of optimizing periodic interrogation of sensors connected in a definite sequence to device for data processing in a system for controlling production processes. It is shown that in designing multiinput radioisotope measurement systems with a centralized data processing, the choice of the method of organizing periodic interrogation should be made with account for the conditions existing in each specific case

  15. Orodispersible films: Product transfer from lab-scale to continuous manufacturing.

    Science.gov (United States)

    Thabet, Yasmin; Breitkreutz, Joerg

    2018-01-15

    Orodispersible films have been described as new beneficial dosage forms for special patient populations. Due to various production settings, different requirements on film formulations are required for non- continuous and continuous manufacturing. In this study, a continuous coating machine was qualified in regards of the process conditions for film compositions and their effects on the formed films. To investigate differences between both manufacturing processes, various film formulations of hydrochlorothiazide and hydroxypropylcellulose (HPC) or hydroxypropylmethycellulose (HPMC) as film formers were produced and the resulting films were characterized. The qualification of the continuously operating coating machine reveals no uniform heat distribution during drying. Coating solutions for continuous manufacturing should provide at least a dynamic viscosity of 1 Pa*s (wet film thickness of 500 μm, velocity of 15.9 cm/min). HPC films contain higher residuals of ethanol or acetone in bench-scale than in continuous production mode. Continuous production lead to lower drug content of the films. All continuously produced films disintegrate within less than 30 s. There are observed significant effects of the production process on the film characteristics. When transferring film manufacturing from lab-scale to continuous mode, film compositions, processing conditions and suitable characterization methods have to be carefully selected and adopted. Copyright © 2017 Elsevier B.V. All rights reserved.

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

    International Nuclear Information System (INIS)

    Pike, V.W.

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    1980-06-01

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

  18. Cadeia do biodiesel da bancada à indústria: uma visão geral com prospecção de tarefas e oportunidades para P&D&I Biodiesel chain from the lab bench to the industry: an overview with technology assesment, R&D&I opportunities and tasks

    Directory of Open Access Journals (Sweden)

    Cristina M. Quintella

    2009-01-01

    Full Text Available Contextualized overview of the Biodiesel Production Chain, from the lab bench to the industry, with critical evaluation of state-of-art and technological development through scientific articles and patents, focusing on feedstock, reaction/production, first and second generation processes, specification and quality, transport, storage, co-products (effluents and sub-products, and emissions. Challenges are identified and solutions are proposed based on the Brazilian feedstock, edaphoclimatic conditions, process monitoring in remote regions, state policy, and environment preservation, among others. Forecasts are made based on the technology assessment, identifying future trends and opportunities for R&D&I.

  19. Environment monitoring using LabVIEW

    International Nuclear Information System (INIS)

    Hawtree, J.

    1995-01-01

    A system has been developed for electronically recording and monitoring temperature, humidity, and other environmental variables at the Silicon Detector Facility located in Lab D. The data is collected by LabVIEW software, which runs in the background on an Apple Macintosh. The software is completely portable between Macintosh, MS Windows, and Sun platforms. The hardware includes a Macintosh with 8 MB of RAM; an external ADC-1 analog-to-digital converter that uses a serial port; LabVIEW software; temperature sensors; humidity sensors; and other voltage/current sensing devices. ADC values are converted to ASCII strings and entered into files which are read over Ethernet. Advantages include automatic logging, automatic recovery after power interruptions, and the availability of stand-alone applications for other locations with inexpensive software and hardware

  20. A Well-Maintained Lab Is a Safer Lab. Safety Spotlight

    Science.gov (United States)

    Walls, William H.; Strimel, Greg J.

    2018-01-01

    Administration and funding can cause Engineering/Technology Education (ETE) programs to thrive or die. To administrators, the production/prototyping equipment and laboratory setting are often viewed as the features that set ETE apart from other school subjects. A lab is a unique gift as well as a responsibility. If an administrator can see that…

  1. Radioisotope applications in petroleum and gas industries

    International Nuclear Information System (INIS)

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

    1974-01-01

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

  2. From 1962 the teaching of Methodology of Radioisotopes is continuous in the University of Buenos Aires of the Argentine Republic

    International Nuclear Information System (INIS)

    Rivera, E.; Cremaschi, G.; Martin, G.; Zubillaga, M.; Cricco, G.; Davio, C.; Genaro, A.; Bianchin, A.; Mohamad, N.; Klecha, A.; Calmanovici, G.; Goldman, G.; Salgueiro, J.; Nunez, M.; Medina, V.; Gutierrez, A.; Leonardi, N.; Bergoc, R.

