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Sample records for radioisotope generator based

  1. 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

  2. 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

  3. Generation of radioisotopes

    International Nuclear Information System (INIS)

    Panek-Finda, H.

    1984-01-01

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

  4. 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

  5. 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

  6. Fuel selection for radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Menezes, A.

    1988-06-01

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

  7. Radioisotope and radiopharmaceutical generators

    International Nuclear Information System (INIS)

    Barak, M.; Winchell, H.W.

    1975-01-01

    A chromatographic column for generating technetium-99m isotopes and technetium-99m labeled pharmaceuticals in a simple two-step process is described. Technetium-99m pertechnetate in a first step is isolated by adsorption upon an adsorbent packing. Then the technetium-99m in a second step is eluted from the packing, either with an immediately labeled biological compound to form a radiopharmaceutical, or by a controlled volume of eluant to produce a 99m-technetium-bearing eluate of a desired specific concentration. (Official Gazette)

  8. Radioisotope generators for nuclear medicine based on Fajans adsorption on glass microspheres

    International Nuclear Information System (INIS)

    Ehrhardt, G.J.; Symes, S.; Guimon, R.K.; Zinn, K.R.

    1992-01-01

    Several radioisotope generator systems exist in which the carrier-free daughter product would precipitate if present in macro amounts at pH levels at which the parent is soluble. Included among these are the 68 Ge/ 68 Ga, 90 Sr/ 90 Y, and 47 Ca/ 47 Sc pairs. This paper reveals that in these systems, chemical separation can be achieved by Fajans adsorption of the radiocolloidal daughter products onto surfaces such as activated glass microspheres at an appropriate pH. This is followed by washing to remove the parent solution and desorption of the daughter crop by acid washes. Investigation of the Ge/Ga and Sr/Y systems demonstrated that this solid-phase extraction method is erratic, but can give daughter yields as high at 89% with separation factors up to ∼ 10,000 form parent isotope. This method has the potential for producing daughter isotopes with a minimum of metal and organic impurities for labeling cells, receptor binding ligands, and antibodies for diagnostic and radiotherapeutic purposes

  9. 82Sr--82Rb radioisotope generator

    International Nuclear Information System (INIS)

    Grant, P.M.; Erdal, B.R.; O'Brien, H.A.

    1976-01-01

    An improved 82 Sr- 82 Rb radioisotope generator system, based upon the complexing ion exchange resin Chelex-100, has been developed. Columns of this material can be easily and rapidly milked, and the Rb-Sr separation factor for a fresh generator was found to be greater than 10 7 . Approximately 80 percent of the 82 Rb present was delivered in a 15-ml volume of aqueous 0.2 M NH 4 Cl solution. After more than 6 liters of eluant had been put through the generator, the Rb-Sr separation factor was still observed to be greater than 10 5 , and no unusual strontium breakthrough behavior was seen in the system over nearly three 82 Sr half lives. 2 claims, no drawings

  10. 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.

  11. Development of Molybdenum Adsorbent for 99Mo/99mTc Radioisotope Generator Based on Irradiated Natural Molybdenum

    International Nuclear Information System (INIS)

    Rohadi Awaludin; Hotman Lubis; Sriyono; Abidin; Herlina; Endang Sarmini; Indra Saptiama; Hambali

    2011-01-01

    Preparation of 99 Mo/ 99m Tc radioisotope generator using irradiated natural molybdenum requires an adsorbent with high absorption capacity. Zirconium-based materials (ZBM), adsorbent with adsorption capacity of about 183 mg(Mo) / g(adsorbent), has been successfully synthesized. However, the adsorbent was easily broken in the Mo adsorption process due to many fractures in the grain. To increase the hardness, the material was immersed in tetraethyl orthosilicate (TEOS) and coated by TEOS flow in a column. The hardness test results showed that the ZBM with TEOS treatment was not broken when immersed into the Mo solution. Observations using SEM showed that the fractures formed on the ZBM were successfully removed by TEOS treatment. Measurements using EDS showed that after TEOS treatment, the silicon was detected and the oxygen content increased in the material surface. Adsorption test results showed that the TEOS immersion decreased the adsorption capacity of molybdenum from 183 to 79.8 mg of Mo per gram of adsorbent. The TEOS flow-in a column gave material with relatively high adsorption capacity, 140 mgMo per gram adsorbent. The content of Silicon in the surface was lower than that of adsorbent immersed in TEOS. (author)

  12. 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)

  13. 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)

  14. Advanced Stirling Radioisotope Generator Life Certification Plan

    Science.gov (United States)

    Rusick, Jeffrey J.; Zampino, Edward J.

    2013-01-01

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

  15. Radioisotope Thermoelectric Generator Transport Trailer System

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  16. 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

  17. Thermal Model Predictions of Advanced Stirling Radioisotope Generator Performance

    Science.gov (United States)

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

    2014-01-01

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

  18. Parametric System Model for a Stirling Radioisotope Generator

    Science.gov (United States)

    Schmitz, Paul C.

    2015-01-01

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

  19. Characterization of the Advanced Stirling Radioisotope Generator EU2

    Science.gov (United States)

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

    2015-01-01

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

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

    Science.gov (United States)

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

    2016-01-01

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

  1. 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

  2. Efficient thermo-mechanical generation of electricity from the heat of radioisotopes

    International Nuclear Information System (INIS)

    Cooke-Yarborough, E.H.; Yeats, F.W.

    1975-01-01

    The thermomechanical generator uses a thermomechanical oscillator to convert heat efficiently into a mechanical oscillation which in turn excites a suitable transducer to generate alternating electricity. The thermomechanical oscillator used is based on the Stirling cycle, but avoids the need for rotary motion and for sliding pistons by having a mechanically-resonant, spring-suspended displacer, and by using an oscillating metal diaphragm to provide the mechanical output. The diaphragm drives an alternator consisting of a spring-suspended permanent magnet oscillating between fixed pole pieces which carry the electrical power output windings. Because a thermomechanical generator is much more efficient than a thermo-electric generator at comparable temperatures, it is particularly suitable for use with a radioisotope heat source. The amounts of radioisotope and of shielding required are both greatly reduced. A machine heated by radioisotopes and delivering 10.7W ac at 80Hz began operating in October, 1974. Operating experience with this machine is reported, and these results, together with those obtained with higher-powered machines heated by other means, are used to calculate characteristics and performance of thermo-mechanical radioisotope generators capable of using heat sources such as the waste-management 90 Sr radioisotope sources becoming available from the US nuclear waste management programme. A design to use one of these heat sources in a 52-W underwater generator is described

  3. 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)

  4. 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

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

    International Nuclear Information System (INIS)

    King, D.A.

    1994-01-01

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

  6. Advanced Stirling Radioisotope Generator EU2 Anomaly Investigation

    Science.gov (United States)

    Lewandowski, Edward J.; Dobbs, Michael W.; Oriti, Salvatore M.

    2016-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) Engineering Unit 2 (EU2) is the highest fidelity electrically-heated Stirling radioisotope generator built to date. NASA Glenn Research Center (GRC) completed the assembly of the ASRG EU2 in September, 2014 using hardware from the now cancelled ASRG flight development project. The ASRG EU2 integrated the first pair of Sunpower's ASC-E3 Stirling convertors (ASC-E3 #1 and #2) in an aluminum generator housing with Lockheed Martin's Engineering Development Unit (EDU) 4 controller. After just 179 hours of EU2 generator operation, the first power fluctuation occurred on ASC-E3 #1. The first power fluctuation occurred 175 hours later on ASC-E3 #2. Over time, the power fluctuations became more frequent on both convertors and larger in magnitude. Eventually the EU2 was shut down in January, 2015. An anomaly investigation was chartered to determine root cause of the power fluctuations and other anomalous observations. A team with members from GRC, Sunpower, and Lockheed Martin conducted a thorough investigation of the EU2 anomalies. Findings from the EU2 disassembly identified proximate causes of the anomalous observations. Discussion of the team's assessment of the primary possible failure theories, root cause, and conclusions is provided. Recommendations are made for future Stirling generator development to address the findings from the anomaly investigation. Additional findings from the investigation are also discussed.

  7. Advanced Stirling Radioisotope Generator Engineering Unit 2 Anomaly Investigation

    Science.gov (United States)

    Lewandowski, Edward J.; Dobbs, Michael W.; Oriti, Salvatore M.