    2006-01-01

    In the Faculty of Pharmacy and Biochemistry of the University of Buenos Aires the teaching of the radioisotopes began in 1960 and uninterruptedly continuous. The application of the radioisotopes and the radiations in different professional activities it is acceptable only in a context of radiological safety and with personal appropriately trained. Conscious of it, the training in grade, postgraduate and technicature, has more of 40% of the thematic one guided to the formation in radiological protection. The courses dictated at the moment in the Laboratory of Radioisotopes they include: Grade formation: to) Subject grade 'Methodology of Radioisotopes' in the Career of Biochemistry: it began to be dictated in 1960 and until the present, more of 6500 students they have gone by our classrooms. b) Grade subject 'Radiopharmacy' in the Career of Pharmacy: guided to the formation of a modern pharmacist, with necessary knowledge to be developed as professional in the Radiopharmaceutical area. Postgraduate formation: c) Postgraduate course of Methodology of Radioisotopes specially directed to biochemical, biologists, veterinarians, chemical. It is dictated uninterruptedly from 1962. d) Postgraduate course in Methodology of Radioisotopes for medical professionals, specially directed to professionals of the medicine that want to specialize in different branches of the Nuclear Medicine. Both courses have 220 present hours and it stops their approval the assistants they should surrender a final exam at open book that consists on the resolution of a practical exercise adapted to their professional practices. Until the present they have surrendered their exams satisfactorily approximately 2000 professionals coming from different areas of the Argentina and of several countries of Hispanic speech. e) Starting from 1992 the Course of Upgrade in Methodology of Radioisotopes directed to professionals that want to upgrade its knowledge in new radioisotopic methodologies is dictated

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

    International Nuclear Information System (INIS)

    Jeanmaire, L.; Michon, G.

    1959-01-01

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

  4. Thyroid Dose Estimation Using WBC and I-131 Concentration in Working Area of Radioisotope Production at Normal Operation; Perkiraan Dosis Thyroid Melalui Pengukuran WBC dan Perhitungan dengan Konsentrasi I-131 Di Daerah Kerja Pada Operasi Normal Produksi Radioisotop

    Energy Technology Data Exchange (ETDEWEB)

    Tedjasari, R S; Lubis, E [Radioactive-Waste Management Technology Centre, National Atomic Energy Agency of Indonesia(Indonesia)

    1996-07-01

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

  5. Application of radioisotopes to studies of crystal imperfections; Application des radioisotopes a l'etude des imperfections des cristaux; Primenenie radioizotopov dlya izucheniya defektov v kristallakh; Aplicaciones de los radioisotopos al estudio de las imperfecciones cristalinas

    Energy Technology Data Exchange (ETDEWEB)

    Sproull, R L; Slack, G A; Moss, M; Pohl, R O; Krumhansl, J A [Laboratory of Atomic and Solid State Physics, Cornell University, Ithaca, NY (United States)

    1962-01-15

    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 Ca{sup 45}. This work is reviewed and some current and possible future applications of radioisotopes in this field are mentioned. (author) [French] Les radioisotopes ont recu deux applications importantes dans l'etude des imperfections des cristaux d'halogenures alcalins. Employes comme indicateurs, ils ont permis de controler le raffinage par zones des composes et, par suite, de determiner les coefficients de segregation. La deuxieme application a consiste a introduire dans les halogenures alcalins de faibles concentrations d'ions sous forme d'impuretes afin d'etudier la diffusion des phonons par ces impuretes ou par les lacunes que celles-ci produisent; les mesures sont effectuees a des temperatures tres basses, auxquelles le libre parcours moyen des phonons se trouve limite par les imperfections du reseau. Le radioisotope le plus frequemment employe pour ces operations a ete le {sup 45}Ca. Le memoire passe en revue ces divers travaux et signale quelques applications effectives ou possibles des radioisotopes dans le domaine considere. (author) [Spanish] Los autores han empleado radioisotopos en dos importantes campos del estudio de los cristales de haluros alcalinos. Uno de estos campos es el control de la purificacion por zonas de los compuestos y la determinacion de los coeficientes de segregacion por medida de las actividades de los

  6. The Synthesis And Characterization Of Wolfram Phthalocyanine For The Target Material Of High Specific Activity Radioisotope Wolfram - 188 (188W)

    International Nuclear Information System (INIS)

    Setiawan, Duyeh

    2000-01-01

    The application of 188 Re radioisotope separation on aluminia column through elution solution has increased significantly since the last two decades. The 188 Re radioisotope has been done fram 188 Re beta-decay through a neutron capture radiation on wolfram -186 target. In trhe column separation, high specific activity of 188 W radioisotope is required to get sufficient activity in small quality 188 W radioisotope has been carried out in this research. Wolfram-phthalocyanine compound was prepared by refluxing a mixture of wolfram trioxyde, (WO 3 ) and phthalonitrile, (C 8 H 4 N 2 ) at 250 o C for two hours. The synthesis of wolfram phthalocyanine is 70% purity yield, the product are green crystals, have a 193,0-193,8 o C melting points, and has a molecular formula C 3 2H 1 6 N8 WO 2 . The infra red spectrum of wolfram-phthalocyanine was the absorption band at 964,3 cm - 1 was due to the vibration of W=O bond of the wolfram dioxy-phthalocyanine. The x-ray diffraction of the wolfram dioxy-phthalocyanine was similar with molybdenum dioxy-phthalocyanine compound. This fact showed that the product was wolfram dioxy-phthalocyanine