    2018-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) Engineering Unit 2 (EU2) is the highest fidelity electrically heated Stirling radioisotope generator built to date. NASA Glenn Research Center completed the assembly of the ASRG EU2 in September 2014 using hardware from the now cancelled ASRG flight development project. The ASRG EU2 integrated the first pair of Sunpower's Advanced Stirling Convertors (ASC-E3 #1 and #2) in an aluminum generator housing with Lockheed Martin's (LM's) Engineering Development Unit (EDU) 4 controller. After just 179 hr of EU2 generator operation, the first power fluctuation occurred on ASC-E3 #1. The first power fluctuation occurred 175 hr later on ASC-E3 #2. Over time, the power fluctuations became more frequent on both convertors and larger in magnitude. Eventually the EU2 was shut down in January 2015. An anomaly investigation was chartered to determine root cause of the power fluctuations and other anomalous observations. A team with members from Glenn, Sunpower, and LM conducted a thorough investigation of the EU2 anomalies. Findings from the EU2 disassembly identified proximate causes of the anomalous observations. Discussion of the team's assessment of the primary possible failure theories, root cause, and conclusions is provided. Recommendations are made for future Stirling generator development to address the findings from the anomaly investigation. Additional findings from the investigation are also discussed.

  8. An overview of the Radioisotope Thermoelectric Generator Transportation System Program

    International Nuclear Information System (INIS)

    McCoy, J.C.; Becker, D.L.

    1996-01-01

    Radioisotope Thermoelectric Generators (RTG) convert the heat generated by radioactive decay to electricity using thermocouples. RTGs have a long operating life, are reasonably lightweight, and require little or no maintenance once assembled and tested. These factors make RTGs particularly attractive for use in spacecraft. However, because RTGs contain significant quantities of radioactive materials, normally plutonium-238 and its decay products, they must be transported in packages built in accordance with Title 10, Code of Federal Regulations, Part 71. The U.S. Department of Energy assigned the Radioisotope Thermoelectric Generator Transportation System (RTGTS) Program to Westinghouse Hanford Company in 1988 to develop a system meeting the regulatory requirements. The program objective was to develop a transportation system that would fully comply with 10 CFR 71 while protecting RTGs from adverse environmental conditions during normal conditions of transport (e.g., shock and heat). The RTGTS is scheduled for completion in December 1996 and will be available to support the National Aeronautics and Space Administration close-quote s Cassini mission to Saturn in October 1997. This paper provides an overview of the RTGTS and discusses the hardware being produced. Additionally, various program management innovations mandated by recent major changes in the U.S. Department of Energy structure and resources will be outlined. copyright 1996 American Institute of Physics

  9. An overview of the Radioisotope Thermoelectric Generator Transporation System Program

    International Nuclear Information System (INIS)

    McCoy, J.C.

    1995-10-01

    Radioisotope Thermoelectric Generators (RTG) convert the heat generated by radioactive decay to electricity using thermocouples. RTGs have a long operating life, are reasonably lightweight, and require little or no maintenance once assembled and tested. These factors make RTGs particularly attractive for use in spacecraft However, because RTGs contain significant quantities of radioactive materials, normally plutonium-238 and its decay products, they must be transported in packages built in accordance with Title 10, Code of Federal Regulations, Part 71. The US Department of Energy assigned the Radioisotope Thermoelectric Generator Transportation System (RTGTS) Program to Westinghouse Hanford Company in 1988 to develop a system meeting the regulatory requirements. The program objective was to develop a transportation system that would fully comply with 10 CFR 71 while protecting RTGs from adverse environmental conditions during normal conditions of transport (e.g., shock and heat). The RTGTS is scheduled for completion in December 1996 and will be available to support the National Aeronautics and Space Administrations Cassini mission to Saturn in October 1997. This paper provides an overview of the RTGTS and discusses the hardware being produced. Additionally, various program management innovations mandated by recent ma or changes in the US Department of Energy structure and resources will be outlined

  10. Using SpaceClaimTD Direct for Modeling Components with Complex Geometries for the Thermal Desktop-Based Advanced Stirling Radioisotope Generator Model

    Science.gov (United States)

    Fabanich, William A., Jr.

    2014-01-01

    SpaceClaim/TD Direct has been used extensively in the development of the Advanced Stirling Radioisotope Generator (ASRG) thermal model. This paper outlines the workflow for that aspect of the task and includes proposed best practices and lessons learned. The ASRG thermal model was developed to predict component temperatures and power output and to provide insight into the prime contractor's thermal modeling efforts. The insulation blocks, heat collectors, and cold side adapter flanges (CSAFs) were modeled with this approach. The model was constructed using mostly TD finite difference (FD) surfaces/solids. However, some complex geometry could not be reproduced with TD primitives while maintaining the desired degree of geometric fidelity. Using SpaceClaim permitted the import of original CAD files and enabled the defeaturing/repair of those geometries. TD Direct (a SpaceClaim add-on from CRTech) adds features that allowed the "mark-up" of that geometry. These so-called "mark-ups" control how finite element (FE) meshes are to be generated through the "tagging" of features (e.g. edges, solids, surfaces). These tags represent parameters that include: submodels, material properties, material orienters, optical properties, and radiation analysis groups. TD aliases were used for most tags to allow analysis to be performed with a variety of parameter values. "Domain-tags" were also attached to individual and groups of surfaces and solids to allow them to be used later within TD to populate objects like, for example, heaters and contactors. These tools allow the user to make changes to the geometry in SpaceClaim and then easily synchronize the mesh in TD without having to redefine the objects each time as one would if using TDMesher. The use of SpaceClaim/TD Direct helps simplify the process for importing existing geometries and in the creation of high fidelity FE meshes to represent complex parts. It also saves time and effort in the subsequent analysis.

  11. Using SpaceClaim/TD Direct for Modeling Components with Complex Geometries for the Thermal Desktop-Based Advanced Stirling Radioisotope Generator Model

    Science.gov (United States)

    Fabanich, William

    2014-01-01

    SpaceClaim/TD Direct has been used extensively in the development of the Advanced Stirling Radioisotope Generator (ASRG) thermal model. This paper outlines the workflow for that aspect of the task and includes proposed best practices and lessons learned. The ASRG thermal model was developed to predict component temperatures and power output and to provide insight into the prime contractors thermal modeling efforts. The insulation blocks, heat collectors, and cold side adapter flanges (CSAFs) were modeled with this approach. The model was constructed using mostly TD finite difference (FD) surfaces solids. However, some complex geometry could not be reproduced with TD primitives while maintaining the desired degree of geometric fidelity. Using SpaceClaim permitted the import of original CAD files and enabled the defeaturing repair of those geometries. TD Direct (a SpaceClaim add-on from CRTech) adds features that allowed the mark-up of that geometry. These so-called mark-ups control how finite element (FE) meshes were generated and allowed the tagging of features (e.g. edges, solids, surfaces). These tags represent parameters that include: submodels, material properties, material orienters, optical properties, and radiation analysis groups. TD aliases were used for most tags to allow analysis to be performed with a variety of parameter values. Domain-tags were also attached to individual and groups of surfaces and solids to allow them to be used later within TD to populate objects like, for example, heaters and contactors. These tools allow the user to make changes to the geometry in SpaceClaim and then easily synchronize the mesh in TD without having to redefine these objects each time as one would if using TD Mesher.The use of SpaceClaim/TD Direct has helped simplify the process for importing existing geometries and in the creation of high fidelity FE meshes to represent complex parts. It has also saved time and effort in the subsequent analysis.

  12. Radioisotope thermoelectric generator/thin fragment impact test

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  13. End-on radioisotope thermoelectric generator impact tests

    International Nuclear Information System (INIS)

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

    1997-01-01

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

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

    Data.gov (United States)

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

  15. Test Program for Stirling Radioisotope Generator Hardware at NASA Glenn Research Center

    Science.gov (United States)

    Lewandowski, Edward J.; Bolotin, Gary S.; Oriti, Salvatore M.

    2015-01-01

    Stirling-based energy conversion technology has demonstrated the potential of high efficiency and low mass power systems for future space missions. This capability is beneficial, if not essential, to making certain deep space missions possible. Significant progress was made developing the Advanced Stirling Radioisotope Generator (ASRG), a 140-W radioisotope power system. A variety of flight-like hardware, including Stirling convertors, controllers, and housings, was designed and built under the ASRG flight development project. To support future Stirling-based power system development NASA has proposals that, if funded, will allow this hardware to go on test at the NASA Glenn Research Center. While future flight hardware may not be identical to the hardware developed under the ASRG flight development project, many components will likely be similar, and system architectures may have heritage to ASRG. Thus, the importance of testing the ASRG hardware to the development of future Stirling-based power systems cannot be understated. This proposed testing will include performance testing, extended operation to establish an extensive reliability database, and characterization testing to quantify subsystem and system performance and better understand system interfaces. This paper details this proposed test program for Stirling radioisotope generator hardware at NASA Glenn. It explains the rationale behind the proposed tests and how these tests will meet the stated objectives.

  16. Analytical thermal model validation for Cassini radioisotope thermoelectric generator

    International Nuclear Information System (INIS)

    Lin, E.I.