  7. Internal dose evaluation of workers involved in radioisotopes and radiopharmaceuticals handling for medical use

    International Nuclear Information System (INIS)

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

    1987-01-01

    The internal dose levels of IPEN workers, involved in the production of radioisotopes and radiopharmaceuticals for medical use are surveyed. In this production, the workers were splited in six group: research and development, routine production, quality control, packaging, radiological protection and maintenance. The internal dose was evaluated according to the models described by ICRP-30, from the results obtained in the whole body counters monitoring. (C.G.C.) [pt

  8. The analysis and investigation on basic data for development status study on the radioisotope industry

    International Nuclear Information System (INIS)

    Kim, In Hwan; Shim, H. S.; Chun, I. Y.; Jang, J. H.

    2005-12-01

    This study is intended to investigate and analysis the use degree of the radioisotope in domestic industry by the data of indirect information in focus of industry using the radioisotope per year basis. The contents and scope of this study is as follows: - Review of the industry sorting methods and application of the UNIDO(United Nation Industry Development organization). - Investigation of RI permitted companies and notified companies by 2003. 12. 31. - The Analysis and investigation of the basic data for the number of workers, wages and salaries of employees, product costs and the value added etc. of RI permitted companies from 1980

  9. Management system in the dose assessment due to the intake of "1"3"1I in occupationally exposed workers (OEW) in a radioisotope production plant

    International Nuclear Information System (INIS)

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

    2015-01-01

    This article presents the evaluation and management processes due to the incorporation of "1"3"1I in occupationally exposed workers (OEW) of a Radioisotope Production Plant by in vivo measurement of the retained activity of this radionuclide in thyroid. The procedures for the occupational control of the OWE were established, including intermediate checks and calibration of the equipment according to the NTP ISO/IEC 17025:2006 standard. (author)

  10. 3D modelling of plug failure in resistance spot welded shear-lab specimens (DP600-steel)

    DEFF Research Database (Denmark)

    Nielsen, Kim Lau

    2008-01-01

    are based on uni-axial tensile testing of the basis material, while the modelled tensile response of the shear-lab specimens is compared to experimental results for the case of a ductile failure near the heat affected zone (HAZ). A parametric study for a range of weld diameters is carried out, which makes......Ductile plug failure of resistance spot welded shear-lab specimens is studied by full 3D finite element analysis, using an elastic-viscoplastic constitutive relation that accounts for nucleation and growth of microvoids to coalescence (The Gurson model). Tensile properties and damage parameters...... it possible to numerically relate the weld diameter to the tensile shear force (TSF) and the associated displacement, u (TSF) , respectively. Main focus in the paper is on modelling the localization of plastic flow and the corresponding damage development in the vicinity of the spot weld, near the HAZ...

  11. A Review of the Production of ''Special'' Radioisotopes; La Production de Radioisotopes «Spéciaux»; ОБЗОР ПРОИЗВОДСТВА ''СПЕЦИАЛЬНЫХ'' ИЗОТОПОВ; Produccion de Radioisotopos ''Especiales''

    Energy Technology Data Exchange (ETDEWEB)

    Stang, Jr., L. G. [Brookhaven National Laboratory, Upton, NY (United States)

    1963-03-15

    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 Ag{sup 110}, In{sup 114}, {sup 116}, Dy{sup 155m}, 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

  12. Agricultural application of radioisotopes

    International Nuclear Information System (INIS)

    Agrawal, H.M.

    2001-01-01

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

  13. Random-process excursions in radioisotope instruments

    International Nuclear Information System (INIS)

    Galochkin, D.V.; Polovko, S.A.

    1984-01-01

    Approximate expressions are derived for the mathematical expectation, variance, and distribution of the durations of the excursions of the output signal from a ratemeter in a radioisotope relay instrument. The tabulated comparison of results from Monte Carlo simulation and analytical calculation shows good agreement over the mean value and the variance of the excursion duration for T 0.2 sec as calculated and as obtained by Monte Carlo simulation with a computer using 5000 realizations. It is suggested that the results should be used in choosing the optimum parameters of radioisotope relay instruments

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

    Westmacott, Chad; Cameron, Ron

    2012-01-01

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

  16. Semi-industrial scale (30 m3) fed-batch fermentation for the production of D-lactate by Escherichia coli strain HBUT-D15.