    1997-01-01

    The Saturn-bound Cassini spacecraft is designed to rely, without precedent, on the waste heat from its three radioisotope thermoelectric generators (RTGs) to warm the propulsion module subsystem, and the RTG end dome temperature is a key determining factor of the amount of waste heat delivered. A previously validated SINDA thermal model of the RTG was the sole guide to understanding its complex thermal behavior, but displayed large discrepancies against some initial thermal development test data. A careful revalidation effort led to significant modifications and adjustments of the model, which result in a doubling of the radiative heat transfer from the heat source support assemblies to the end domes and bring up the end dome and flange temperature predictions to within 2 C of the pertinent test data. The increased inboard end dome temperature has a considerable impact on thermal control of the spacecraft central body. The validation process offers an example of physically-driven analytical model calibration with test data from not only an electrical simulator but also a nuclear-fueled flight unit, and has established the end dome temperatures of a flight RTG where no in-flight or ground-test data existed before

  17. Radioisotope instruments

    CERN Document Server

    Cameron, J F; Silverleaf, D J

    1971-01-01

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

  18. Thermal Model Predictions of Advanced Stirling Radioisotope Generator Performance

    Science.gov (United States)

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

    2014-01-01

    This paper presents recent thermal model results of the Advanced Stirling Radioisotope Generator (ASRG). The three-dimensional (3D) ASRG thermal power model was built using the Thermal Desktop(trademark) thermal analyzer. The model was correlated with ASRG engineering unit test data and ASRG flight unit predictions from Lockheed Martin's (LM's) I-deas(trademark) TMG thermal model. The auxiliary cooling system (ACS) of the ASRG is also included in the ASRG thermal model. The ACS is designed to remove waste heat from the ASRG so that it can be used to heat spacecraft components. The performance of the ACS is reported under nominal conditions and during a Venus flyby scenario. The results for the nominal case are validated with data from Lockheed Martin. Transient thermal analysis results of ASRG for a Venus flyby with a representative trajectory are also presented. In addition, model results of an ASRG mounted on a Cassini-like spacecraft with a sunshade are presented to show a way to mitigate the high temperatures of a Venus flyby. It was predicted that the sunshade can lower the temperature of the ASRG alternator by 20 C for the representative Venus flyby trajectory. The 3D model also was modified to predict generator performance after a single Advanced Stirling Convertor failure. The geometry of the Microtherm HT insulation block on the outboard side was modified to match deformation and shrinkage observed during testing of a prototypic ASRG test fixture by LM. Test conditions and test data were used to correlate the model by adjusting the thermal conductivity of the deformed insulation to match the post-heat-dump steady state temperatures. Results for these conditions showed that the performance of the still-functioning inboard ACS was unaffected.

  19. Radioisotope power system based on derivative of existing Stirling engine

    International Nuclear Information System (INIS)

    Schock, A.; Or, C.T.; Kumar, V.

    1995-01-01

    In a recent paper, the authors presented the results of a system design study of a 75-watt(c) RSG (Radioisotope Stirling Generator) for possible application to the Pluto Fast Flyby mission. That study was based on a Stirling engine design generated by MTI (Mechanical Technology, Inc.). The MTI design was a derivative of a much larger (13 kwe) engine that they had developed and tested for NASA's LERC. Clearly, such a derivative would be a major extrapolation (downsizing) from what has actually been built and tested. To avoid that, the present paper describes a design for a 75-watt RSG system based on derivatives of a small (11-watt) engine and linear alternator system that has been under development by STC (Stirling Technology Company) for over three years and that has operated successfully for over 15,000 hours as of March 1995. Thus, the STC engines would require much less extrapolation from proven designs. The design employs a heat source consisting of two standard General Purpose Heat Source (GPHS) modules, coupled to four Stirling engines with linear alternators, any three of which could deliver the desired 75-watt(e) output if the fourth should fail. The four engines are coupled to four common radiators with redundant heatpipes for rejecting the engines' waste heat to space. The above engine and radiator redundancies promote system reliability. The paper describes detailed analyses to determine the effect of radiator geometry on system mass and performance, before and after an engine or heatpipe failure

  20. Development of a Power Electronics Controller for the Advanced Stirling Radioisotope Generator

    Science.gov (United States)

    Leland, Douglas K.; Priest, Joel F.; Keiter, Douglas E.; Schreiber, Jeffrey G.

    2008-01-01

    Under a U.S. Department of Energy program for radioisotope power systems, Lockheed Martin is developing an Engineering Unit of the Advanced Stirling Radioisotope Generator (ASRG). This is an advanced version of the previously reported SRG110 generator. The ASRG uses Advanced Stirling Convertors (ASCs) developed by Sunpower Incorporated under a NASA Research Announcement contract. The ASRG makes use of a Stirling controller based on power electronics that eliminates the tuning capacitors. The power electronics controller synchronizes dual-opposed convertors and maintains a fixed frequency operating point. The controller is single-fault tolerant and uses high-frequency pulse width modulation to create the sinusoidal currents that are nearly in phase with the piston velocity, eliminating the need for large series tuning capacitors. Sunpower supports this effort through an extension of their controller development intended for other applications. Glenn Research Center (GRC) supports this effort through system dynamic modeling, analysis and test support. The ASRG design arrived at a new baseline based on a system-level trade study and extensive feedback from mission planners on the necessity of single-fault tolerance. This paper presents the baseline design with an emphasis on the power electronics controller detailed design concept that will meet space mission requirements including single fault tolerance.

  1. Radioisotope space power generator. Annual report, October 1978-September 1979

    International Nuclear Information System (INIS)

    Elsner, N.B.; Chin, J.; Staley, H.G.; Bass, J.C.; Morris, C.C.; Shearer, C.H.; Steeger, E.J.

    1982-03-01

    The emphasis of the Isotec Technology Program shifted from development of a Galileo generator to study of a segmented selenide element and couple technology. The goal of the FY 79 program was to determine the feasibility of fabricating segmented selenide P and N elements which exploit the high thermoelectric efficiency of (Cu,Ag) 2 Se and Gd 2 Se 3 materials. A preliminary evaluation of segmented element efficiencies, material compatibilities, and fabrication abilities was used to select (Cu,Ag) 2 Se/Fe(Bi,Sb) 2 Te 3 for the P element and Gd 2 Se 3 /PbTe for the N element. The iron barrier between the (Cu,Ag) 2 Se and (Bi,Sb) 2 Te 3 prevented degradation of thermoelectric properties from copper contamination of the (Bi,Sb) 2 Te 3 . Fabrication processes for both elements were developed. Gd 2 Se 3 was friable and difficult to fabricate crack-free. It also exhibited a phase transition from cubic to orthorhombic, which increased its susceptibility to microcracking and reduced its thermoelectric efficiency. Life testing of an all-bonded couple with unsegmented (Cu,Ag) 2 Se P-type and Gd 2 Se 3 N-type elements was stopped after 3300 h in a nominal 830 0 C/390 0 C thermal gradient. The Gd 2 Se 3 leg did not show any significant degradation during the test. Examination of the hot end of the P element showed the need for a less reactive hot cap material and an improved vapor supression system. Module testing of a 1-W (Bi,Sb) 2 (Se,Te) 3 generator was performed for 5000 h with no degradation in power. High-temperature Thermid 600 adhesive curing cycles were examined, 75-mW module loading tests were performed, and diagnostic examination of RTG-2A and RTG-201 was completed

  2. Advanced Stirling Radioisotope Generator (ASRG) Thermal Power Model in MATLAB

    Science.gov (United States)

    Wang, Xiao-Yen, J.

    2012-01-01

    This paper presents a one-dimensional steady-state mathematical thermal power model of the ASRG. It aims to provide a guideline of understanding how the ASRG works and what can change its performance. The thermal dynamics and energy balance of the generator is explained using the thermal circuit of the ASRG. The Stirling convertor performance map is used to represent the convertor. How the convertor performance map is coupled in the thermal circuit is explained. The ASRG performance characteristics under i) different sink temperatures and ii) over the years of mission (YOM) are predicted using the one-dimensional model. Two Stirling converter control strategies, i) fixing the hot-end of temperature of the convertor by adjusting piston amplitude and ii) fixing the piston amplitude, were tested in the model. Numerical results show that the first control strategy can result in a higher system efficiency than the second control strategy when the ambient gets warmer or the general-purpose heat source (GPHS) fuel load decays over the YOM. The ASRG performance data presented in this paper doesn't pertain to the ASRG flight unit. Some data of the ASRG engineering unit (EU) and flight unit that are available in public domain are used in this paper for the purpose of numerical studies.

  3. 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

  4. Radioisotopes Thermal Generators and its applications; Generadores térmicos de radioisótopos y sus aplicaciones

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C.

    2016-07-01

    An historical review of the technologies for electricity generation using the decay heat of the radioisotopes is done. The technologies to convert the heat into electricity in the RTG (Radioisotopes Thermal Generators) Systems are described. The past, todays and future applications of RTG are described, to provide electricity to equipment in spatial satellites and spacecraft, lighthouse tower and sea bouys, submarine rovers, etc. At the end the safety characteristics and international regulations for RTG are mentioned.

  5. Status report on performance of radioisotope thermoelectric generators using silicon germanium thermoelectric elements

    International Nuclear Information System (INIS)

    Bennett, G.L.; Campbell, R.W.; Putnam, L.R.; Hemler, R.J.

    1994-01-01

    Three general-purpose heat source radioisotope thermoelectric generators (GPHS-RTGs) are currently in use in space: two on board the Galileo spacecraft on its way to Jupiter and one on the Ulysses spacecraft exploring the polar regions of the Sun. The GPHS-RTG was designed to provide at least 285 W(e) at the beginning of mission (BOM) within a mass constraint of 56 kg and an overall size envelope of 42.2 cm in diameter and 114 cm in length. The Galileo spacecraft, which as already sent back exciting scientific information on Venus, Earth, and the asteroids Gaspra and Ida, carries two GPHS-RTGs which operate at 30 V. The Ulysses spacecraft, which has already successfully swung past Jupiter on its way to the southern polar regions of the Sun, carries one GPHS-RTG which operates at 28 V. The analyses presented in the paper show that both Galileo and Ulysses will have sufficient power for the baseline missions and analyses are under way to determine the power available for an extended Ulysses mission out to the year 2002. Ten other silicon-germanium-based RTGs on the LES 8/9 and Voyager 1/2 spacecraft have completed their prime missions and are now successfully performing extended missions

  6. Radioisotope Power System Delivery, Ground Support and Nuclear Safety Implementation: Use of the Multi-Mission Radioisotope Thermoelectric Generator for the NASA's Mars Science Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    S.G. Johnson; K.L. Lively; C.C. Dwight

    2014-07-01

    Radioisotope power systems have been used for over 50 years to enable missions in remote or hostile environments. They are a convenient means of supplying a few milliwatts up to a few hundred watts of useable, long-term electrical power. With regard to use of a radioisotope power system, the transportation, ground support and implementation of nuclear safety protocols in the field is a complex process that requires clear identification of needed technical and regulatory requirements. The appropriate care must be taken to provide high quality treatment of the item to be moved so it arrives in a condition to fulfill its missions in space. Similarly it must be transported and managed in a manner compliant with requirements for shipment and handling of special nuclear material. This presentation describes transportation, ground support operations and implementation of nuclear safety and security protocols for a radioisotope power system using recent experience involving the Multi-Mission Radioisotope Thermoelectric Generator for National Aeronautics and Space Administration’s Mars Science Laboratory, which launched in November of 2011.

  7. 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.

  8. 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

  9. Organization of a radioisotope based molecular biology laboratory

    International Nuclear Information System (INIS)

    2006-12-01

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

  10. Work plan for the fabrication of the radioisotope thermoelectric generator transportation system package mounting

    International Nuclear Information System (INIS)

    Satoh, J.A.

    1994-01-01

    The Radioisotope Thermoelectric Generator (RTG) has available a dedicated system for the transportation of RTG payloads. The RTG Transportation System (System 100) is comprised of four systems; the Package (System 120), the Semi-trailer (System 140), the Gas Management (System 160), and the Facility Transport (System 180). This document provides guidelines on the fabrication, technical requirements, and quality assurance of the Package Mounting (Subsystem 145), part of System 140. The description follows the Development Control Requirements of WHC-CM-6-1, EP 2.4, Rev. 3

  11. Development of disposal technologies for radioactive waste generated from radioisotope users and research institutes

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro

    2001-01-01

    In order to safely dispose of a radioactive waste, which is generated from radioisotope users and research institutes, investigation of characteristics of the waste and conceptual design of disposal facility were carried out. As a result of investigating JAERI that the waste has mainly been stored, it became clear that radioactivities of 19 nuclides are important from the viewpoint of the safety of the disposal. And the result of the conceptual design of disposal facilities on the assumption of 3 kinds of sites, the differences on the safety could not be recognized in either case, though the installation depth to construct the facilities influenced the economical efficiency. (author)

  12. Testing of the Advanced Stirling Radioisotope Generator Engineering Unit at NASA Glenn Research Center

    Science.gov (United States)

    Lewandowski, Edward J.

    2013-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) is a high-efficiency generator being developed for potential use on a Discovery 12 space mission. Lockheed Martin designed and fabricated the ASRG Engineering Unit (EU) under contract to the Department of Energy. This unit was delivered to NASA Glenn Research Center in 2008 and has been undergoing extended operation testing to generate long-term performance data for an integrated system. It has also been used for tests to characterize generator operation while varying control parameters and system inputs, both when controlled with an alternating current (AC) bus and with a digital controller. The ASRG EU currently has over 27,000 hours of operation. This paper summarizes all of the tests that have been conducted on the ASRG EU over the past 3 years and provides an overview of the test results and what was learned.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-01-22

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

  14. Design of a Facility to Test the Advanced Stirling Radioisotope Generator Engineering Unit

    Science.gov (United States)

    Lewandowski, Edward J.; Schreiber, Jeffrey G.; Oriti, Salvatore M.; Meer, David W.; Brace, Michael H.; Dugala, Gina

    2009-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) is being considered to power deep space missions. An engineering unit, the ASRG-EU, was designed and fabricated by Lockheed Martin under contract to the Department of Energy. This unit is currently on an extended operation test at NASA Glenn Research Center to generate performance data and validate the life and reliability predictions for the generator and the Stirling convertors. A special test facility was designed and built for testing the ASRG-EU. Details of the test facility design are discussed. The facility can operate the convertors under AC bus control or with the ASRG-EU controller. It can regulate input thermal power in either a fixed temperature or fixed power mode. An enclosure circulates cooled air around the ASRG-EU to remove heat rejected from the ASRG-EU by convection. A custom monitoring and data acquisition system supports the test. Various safety features, which allow 2417 unattended operation, are discussed.

  15. Management of radioisotope, radiation generator and fuel materials for independent administrative corporations of national university

    International Nuclear Information System (INIS)

    2003-03-01

    This report states the situation, problems and proposal of management of radioisotope, radiation generator and fuel materials by independent administrative corporations of national universities. Four proposals are stated as followings; 1) in order to improve management of radioisotope, radiation generator, fuel materials and X-ray in the universities, organization and definition of the control department in each university and accident measures have to be decided. The middle object and plan should be needed. An appropriate management for proceeding researches should be discussed by closer connection of universities in the country. 2) The budget for safety control has to be identified at distribution of budget of each national university corporations. The insurance method is needed to be discussed. 3) The department in the MEXT (Ministry of Education, Culture, Sports, Science and Technology) should be enriched to support researches and safety control of the staff and students. 4) The system, which carries out treatment and disposal of disuse materials and keeps them under the responsibility of the nation, is necessary. (S.Y.)

  16. Pseudo-random generator to allow to an electronic pulse simulator the ability to emulate radioisotopes spectra

    International Nuclear Information System (INIS)

    Lucianna F A; Carrillo M A; Mangussi M J

    2012-01-01

    The present work describes the development of a pseudo-random system to provide to a simulator pulse of radiation detectors the ability to emit pulses patterns similar to those recorded when measuring actual radioisotope. The idea is that the system can emulate characteristic spectral distributions of known radioisotopes, as well as creating individual spectra for specific purposes. This design is based on an improvement in terms of software from earlier development that only supplied predefined amplitude pulses at constant intervals (author)

  17. The General-Purpose Heat Source Radioisotope Thermoelectric Generator: Power for the Galileo and Ulysses missions

    International Nuclear Information System (INIS)

    Bennett, G.L.; Lombardo, J.J.; Hemler, R.J.; Peterson, J.R.