    Science.gov (United States)

    Fu, Xiangmin; Wang, Yongze; Wang, Jinhua; Garza, Erin; Manow, Ryan; Zhou, Shengde

    2017-02-01

    D(-)-lactic acid is needed for manufacturing of stereo-complex poly-lactic acid polymer. Large scale D-lactic acid fermentation, however, has yet to be demonstrated. A genetically engineered Escherichia coli strain, HBUT-D, was adaptively evolved in a 15% calcium lactate medium for improved lactate tolerance. The resulting strain, HBUT-D15, was tested at a lab scale (7 L) by fed-batch fermentation with up to 200 g L -1 of glucose, producing 184-191 g L -1 of D-lactic acid, with a volumetric productivity of 4.38 g L -1  h -1 , a yield of 92%, and an optical purity of 99.9%. The HBUT-D15 was then evaluated at a semi-industrial scale (30 m 3 ) via fed-batch fermentation with up to 160 g L -1 of glucose, producing 146-150 g L -1 of D-lactic acid, with a volumetric productivity of 3.95-4.29 g L -1  h -1 , a yield of 91-94%, and an optical purity of 99.8%. These results are comparable to that of current industrial scale L(+)-lactic acid fermentation.

  17. In vivo evaluation of biosensors volumetric bio-distribution for measurement of metabolic activity by X-ray correlation, fluorescence, Cerenkov image and radioisotope; Evaluacion in vivo de la biodistribucion volumetrica de biosensores para medicion de la actividad metabolica por correlacion de rayos X, fluorescencia, imagen Cerenkov y radioisotopica

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez N, G. J.

    2016-07-01

    The aim of this study was to characterize the in vivo volumetric distribution of three folate based biosensors by different imaging modalities (X-ray, fluorescence, Cerenkov luminescence and radioisotopic imaging) through the development of a tri dimensional (3D) image reconstruction algorithm. The preclinical and multimodal Xtreme imaging system, with a Multimodal Animal Rotation System (Mars), was used to acquire bidimensional (2D) images, which were processed to obtain the 3D reconstruction. Images of mice at different times (biosensor distribution) were simultaneously obtained from the four imaging modalities. The filtered backprojection and inverse Radon transformation were used as main image-processing techniques. In the first instance, the algorithm developed in Mat lab was able to reconstruct in the 3D form the skeleton of the mice under study. Subsequently, the algorithm was able to get the volumetric profiles of {sup 99m}Tc-Folate-Bombesin (radioisotopic image), {sup 177}Lu-Folate-Bombesin (Cerenkov image), and FolateRSense 680 (fluorescence image) in the tumors and kidneys of the mice. No significant differences were detected between the volumetric quantifications using the standard measurement techniques and the quantifications obtained with the proposal made in this study, nor between the volumetric uptakes in the structures of interest. With the structures reconstructed in the 3D form, the fusion of anatomical (as the skeleton) and functional structures derived from the images of the biosensors uptake was achieved The imaging 3D reconstruction algorithm can be easily extrapolated to different 2D acquisition-type images. This characteristic flexibility of the algorithm developed in this study is an advantage in comparison to similar reconstruction methods. (Author)

  18. Advanced Radioisotope Power Systems Segmented Thermoelectric Research

    Science.gov (United States)

    Caillat, Thierry

    2004-01-01

    Flight times are long; - Need power systems with >15 years life. Mass is at an absolute premium; - Need power systems with high specific power and scalability. 3 orders of magnitude reduction in solar irradiance from Earth to Pluto. Nuclear power sources preferable. The Overall objective is to develop low mass, high efficiency, low-cost Advanced Radioisotope Power System with double the Specific Power and Efficiency over state-of-the-art Radioisotope Thermoelectric Generators (RTGs).

  19. Work Began on Contracts for Radioisotope Power Conversion Technology Research and Development

    Science.gov (United States)

    Wong, Wayne A.

    2005-01-01

    NASA has had a history of successful space flight missions that depended on radioisotope-fueled power systems. These Radioisotope Power Systems (RPSs) converted the heat generated from the decay of radioisotope material into useful electrical power. An RPS is most attractive in applications where photovoltaics are not optimal, such as deep-space applications where the solar flux is too low or extended applications on planets such as Mars where the day/night cycle, settling of dust, and life requirements limit the usefulness of photovoltaics. NASA s Radioisotope Power Conversion Technology (RPCT) Program is developing next-generation power-conversion technologies that will enable future missions that have requirements that cannot be met by the two RPS flight systems currently being developed by the Department of Energy for NASA: the Multi-Mission Radioisotope Thermoelectric Generator and the Stirling Radioisotope Generator (SRG).