    1986-01-01

    Electrical power for NASA's Galileo mission to Jupiter and ESA's Ulysses mission to explore the polar regions of the Sun will be provided by General-Purpose Heat Source Radioisotope Thermo-electric Generators (GPHS-RTGs). Building upon the successful RTG technology used in the Voyager program, each GPHS-RTG will provide at least 285 W(e) at beginning-of-mission. The design concept has been proven through extensive tests of an electrically heated Engineering Unit and a nuclear-heated Qualification Unit. Four flight generators have been successfully assembled and tested for use on the Galileo and Ulysses spacecraft. All indications are that the GPHS-RTGs will meet or exceed the power requirement of the missions

  18. Automatic deodorizing system for waste water from radioisotope facilities using an ozone generator

    International Nuclear Information System (INIS)

    Kawamura, Hiroko; Hirata, Yasuki

    2002-01-01

    We applied an ozone generator to sterilize and to deodorize the waste water from radioisotope facilities. A small tank connected to the generator is placed outside of the drainage facility founded previously, not to oxidize the other apparatus. The waste water is drained 1 m 3 at a time from the tank of drainage facility, treated with ozone and discharged to sewer. All steps proceed automatically once the draining work is started remotely in the office. The waste water was examined after the ozone treatment for 0 (original), 0.5, 1.0, 1.5 and 2.0 h. Regarding original waste water, the sum of coliform groups varied with every examination repeated - probably depend on the colibacilli used in experiments; hydrogen sulfide, biochemical oxygen demand and the offensive odor increased with increasing coliform groups. The ozone treatment remarkably decreased hydrogen sulfide and the offensive odor, decreased coliform groups when the original water had rich coliforms. (author)

  19. Automatic deodorizing system for waste water from radioisotope facilities using an ozone generator

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, Hiroko; Hirata, Yasuki [Kyushu Univ., Fukuoka (Japan). Radioisotope Center; Taguchi, Kenji [Riken Co. Ltd., Kitakyushu, Fukuoka (Japan)

    2002-03-01

    We applied an ozone generator to sterilize and to deodorize the waste water from radioisotope facilities. A small tank connected to the generator is placed outside of the drainage facility founded previously, not to oxidize the other apparatus. The waste water is drained 1 m{sup 3} at a time from the tank of drainage facility, treated with ozone and discharged to sewer. All steps proceed automatically once the draining work is started remotely in the office. The waste water was examined after the ozone treatment for 0 (original), 0.5, 1.0, 1.5 and 2.0 h. Regarding original waste water, the sum of coliform groups varied with every examination repeated - probably depend on the colibacilli used in experiments; hydrogen sulfide, biochemical oxygen demand and the offensive odor increased with increasing coliform groups. The ozone treatment remarkably decreased hydrogen sulfide and the offensive odor, decreased coliform groups when the original water had rich coliforms. (author)

  20. Radioisotope thermoelectric generator load and unload sequence from the licensed hardware package system and the trailer system

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1995-01-01

    The Radioisotope Thermoelectric Generator Transportation System, designated as System 100, comprises four major systems. The four major systems are designated as the Packaging System (System 120), Trailer System (System 140), Operations and Ancillary Equipment System (System 160), including the Radioisotope Thermoelectric Generator Transportation System packaging is licensed (regularoty) hardware, certified by the U.S. Department of Energy to be in accordance with Title 10, Code of Federal Regulations, Part 71 (10 CFR 71). System 140, System 160, and System 180 are nonlicensed (nonregulatory) hardware. This paper focuses on the required interfaces and sequencing of events required by these systems and the shipping and receiving facilities in preparation of the Radioisotope Thermoelectric Generator for space flight. copyright 1995 American Institute of Physics

  1. System-Level Testing of the Advanced Stirling Radioisotope Generator Engineering Hardware

    Science.gov (United States)

    Chan, Jack; Wiser, Jack; Brown, Greg; Florin, Dominic; Oriti, Salvatore M.

    2014-01-01

    To support future NASA deep space missions, a radioisotope power system utilizing Stirling power conversion technology was under development. This development effort was performed under the joint sponsorship of the Department of Energy and NASA, until its termination at the end of 2013 due to budget constraints. The higher conversion efficiency of the Stirling cycle compared with that of the Radioisotope Thermoelectric Generators (RTGs) used in previous missions (Viking, Pioneer, Voyager, Galileo, Ulysses, Cassini, Pluto New Horizons and Mars Science Laboratory) offers the advantage of a four-fold reduction in Pu-238 fuel, thereby extending its limited domestic supply. As part of closeout activities, system-level testing of flight-like Advanced Stirling Convertors (ASCs) with a flight-like ASC Controller Unit (ACU) was performed in February 2014. This hardware is the most representative of the flight design tested to date. The test fully demonstrates the following ACU and system functionality: system startup; ASC control and operation at nominal and worst-case operating conditions; power rectification; DC output power management throughout nominal and out-of-range host voltage levels; ACU fault management, and system command / telemetry via MIL-STD 1553 bus. This testing shows the viability of such a system for future deep space missions and bolsters confidence in the maturity of the flight design.

  2. A compendium of the radioisotope thermoelectric generator transportation system and recent programmatic changes

    International Nuclear Information System (INIS)

    Becker, D.L.; McCoy, J.C.

    1996-03-01

    Because RTGs contain significant quantities of radioactive materials, usually plutonium-238 and its decay products, they must be transported in packages built in accordance with 10 CFR 71 (1994). To meet these regulatory requirements, US DOE commissioned Westinghouse Hanford Co. in 1988 to develop a Radioisotope Thermoelectric Generator Transportation System (RTGTS) that would fully comply while protecting RTGs from adverse environmental conditions during normal transport conditions (eg, mainly shock and heat). RTGTS is scheduled for completion Dec. 1996 and will be available to support NASA's Cassini mission to Saturn in Oct. 1997. This paper provides an overview of the RTGTS project, discusses the hardware being produced, and summarizes various programmatic and management innovations required by recent changes at DOE

  3. Theoretical analysis of heat transfer in, and electrical performance of, a milliwatt radioisotopic powered thermoelectric generator

    International Nuclear Information System (INIS)

    Biver, C.J.

    1975-01-01

    A simplified, theoretical model has been made for a radioisotope-powered milliwatt thermoelectric generator (RTG). Calculations of unit heat transfer and electrical performance characteristics are made in two ways: (a) using discrete values of input physical parameters for an individual unit; and (b) using a statistical simulation (Monte Carlo) approach for estimating the variation in performance in a group of N-units. The statistical simulation approach is useful in: (a) estimating the allowable range of input parameters conducive to the production design meeting specifications in a group of N-units; and (b) determining particular parameters that must be significantly restricted in variation to achieve desired performance. The available experimental data, as compared with the discrete value calculations, are in quite good agreement (within 5 percent generally). (U.S.)

  4. Radiation field calculation in the vicinity of Russian radioisotope generator sources

    Energy Technology Data Exchange (ETDEWEB)

    Pretzsch, Gunter; Hummelsheim, Klemens; Bogorinski, Peter [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Kurfuerstendamm 200, 10719 Berlin (Germany)

    2005-07-01

    Germany supports the Russian Federation in the framework of the G8 Global Partnership programme to secure nuclear and radioactive materials against misuse and proliferation. In this context, GRS, on behalf of the German Foreign Office, is coordinating activities to remove disused radioisotope thermoelectric generators (RITEG) from the Baltic Sea which serve as power supply for marine lighthouses and their replacement by alternative energy sources. Further the planned project includes transportation to an interim storage, the storage equipped with radiation monitoring and physical protection measures, later transportation for reprocessing to the Mayak Production Association, where the RITEG will be dismantled in a hot cell and encapsulated radioactive source will be vitrified and stored as radioactive waste. For the whole project safety analyses are to be performed e.g. to meet radiation protection requirements. In the present paper modelling and calculation of radiation fields in the vicinity of RITEG as a basis for safety analyses is reported. (authors)

  5. External Magnetic Field Reduction Techniques for the Advanced Stirling Radioisotope Generator

    Science.gov (United States)

    Niedra, Janis M.; Geng, Steven M.

    2013-01-01

    Linear alternators coupled to high efficiency Stirling engines are strong candidates for thermal-to-electric power conversion in space. However, the magnetic field emissions, both AC and DC, of these permanent magnet excited alternators can interfere with sensitive instrumentation onboard a spacecraft. Effective methods to mitigate the AC and DC electromagnetic interference (EMI) from solenoidal type linear alternators (like that used in the Advanced Stirling Convertor) have been developed for potential use in the Advanced Stirling Radioisotope Generator. The methods developed avoid the complexity and extra mass inherent in data extraction from multiple sensors or the use of shielding. This paper discusses these methods, and also provides experimental data obtained during breadboard testing of both AC and DC external magnetic field devices.

  6. Power performance of the general-purpose heat source radioisotope thermoelectric generator

    International Nuclear Information System (INIS)

    Bennett, G.L.; Lombardo, J.J.; Rock, B.J.

    1986-01-01

    The General-Purpose Heat Source Radioisotope Thermoelectric Generator (GRHS-RTG) has been developed under the sponsorship of the Department of Energy (DOE) to provide electrical power for the National Aeronautics and Space Administration (NASA) Galileo mission to Jupiter and the joint NASA/European Space Agency (ESA) Ulysses mission to study the polar regions of the sun. A total of five nuclear-heated generators and one electrically heated generator have been built and tested, proving out the design concept and meeting the specification requirements. The GPHS-RTG design is built upon the successful-technology used in the RTGs flown on the two NASA Voyager spacecraft and two US Air Force communications satellites. THe GPHS-RTG converts about 4400 W(t) from the nuclear heat source into at least 285 W(e) at beginning of mission (BOM). The GPHS-RTG consists of two major components: the General-Purpose Heat Source (GPHS) and the Converter. A conceptual drawing of the GPHs-RTG is presented and its design and performance are described

  7. Advanced Stirling Radioisotope Generator Engineering Unit 2 (ASRG EU2) Final Assembly

    Science.gov (United States)

    Oriti, Salvatore M.

    2015-01-01

    NASA Glenn Research Center (GRC) has recently completed the assembly of a unique Stirling generator test article for laboratory experimentation. Under the Advanced Stirling Radioisotope Generator (ASRG) flight development contract, NASA GRC initiated a task to design and fabricate a flight-like generator for in-house testing. This test article was given the name ASRG Engineering Unit 2 (EU2) as it was effectively the second engineering unit to be built within the ASRG project. The intent of the test article was to duplicate Lockheed Martin's qualification unit ASRG design as much as possible to enable system-level tests not previously possible at GRC. After the cancellation of the ASRG flight development project, the decision was made to continue the EU2 build, and make use of a portion of the hardware from the flight development project. GRC and Lockheed Martin engineers collaborated to develop assembly procedures, leveraging the valuable knowledge gathered by Lockheed Martin during the ASRG development contract. The ASRG EU2 was then assembled per these procedures at GRC with Lockheed Martin engineers on site. The assembly was completed in August 2014. This paper details the components that were used for the assembly, and the assembly process itself.

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

    International Nuclear Information System (INIS)

    Becker, D.L.

    1997-01-01

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

  9. Guide to the safe design, construction and use of radioisotopic power generators for certain land and sea applications

    International Nuclear Information System (INIS)

    1970-01-01

    The increasing development and production of certain types of radioisotopic power generators has indicated the need for internationally acceptable recommendations to be formulated governing the health and safety aspects of their construction and use. Accordingly, a Joint IAEA/ENEA Working Group was set up in 1966 with the task of studying the health and safety problems associated with such devices. The Working Group met twice, in April and December 1967, and prepared a draft guide to the safe design, construction and use of radioisotopic power generators. This draft guide was circulated in September 1968 to IAEA and ENEA Member States for consideration, and the comments that were subsequently received have formed the basis of a re-examination of the draft text in June 1969 by a joint IAEA/ENEA group of consultants set up by the two Agencies to bring the draft guide to its final form. This guide is intended to facilitate the establishment of an adequate standard of safety in the design, construction, installation and use of radioisotopic power generators, and in their ultimate disposal. The immediate requirement is considered to be in relation to those generators which are in an advanced state of development and production and which are designed for use on land and on o r under the sea. The guide deals mainly with radioisotopic power generators in the power range from about one hundred milliwatts to some hundred watts. However, competent national authorities may adapt these guidelines to generators outside this power range. It has been decided at this stage to exclude consideration of miniature generators for medical use, in watches and in other devices available to the general public. Generators for use in space have also been excluded.

  10. 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.

  11. Radiation Environments and Exposure Considerations for the Multi-Mission Radioisotope Thermoelectric Generator

    International Nuclear Information System (INIS)

    Kelly, William M.; Low, Nora M.; Zillmer, Andrew; Johnson, Gregory A.; Normand, Eugene

    2006-01-01

    The Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) is the next generation (RTG) being developed by DOE to provide reliable, long-life electric power for NASA's planetary exploration programs. The MMRTG is being developed by Pratt and Whitney Rocketdyne and Teledyne Energy Systems Incorporated (TESI) for use on currently planned and projected flyby, orbital and planet landing missions. This is a significant departure from the design philosophy of the past which was to match specific mission requirements to RTG design capabilities. Undefined mission requirements provide a challenge to system designers by forcing them to put a design envelope around 'all possible missions'. These multi-mission requirements include internal and external radiation sources. Internal sources include the particles ejected by decaying Pu-238 and its daughters plus particles resulting from the interaction of these particles with other MMRTG materials. External sources include the full spectrum of charged particle radiation surrounding planets with magnetic fields and the surfaces of extraterrestrial objects not shielded by magnetic fields. The paper presents the results of investigations into the environments outlined above and the impact of radiation exposure on potential materials to be used on MMRTG and ground support personnel. Mission requirements were also reviewed to evaluate total integrated dose and to project potential shielding requirements for materials. Much of the information on mission shielding requirements was provided by NASA's Jet Propulsion Laboratory. The primary result is an ionizing radiation design curve which indicates the limits to which a particular mission can take the MMRTG in terms of ionizing radiation exposure. Estimates of personnel radiation exposure during ground handling are also provided

  12. Disposition of Radioisotope Thermoelectric Generators Currently Located at the Oak Ridge National Laboratory - 12232

    Energy Technology Data Exchange (ETDEWEB)

    Glenn, J. [U.S. Department of Energy, Oak Ridge Operations Office, 200 Administrative Road, Oak Ridge, TN 37830 (United States); Patterson, J.; DeRoos, K. [SEC Federal Services Corporation (SEC), 2800 Solway Road, Knoxville, TN 37931 (United States); Patterson, J.E.; Mitchell, K.G. [Strata-G, LLC, 2027 Castaic Lane, Knoxville, TN 37932 (United States)

    2012-07-01

    Under the American Recovery and Reinvestment Act (ARRA), the U.S. Department of Energy (DOE) awarded SEC Federal Services Corporation (SEC) a 34-building demolition and disposal (D and D) project at the Oak Ridge National Laboratory (ORNL) that included the disposition of six Strontium (Sr-90) powered Radioisotope Thermoelectric Generators (RTGs) stored outside of ORNL Building 3517. Disposition of the RTGs is very complex both in terms of complying with disposal facility waste acceptance criteria (WAC) and U.S. Department of Transportation (DOT) requirements for packaging and transportation in commerce. Two of the RTGs contain elemental mercury which requires them to be Land Disposal Restrictions (LDR) compliant prior to disposal. In addition, all of the RTGs exceed the Class C waste concentration limits under Nuclear Regulatory Commission (NRC) Waste Classification Guidelines. In order to meet the LDR requirements and Nevada National Security Site (NNSS) WAC, a site specific treatability variance for mercury was submitted to the U.S. Environmental Protection Agency (EPA) to allow macro-encapsulation to be an acceptable treatment standard for elemental mercury. By identifying and confirming the design configuration of the mercury containing RTGs, the SEC team proved that the current configuration met the macro-encapsulation standard of 40 Code of Federal Regulations (CFR) 268.45. The SEC Team also worked with NNSS to demonstrate that all radioisotope considerations are compliant with the NNSS low-level waste (LLW) disposal facility performance assessment and WAC. Lastly, the SEC team determined that the GE2000 Type B cask met the necessary size, weight, and thermal loading requirements for five of the six RTGs. The sixth RTG (BUP-500) required a one-time DOT shipment exemption request due to the RTG's large size. The DOT exemption justification for the BUP-500 relies on the inherent robust construction and material make-up of the BUP- 500 RTG. DOE-ORO, SEC

  13. 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

  14. KOVEC studies of radioisotope thermoelectric generator response (In connection with possible NASA space shuttle accident explosion scenarios)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, J.; Weston, A.; Lee, E.

    1984-06-26

    The Department of Energy (DOE) commissioned a study leading to a final report (NUS-4543, Report of the Shuttle Transportation System (STS) Explosion Working Group (EWG), June 8, 1984), concerned with PuO/sub 2/ dispersal should the NASA space shuttle explode during the proposed Galileo and ISPN launches planned for 1986. At DOE's request, LLNL furnished appendices that describe hydrocode KOVEC calculations of potential damage to the Radioisotope Thermoelectric Generators, fueled by PuO/sub 2/, should certain explosion scenarios occur. These appendices are contained in this report.

  15. 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)

  16. Present status of unsealed radioisotope therapy in Japan based on the nation-wide questionnaire

    International Nuclear Information System (INIS)

    Oyamada, Hiyoshimaru

    1999-01-01

    In Japan, clinical application of unsealed radioisotopes is strictly regulated. Especially in the field of therapy, we are allowed to use only Na 131 I at present. Under such circumstances, the present status of therapeutic nuclear medicine in Japan was surveyed by means of a nation-wide questionnaire, conducted in 193 hospitals. Then, 113 hospitals replied to such questionnaire (recovery rate: 58.5%), and it was found that in 77 hospitals, radioisotope therapy is being performed for Graves' disease and/or thyroid cancer. The questionnaire covered the following points: for Graves' disease-the basic strategy of 131 I therapy, its indications, absorbed doses planned to be given, whether the therapy had been conducted on outpatient basis or in-patient basis, method of thyroid weight estimation, interval of administration in case of multiple doses, number of patients treated per year (1996) etc., and for thyroid cancer-strategy for thyroid remnant, the doses to be given, the maximum doses permitted by the authorities in each hospital both per day and per year, handling of highly contaminated urine in each hospital, interval of administration in case of multiple doses, number of patients treated per year (1996) etc. Also questioned were dissatisfaction with the present regulation by the authorities and/or requests for the better daily work, if any. Based on the above questionnaire, the present status of unsealed radioisotope therapy in Japan was investigated. (author)

  17. 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...