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

    International Nuclear Information System (INIS)

    1965-01-01

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

  1. Application of static electricity radioisotope eliminators in oil-processing and petrochemical industry

    International Nuclear Information System (INIS)

    Zhuravlev, V.S.; Evmenov, A.K.; Bondarev, L.M.; Kharlamov, O.V.

    1977-01-01

    Examples are discussed of the use of radioisotope eliminators of the static electricity on the basis of the 239 Pu apha radiation sources in the technological processes of the production and processing synthetic caoutchoucs, rubbers and film materials. The efficiency of different types of eliminators is testified; prospects of their application in the industry are outlined

  2. Control of radioisotopes and radiation sources in Indonesia

    International Nuclear Information System (INIS)

    Ridwan, M.

    2001-01-01

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

  3. New Directions In Radioisotope Spectrum Identification

    International Nuclear Information System (INIS)

    Salaymeh, S.; Jeffcoat, R.

    2010-01-01

    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.

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

    CERN Document Server

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

    2016-01-01

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

  5. Radiopharmaceuticals labelled with positron-emitting radioisotopes

    International Nuclear Information System (INIS)

    Comar, D.; Berridge, M.; Maziere, B.; Crouzel, C.

    1982-01-01

    This chapter reviews the preparation of radioisotopes for biochemical and physiological studies and the principal methods for their incorporation into radiopharmaceuticals, while pointing out the problems encountered with their use and considering their medical interest in the following areas: distribution and flow of fluids, metabolic and pharmacokinetic studies. Inorganic and organic radiopharmaceuticals presently in use and most probable to be used in the future are reviewed. It is anticipated that three types of products labelled with 15 O, 13 N, 11 C and 18 F will be developed in the future. The first type includes products which trace general phenomena such as fluid movement or metabolism of sugars, fats and proteins. The compromise between physiological accuracy and imaging technology is discussed in relation to the use of 11 C and 18 F. The second type of product is one to measure more specific parameters such as those of molecular transport kinetics, membrane permeability, cellular pH and receptor-ligand interactions, again with particular reference to 11 C and 18 F. The third type of product discussed is that intended for pharmacology studies, particular reference being made to 68 Ga, 82 Rb. Extensive bibliography. (U.K.)

  6. Technology Roadmap: Lab-on-a-Chip

    OpenAIRE

    Pattharaporn Suntharasaj; Tugrul U Daim

    2010-01-01

    With the integration of microfluidic and MEMS technologies, biochips such as the lab-on-a-chip (LOC) devices are at the brink of revolutionizing the medical disease diagnostics industries. Remarkable advancements in the biochips industry are making products resembling Star Trek.s "tricorder" and handheld medical scanners a reality. Soon, doctors can screen for cancer at the molecular level without costly and cumbersome equipments, and discuss treatment plans based on immediate lab results. Th...

  7. 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.

  8. Metabolic engineering of strains: from industrial-scale to lab-scale chemical production.

    Science.gov (United States)

    Sun, Jie; Alper, Hal S

    2015-03-01

    A plethora of successful metabolic engineering case studies have been published over the past several decades. Here, we highlight a collection of microbially produced chemicals using a historical framework, starting with titers ranging from industrial scale (more than 50 g/L), to medium-scale (5-50 g/L), and lab-scale (0-5 g/L). Although engineered Escherichia coli and Saccharomyces cerevisiae emerge as prominent hosts in the literature as a result of well-developed genetic engineering tools, several novel native-producing strains are gaining attention. This review catalogs the current progress of metabolic engineering towards production of compounds such as acids, alcohols, amino acids, natural organic compounds, and others.

  9. Radioisotopes in Hydrology. Proceedings of a Symposium

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-08-15

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

  10. Digital Design with KP-Lab

    Directory of Open Access Journals (Sweden)

    D. Ponta

    2007-08-01

    Full Text Available KP-Lab is an EU Integrated Project envisioning a learning system that facilitates innovative practices of sharing, creating and working with knowledge in education and workplaces. The project exploits a novel pedagogical view, the knowledge-creation metaphor of learning. According to such “trialogical” approach, cognition arises through collaborative work in systematically developing shared “knowledge artefacts”, such as concepts, plans, material products, or social practices. The paper presents the plan of a pilot course to test the KP-Lab methodologies and tools in the field of Digital Design.

  11. Application of radioisotope technique for investigation of pumps seals

    International Nuclear Information System (INIS)

    Antoszewski, B.; Zorawska, A.

    1988-01-01

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

  12. Safety regulations for radioisotopes, etc. (interim report)

    International Nuclear Information System (INIS)

    1980-01-01

    An (interim) report by an ad hoc expert committee to the Nuclear Safety Commission, on the safety regulations for radioisotopes, etc., was presented. For the utilization of radioisotopes, etc., there is the Law Concerning Prevention of Radiation Injury Due to Radioisotopes, etc. with the advances in this field and the improvement in international standards, the regulations by the law have been examined. After explaining the basic ideas of the regulations, the problems and countermeasures in the current regulations are described: legal system, rationalization in permission procedures and others, inspection on RI management, the system of the persons in charge of radiation handling, RI transport, low-level radioactive wastes, consumer goods, definitions of RIs, radiation and sealed sources, regulations by group partitioning, RI facilities, system of personnel exposure registration, entrusting of inspection, etc. to private firms, and reduction in the works for permission among governmental offices. (author)

  13. Radioisotope Power Systems Technology Development

    Data.gov (United States)

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

  14. Radioisotopic heat source

    Science.gov (United States)

    Jones, G.J.; Selle, J.E.; Teaney, P.E.

    1975-09-30

    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 1570$sup 0$F to about 1720$sup 0$F for about one h. (auth)

  15. Challenges of building and sustaining living labs for designing services and products

    DEFF Research Database (Denmark)

    Subasi, Özge; Werner, Katharina; Fitzpatrick, Geraldine

    2016-01-01

    In this paper, we show examples from one of the living labs from the Give&Take project and discuss the observed challenges of establishing and sustaining living labs in a participatory design context. The observations we present are around the mismatch between research language and everyday...

  16. Development Labs: University Knowledge Production and Global Poverty

    Science.gov (United States)

    Collins, Christopher S.

    2017-01-01

    In 2012, the United States Agency for International Development allocated $137 million to fund seven universities to create "development labs" to advance social/economic progress and reduce poverty. International economic development has become a booming field and industry but is also highly contested. The function of the university as a…

  17. Study on the status of radiation/radioisotope utilization during the last 5 years

    International Nuclear Information System (INIS)

    Lee, Yun Jong; Park, Tae Jin; Kuk, Il Hiun

    2007-01-01

    The objectives of this study is derivation of important indices for establishing government policy to promote radiation and radioisotope utilization and for setting up effective strategy o develop related industries, on the basis of utilization data, and deduction of economic scale induced by using radiation and radioisotope, through the analysis of economic contribution by multi-variate model. Uses of radiation and radioisotopes are increasing annually in Korea, and the effect of utilization to economy and industry is continuously enlarged in accordance with technology development and expansion of radiation and radioisotope uses. Indices related to radiation nd radioisotope uses, which are useful for the promotion of utilization and establishment of development strategy, have to be derived and updated every year. Important indices related to radiation and radioisotope utilization are derived through the study. The indices are useful for planning establishing, and revising policies to promote radiation and radioisotope utilization, and re furthermore valuable for public acceptance nuclear energy

  18. Hygienic efficiency of radioisotope instruments application in motor-car industry

    International Nuclear Information System (INIS)

    Tolokonnikov, M.I.; Lev, M.Ya.; Liberman, A.N.; Chictov, E.D.

    1978-01-01

    At the Moscow Automobile Works named after I.A. Likhachev, an analysis was made of the hygienic and technologic-economic benefits from use of radioisotope instruments. Radioisotopic sources of radiation are used for research and measuring purposes in various automatic control and monitoring systems, and in evaluating the effectiveness of cleaning facilities. The application of radioisotopic instruments contributes to achieving the maximum possible efficiency of the equipment, to the improvement of working conditions, and to the prevention of environmental pollution

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

    International Nuclear Information System (INIS)

    1983-04-01

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

  20. The Research and Development of the Radioisotope Energy Conversion System

    International Nuclear Information System (INIS)

    Steinfelds, E.V.; Ghosh, T.K.; Prelas, M.A.; Tompson, R.V.; Loyalka, S.K.

    2001-01-01

    The project of developing radioisotope energy conversion system (RECS) involves analytical computational assisted design and modeling and also laboratory research. The computational analysis consists of selecting various geometries and materials for the main RECS container and the internally located radioisotope, computing the fluxes of the beta (-) particles and of the visible (or ultraviolet) photons produced by the beta (-) s, computing the transport of these photons to the photovoltaic cells, and computing the overall efficiency of useful conversion of the radioisotope power

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

    International Nuclear Information System (INIS)

    Gardner, Robin P.; Lee, Kyoung O.

    2015-01-01

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

  2. Technical diagnosis of industrial plants with radioisotopes

    International Nuclear Information System (INIS)

    Hartmann, G.

    1984-01-01

    A survey is given of the application of radioisotopes in technical diagnosis of industrial plants. Proceeding from the economic importance and the state of the art of radioisotope applications, the principles of tracer techniques are outlined including topical examples of application such as passage of coal through a steam generator, wear in impact crashing of coal, wear and corrosion in pipelines, testing the effective cross section of pipes, and investigations of microstructures. Limits and restrictions of applications are briefly discussed

  3. Radioisotope sources for X-ray fluorescence analysis

    International Nuclear Information System (INIS)

    Leonowich, J.; Pandian, S.; Preiss, I.L.