  18. Implementation of EPICS based Control System for Radioisotope Beam line

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae-Ha; Ahn, Tae-Sung; Song, Young-Gi; Kwon, Hyeok-Jung; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Gyeongju (Korea, Republic of)

    2015-10-15

    Korea Mult-purpose Accelerator Complex (KOMAC) has been operating 100 MeV proton linear accelerator . For operating 100 MeV linac, various control system has been implemented such as vacuum, power supply, RCCS and etc. KOMAC is operating two beam lines so that clients can use 100 MeV proton beam for their experiment. KOMAC sends beam to beam line and target room using two dipole magnets and several quadrupole magnets. As demand for experiments and Radius Isotope using beam is increased, another beam line is under construction and RI beam line control system is need. To synchronize with KOMAC control system, RI beam line control system is based on Experimental Physics and Industrial control System (EPICS) software. The beam is transported to RI beam line to control magnet power supply and vacuum. Implementation of RI beam line control system is presented and some preliminary results are reported. The base RI beam line control system is implemented. It can control beam direction and vacuum. Comparing archived data and current data, RI beam line and control system will be improved. In the future, scroll pump and gate control system will be implemented using programmable logic controller PLC. RI beam interlock sequence will be added to KOMAC interlock system to protect linac.

  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. 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)

  1. An approach to design a 90Sr radioisotope thermoelectric generator using analytical and Monte Carlo methods with ANSYS, COMSOL, and MCNP.

    Science.gov (United States)

    Khajepour, Abolhasan; Rahmani, Faezeh

    2017-01-01

    In this study, a 90 Sr radioisotope thermoelectric generator (RTG) with power of milliWatt was designed to operate in the determined temperature (300-312K). For this purpose, the combination of analytical and Monte Carlo methods with ANSYS and COMSOL software as well as the MCNP code was used. This designed RTG contains 90 Sr as a radioisotope heat source (RHS) and 127 coupled thermoelectric modules (TEMs) based on bismuth telluride. Kapton (2.45mm in thickness) and Cryotherm sheets (0.78mm in thickness) were selected as the thermal insulators of the RHS, as well as a stainless steel container was used as a generator chamber. The initial design of the RHS geometry was performed according to the amount of radioactive material (strontium titanate) as well as the heat transfer calculations and mechanical strength considerations. According to the Monte Carlo simulation performed by the MCNP code, approximately 0.35 kCi of 90 Sr is sufficient to generate heat power in the RHS. To determine the optimal design of the RTG, the distribution of temperature as well as the dissipated heat and input power to the module were calculated in different parts of the generator using the ANSYS software. Output voltage according to temperature distribution on TEM was calculated using COMSOL. Optimization of the dimension of the RHS and heat insulator was performed to adapt the average temperature of the hot plate of TEM to the determined hot temperature value. This designed RTG generates 8mW in power with an efficiency of 1%. This proposed approach of combination method can be used for the precise design of various types of RTGs. Copyright © 2016 Elsevier Ltd. All rights reserved.

  2. Radioisotope fueled pulsed power generation system for propulsion and electrical power for deep space missions

    Science.gov (United States)

    Howe, Troy

    Space exploration missions to the moon, Mars, and other celestial bodies have allowed for great scientific leaps to enhance our knowledge of the universe; yet the astronomical cost of these missions limits their utility to only a few select agencies. Reducing the cost of exploratory space travel will give rise to a new era of exploration, where private investors, universities, and world governments can send satellites to far off planets and gather important data. By using radioisotope power sources and thermal storage devices, a duty cycle can be introduced to extract large amounts of energy in short amounts of time, allowing for efficient space travel. The same device can also provide electrical power for subsystems such as communications, drills, lasers, or other components that can provide valuable scientific information. This project examines the use of multiple radioisotope sources combined with a thermal capacitor using Phase Change Materials (PCMs) which can collect energy over a period of time. The result of this design culminates in a variety of possible spacecraft with their own varying costs, transit times, and objectives. Among the most promising are missions to Mars which cost less than 17M, missions that can provide power to satellite constellations for decades, or missions that can deliver large, Opportunity-sized (185kg) payloads to mars for less than 53M. All made available to a much wider range of customer with commercially available satellite launches from earth. The true cost of such progress though lies in the sometimes substantial increase in transit times for these missions.

  3. Nano-technology contributions towards the development of high performance radioisotope generators: The future promise to meet the continuing clinical demand.

    Science.gov (United States)

    Sakr, Tamer M; Nawar, Mohamed F; Fasih, T W; El-Bayoumy, S; Abd El-Rehim, H A

    2017-11-01

    Nanostructured materials attracted considerable attention because of its high surface area to volume ratio resulting from their nano-scale dimensions. This class of sorbents is expected to have a potential impact on enhancement the efficacy of radioisotope generators for diagnostic and therapeutic applications in nuclear medicine. This review provides a summary on the importance of nanostructured materials as effective sorbents for the development of clinical-scale radioisotope generators and outlining the assessment of recent developments, key challenges and promising access to the near future. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. General-purpose heat source: Research and development program, radioisotope thermoelectric generator/thin fragment impact test

    International Nuclear Information System (INIS)

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

    1996-11-01

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

  5. 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)

  6. The interchangeability of radioisotope and X-ray based measurements of bone mineral density

    International Nuclear Information System (INIS)

    Adachi, J.D.; Webber, C.E.

    1991-01-01

    Lumbar spine and femoral neck bone mineral density (BMD) were measured with a Novo radioisotope based dual photon densitometer and with a Lunar X-ray densitometer in 94 subjects attending a Metabolic Bone Disease Clinic. There was a strong correlation between results obtained from each machine. The correlation coefficients for the spine and femoral neck were 0.97 and 0.88, respectively. Differences between results from each machine were normally distributed with a mean bias of 37.5% (spine) and 27.8% (femur), arising principally from differences in machine calibration. In each case the BMD was greater measured by X-ray absorptiometry. The range for the bias was approximately 25-50% for the spine and 10-45% for the femoral neck. The results from these two machines are not interchangeable. When subjects participating in long term studies using a radioisotope densitometer are transferred to an X-ray densitometer, an individual conversion factor must be measured at each site for each subject. (author)

  7. Effect of heat treatment on the electrical resistance of photoresist as related to radioisotopic thermoelectric generator aging

    International Nuclear Information System (INIS)

    Johnson, R.T. Jr.

    1979-03-01

    Photoresist is used in electrical contact definition and processing in radioisotopic thermoelectric generators. Inadequate removal of material during processing could lead to electrical shorting when exposed to the high temperature use environment. This effect has been simulated through studies of the electrical resistance of thin layers of photoresist (Kodak Metal Etch Resist) on glass (Corning 7052) with tungsten electrodes. Results show that both the photoresist and the glass contribute to the resistance. The glass resistance decreases with increasing temperature and becomes significant at high temperatures. Annealing studies on the photoresist show that the resistance of the photoresist decreases by over five orders of magnitude upon annealing to 500 0 C, with a corresponding decrease in activation energy from 0.27 eV (350 0 C anneal) to 0.10 eV (500 0 C anneal). Time dependent decreases in resistance of the photoresist were also measured for up to 8 to 9 days during high temperature anneals. Some electrolytic transport of tungsten may occur through the photoresist at high temperatures. Results are compared with data on thermoelectric generators and show that photoresist could cause the electrical aging (voltage degradation) problem observed in some generators

  8. 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)

  9. Self-supporting radioisotope generators with STC-55W Stirling converters

    International Nuclear Information System (INIS)

    Or, C.; Kumar, V.; Carpenter, R.; Schock, A.

    2000-01-01

    Previous Orbital Stirling generator designs rely on the spacecraft mounting structure to fasten the radiators, the converters, and the heat source assembly. This paper describes a self-supporting generator concept with a 1-piece honeycomb panel serving as a radiator and a rigid platform for the converters and the heat source assembly to be bolted on. This self-supporting generator allows for simpler mounting structure and more options on mounting location. Using this self-supporting generator concept, we derived four different design options to connect the converter pair rigidly to reduce vibration. This paper describes the four design options and their assembly procedure

  10. 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

  11. 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.

  12. 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

  13. Epoxy Adhesives for Stator Magnet Assembly in Stirling Radioisotope Generators (SRG)

    Science.gov (United States)

    Cater, George M.