    1977-01-01

    Problems involved in developing radioisotope sources and the characteristics of potentially useful radioisotopes for X-ray fluorescence analysis are presented. These include the following. The isotope must be evaluated for the physical and chemical forms available, purity, half-life, specific activity, toxicity, and cost. The radiation hazards of the source must be considered. The type and amount of radiation output of the source must be evaluated. The source construction must be planned. The source should also present an advance over those currently available in order to justify its development. Some of the isotopes, which are not in use but look very promising, are indicated, and their data are tabulated. A more or less ''perfect'' source within a given range of interest would exhibit the following characteristics. (1) Decay by an isometric transition with little or no internal conversion, (2) Have an intense gamma transition near the absorption edge of the element(s) of interest with no high energy gammas, (3) Have a sufficiently long half-life (in the order of years) for both economic and calibration reasons, (4) Have a sufficiently large cross-section for production in a reasonable amount of time. If there are competing reactions the interfering isotopes should be reasonably short-lived, or if not, be apt to be separated from the isotope chemically with a minimum of difficulty. (T.G.)

  4. Radioisotopes labelled agrochemicals for fertiliser development

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  5. Radioisotope studies under pathologic conditions

    International Nuclear Information System (INIS)

    DeRossi; Salvatori, M.; Valenza, V.

    1987-01-01

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

  6. An Updated Comprehensive Risk Analysis for Radioisotopes Identified of High Risk to National Security in the Event of a Radiological Dispersion Device Scenario

    Science.gov (United States)

    Robinson, Alexandra R.

    An updated global survey of radioisotope production and distribution was completed and subjected to a revised "down-selection methodology" to determine those radioisotopes that should be classified as potential national security risks based on availability and key physical characteristics that could be exploited in a hypothetical radiological dispersion device. The potential at-risk radioisotopes then were used in a modeling software suite known as Turbo FRMAC, developed by Sandia National Laboratories, to characterize plausible contamination maps known as Protective Action Guideline Zone Maps. This software also was used to calculate the whole body dose equivalent for exposed individuals based on various dispersion parameters and scenarios. Derived Response Levels then were determined for each radioisotope using: 1) target doses to members of the public provided by the U.S. EPA, and 2) occupational dose limits provided by the U.S. Nuclear Regulatory Commission. The limiting Derived Response Level for each radioisotope also was determined.

  7. Radioisotopes and radiation technology

    International Nuclear Information System (INIS)

    Ramamoorthy, N.

    2011-01-01

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

  8. 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.

  9. Assessment of DoD’s Central Identification Lab and the Feasibility of Increasing Identification Rates

    Science.gov (United States)

    2009-06-01

    Lab and the Feasibility of Increasing Identification Rates David R. Graham Ashley N. Bybee Susan L. Clark-Sestak Michael S. Finnin Approved for public...Feasibility of Increasing Identification Rates David R. Graham Ashley N. Bybee Susan L. Clark-Sestak Michael S. Finnin iii PREFACE This study was...6 . A U TH O R ( S ) 5 d . P R O JE C T N O. David R. Graham, Ashley N. Bybee , Susan L. Clark-Sestak, Michael S. Finnin 5 e . TAS K N O

  10. Radioisotope labelling of several major insect pest

    International Nuclear Information System (INIS)

    Sutrisno, Singgih

    1981-01-01

    Radioisotope uptake by insects could take place through various parts i.e. mouth, cuticula, intersegmental, secretion and excretion organs. Usually insects are labelled internally by feeding them on an artificial diet containing radioisotope solution. Labelling of several insect pests of cabbage (Crocidolomia binotalis) Zell and Plutella maculipennis Curt and rice (Chilo suppressalis Walker) by dipping of the pupae in 32 P solution showed a promising result. Pupae of Crocidolomia binotalis Zell dipped in 3 ml solution of 32 P with specific activities of 1, 3, 5 and 7 μCi/ml had developed labelled adults of sufficiently high radioactivity levels for ecological studies. Similar results were also obtained with Plutella maculipennis Curt and Chilo suppressalis Walker with doses of 1, 3, 5, 7 and 9 μCi/ml 32 P solution. The best doses for radioisotope labelling by dipping of the insects Crocidolomia binotalis Zell, Plutella maculipennis Curt, and Chilo suppressalis Walker were 1, 9, and 7 μCi/ml respectivelly. (author)

  11. Utilization of radioisotopes and irradiation in crop protection research

    International Nuclear Information System (INIS)

    Ong, S.H.

    1981-01-01

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

  12. The use of radioisotope tracers in the metallurgical industries

    International Nuclear Information System (INIS)

    Easey, J.F.

    1987-01-01

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

  13. Remembering the early days of the Met Lab

    International Nuclear Information System (INIS)

    Katz, J.J.

    1990-01-01

    The Met Lab was set up by the war-time Manhattan District, US Corp of Engineers to (i) find a system using normal uranium in which a chain reaction would occur; (ii) to show that if such a chain reaction did occur, it would be possible to separate plutonium chemically from the uranium matrix and the fission products formed in the chain reactions; and (iii) to prepare plans for the large-scale production of plutonium. Chemistry Section C-1 of the Met Lab was assigned the responsibility for developing separation methods for plutonium production on the industrial scale. This report describes some aspects of daily life in Section C-1

  14. Industrial applications of radioisotope techniques in Poland

    International Nuclear Information System (INIS)

    Michalik, J.St.

    1985-01-01

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

  15. Clinical evaluation of radioisotope examination in oncology

    Energy Technology Data Exchange (ETDEWEB)

    Yasukochi, H [National Konodai Hospital (Japan)

    1979-07-01

    Although many approaches are tried for the diagnoses of malignant tumor, radiological examinations act surely main parts. Among the radiological examinations, radioisotope techniques are not well evaluated instead of their usefulness in this field. The reason may depend on the complexity and difficulty in legal limitations, however, the lack of knowledge in this field is also a main reason. In this paper, the present status of the evaluation of radioisotope techniques is discussed in selected region of the body and some characteristic cases are demonstrated.

  16. Radioisotopes in Burmese agricultural research

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-07-15

    The Burmese authorities decided to start a laboratory for the use of radioisotope techniques in agricultural r e search. The laboratory was set up at the Agricultural Research Institute at Gyogon, on the outskirts of Rangoon. Under its technical assistance program, IAEA assigned an expert in the agricultural applications of radioisotopes for this project. Discussions were held with regional representatives of the Food and Agriculture Organization on the best lines of research to be adopted at the laboratory in its early stages. As the most important crop in Burma is rice, a series of experiments were planned for a study of the nutrition of rice, particularly its phosphorus uptake, with special reference to comparative responses on a range of typical paddy soils. The experiments began last year and are being continued.

  17. Use of radioisotopes in Japan

    International Nuclear Information System (INIS)

    Foeldiak, G.

    1974-01-01

    A survey of the following general data on the use of radioisotopes in Japan is given (from the material of the 11th Japan Conference on Radioisotopes): 1. number of the organizations using radioactive isotopes, grouped according to special working fields and instruments; 2. amount of the unsealed sources (Ci) used in the different special working fields in 1971, 4. amount of the sealed sources (Ci) used between 1966 and 1971. 5. number of the institutions using sealed sources, grouped according to special working fields (March, 1972), 6. number of the accelerators applied, grouped according to special working fields (March, 1972), 7. number of the nuclear instruments in the education and research institutes (March, 1972), 8. amount of the collected radioactive waste material between 1960 and 1971 (number of containers). (K.A.)

  18. Injection and injection-compression moulding replication capability for the production of polymer lab-on-a-chip with nano structures

    DEFF Research Database (Denmark)

    Calaon, M.; Tosello, G.; Garnaes, J.

    2017-01-01

    The manufacturing precision and accuracy in the production of polymer lab-on-a-chip components with 100-130 nm deep nanochannels are evaluated using a metrological approach. Replication fidelity on corresponding process fingerprint test nanostructures over different substrates (nickel tool and po...

  19. Microstructural characterization of LaB6-ZrB2 eutectic composites

    International Nuclear Information System (INIS)

    Wang Shengchang; Wei, W.J.; Zhang Litong

    2003-01-01

    Detail microstructure of LaB 6 -ZrB 2 composites has been characterized by TEM and HRTEM. The directionally solidified ZrB 2 fibers in LaB 6 matrix near LaB 6 -ZrB 2 eutectics present at least three growing relationship systems. In addition to previous report of [001]LaB 6 / [0001]ZrB 2 relationship, [0 anti 11]LaB 6 / [0001]ZrB 2 and [1 anti 20]LaB 6 / [0001]ZrB 2 . were identified. Different with [001]LaB 6 / [0001]ZrB 2 system, the interfaces of [0 anti 11]LaB 6 / [0001]ZrB 2 and [1 anti 20]LaB 6 / [0001]ZrB 2 . show non-coherent and clean interfaces. There is neither glassy phase nor reaction products found at the interfaces (orig.)

  20. Calculation correlations for radioisotope level gages with relay tracing systems

    International Nuclear Information System (INIS)

    Krejndlin, I.I.; Pakhunkov, Yu.I.

    1978-01-01

    The interrelationship was examined between the operational and instrumental parameters of radioisotope tracking level indicators. The relationships were obtained permitting to check the reliability of the tracking regime, and also of the equilibrium state of the radioisotope tracking level indicator

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