    2004-01-01

    As NASA seeks to fulfill its goals of exploration and understanding through missions planned to visit the moons of Saturn and beyond, a number of challenges arise from the idea of deep space flight. One of the first problems associated with deep space travel is electrical power production for systems on the spacecraft. Conventional methods such as solar power are not practical because efficiency decreases substantially as the craft moves away from the Sun. The criterion for power generation during deep space missions are very specific, the main points requiring high reliability, low mass, minimal vibration and a long lifespan. A Stirling generator, although fairly old in concept, is considered to be a potential solution for electrical power generation for deep space flight. A Stirling generator works on the same electromagnetic principles of a standard generator, using the linear motion of the alternator through the stationary stator which produces electric induction. The motion of the alternator, however, is produced by the heating and cooling dynamics of pressurized gases. Essentially heating one end and cooling another of a contained gas will cause a periodic expansion and compression of the gas from one side to the other, which a displacer translates into linear mechanical motion. NASA needs to confirm that the materials used in the generator will be able to withstand the rigors of space and the life expectancy of the mission. I am working on the verification of the epoxy adhesives used to bond magnets to the steel lamination stack to complete the stator; in terms of in-service performance and durability under various space environments. Understanding the proper curing conditions, high temperature properties, and degassing problems as well as production difficulties are crucial to the long term success of the generator. system and steel substrate used in the stator. To optimize the curing conditions of the epoxies, modulated differential scanning calorimetry

  14. Creep properties of forged 2219 T6 aluminum alloy shell of general-purpose heat source-radioisotope thermoelectric generator

    International Nuclear Information System (INIS)

    Hammond, J.P.

    1981-12-01

    The shell (2219 T6 aluminum forging) of the General Purpose Heat Source-Radioisotope Thermoelectric Generator was designed to retain the generator under sufficient elastic stress to secure it during space flight. A major concern was the extent to which the elastic stress would relax by creep. To determine acceptability of the shell construction material, the following proof tests simulating service were performed: 600 h of testing at 270 0 C under 24.1 MPa stress followed by 10,000 h of storage at 177 0 C under 55.1 MPa, both on the ground; and 10,000 h of flight in space at 270 0 C under 34.4 MPa stress. Additionally, systematic creep testing was performed at 177 and 260 0 C to establish creep design curves. The creep tests performed at 177 0 C revealed comparatively large amounts of primary creep followed by small amounts of secondary creep. The early creep is believed to be abetted by unstable substructures that are annealed out during testing at this temperature. The creep tests performed at 270 0 C showed normal primary creep followed by large amounts of secondary creep. Duplicate proof tests simulating the ground exposure conditions gave results that were in good agreement. The proof test simulating space flight at 270 0 C gave 0.11% primary creep followed by 0.59% secondary creep. About 10% of the second-stage creep was caused by four or five instantaneous strains, which began at the 4500-h mark. One or two of these strain bursts, occurred in each of several other tests at 177 and 260 0 C but were assessed as very moderate in magnitude. The effect is attributable to a slightly microsegregated condition remaining from the original cast structure

  15. 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)

  16. 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)

  17. Laser generation of proton beams for the production of short-lived positron emitting radioisotopes

    International Nuclear Information System (INIS)

    Spencer, I.; Ledingham, K.W.D.; Singhal, R.P.; McCanny, T.; McKenna, P.; Clark, E.L.; Krushelnick, K.; Zepf, M.; Beg, F.N.; Tatarakis, M.; Dangor, A.E.; Norreys, P.A.; Clarke, R.J.; Allott, R.M.; Ross, I.N.

    2001-01-01

    Protons of energies up to 37 MeV have been generated when ultra-intense lasers (up to 10 20 W cm -2 ) interact with hydrogen containing solid targets. These protons can be used to induce nuclear reactions in secondary targets to produce β + -emitting nuclei of relevance to the nuclear medicine community, namely 11 C and 13 N via (p, n) and (p,α) reactions. Activities of the order of 200 kBq have been measured from a single laser pulse interacting with a thin solid target. The possibility of using ultra-intense lasers to produce commercial amounts of short-lived positron emitting sources for positron emission tomography (PET) is discussed

  18. Elementary study of encapsulation of radioisotope battery prototype based on 63Ni radio-voltaic effect

    International Nuclear Information System (INIS)

    Gao Hui; Zhang Huaming; Luo Shunzhong; Wang Heyi; Fu Zhonghua

    2012-01-01

    For isotope battery application, it is necessary to encapsulate in a certain method. After having accomplished selection of material composing and proportion, procedure and encapsulating process based on GD3217Y detector. the different types of device come from untouched, loaded by slip of stainless steel with or without 63 Ni isotope were encapsulated respectively. Despite necessary reliability of package has been evaluated in the previous work. in view of specialty due to the incorporation of radioactive isotopes into device, the reliability issue must be further taken into account for actual application. Hence, we emphasize on the comparison about electrical capability of types of devices under the different situations, namely, before and after encapsulation, the natural aging and artificial accelerated aging. The results of the comparison indicate that the adoption of the method of the encapsulation supply effectively stable electrical capability at the condition of ensuring safety of radioactive source besides improving environmental adaptability for device. Further, it offers technological support for the encapsulation of radioisotope battery based on β radio-voltaic effect. (authors)

  19. Characterization of mercury based Indian herbomineral drug by radioisotope induced EDXRF and synchrotron based EXAFS

    International Nuclear Information System (INIS)

    Joseph, Daisy; Saxena, A.; Joseph, Rajeeta; Rajput, P.; Nayak, C.; Bhattacharya, D.; Jha, S.N.; Natrajan, V.

    2014-01-01

    An Indian herbomineral drug was characterized for its trace elements by radioisotope induced EDXRF. The drug contains minerals like mercury, sulfur and arsenic disulfide, along with herbs such as dhaturra, bhrami, vacha etc. All the above ingredients were processed together in a step wise manner (6 steps). Hence the motive was to expect some change in the drug molecule at every step of processing it. The 6 samples are the samples collected at every step of drug preparation. These 6 samples which are collected as intermediatary samples would be then evaluated for its role in various neuropsychological (psychosis, depression etc) disorders in experimental animals such as rats/mice. Hence it was required to find the elements/trace elements composition, details of chemical components present in the drug samples. It was seen that using EDXRF it was possible to determine As and Hg. The EXAFS results also showed the presence of As in their sulphide form. (author)

  20. Radioisotope Thermoelectric Generator Transporation System licensed hardware second certification test series and package shock mount system test

    International Nuclear Information System (INIS)

    Ferrell, P.C.; Moody, D.A.

    1995-10-01

    This paper presents a summary of two separate drop test a e performed in support of the Radioisotope Thermoelectric Generator (RTG) Transportation System (RTGTS). The first portion of this paper presents the second series of drop testing required to demonstrate that the RTG package design meets the requirements of Title 10, Code of Federal Regulations, ''Part 71'' (10 CFR 71). Results of the first test series, performed in July 1994, demonstrated that some design changes were necessary. The package design was modified to improve test performance and the design changes were incorporated into the Safety Analysis Report for Packaging (SARP). The second full-size certification test article (CTA-2) incorporated the modified design and was tested at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. With the successful completion of the test series, and pending DOE Office of Facility Safety Analysis approval of the SARP, a certificate of compliance will be issued for the RTG package allowing its use. The second portion of this paper presents the design and testing of the RTG Package Mount System. The RTG package mount was designed to protect the RTG from excessive vibration during transport, provide shock protection during on/off loading, and provide a mechanism for moving the RTG package with a forklift. Military Standard (MIL-STD) 810E, Transit Drop Procedure (DOE 1989), was used to verify that the shock limiting system limited accelerations in excess of 15 G's at frequencies below 150 Hz. Results of the package mount drop tests indicate that an impact force of 15 G's was not exceeded in any test from a free drop height of 457 mm (18 in.)

  1. 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.

  2. Operations of a Radioisotope-based Propulsion System Enabling CubeSat Exploration of the Outer Planets

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Steven Howe; Nathan Jerred; Troy Howe; Adarsh Rajguru

    2014-05-01

    Exploration to the outer planets is an ongoing endeavor but in the current economical environment, cost reduction is the forefront of all concern. The success of small satellites such as CubeSats launched to Near-Earth Orbit has lead to examine their potential use to achieve cheaper science for deep space applications. However, to achieve lower cost missions; hardware, launch and operations costs must be minimized. Additionally, as we push towards smaller exploration beds with relative limited power sources, allowing for adequate communication back to Earth is imperative. Researchers at the Center for Space Nuclear Research are developing the potential of utilizing an advanced, radioisotope-based system. This system will be capable of providing both the propulsion power needed to reach the destination and the additional requirements needed to maintain communication while at location. Presented here are a basic trajectory analysis, communication link budget and concept of operations of a dual-mode (thermal and electric) radioisotope-based propulsion system, for a proposed mission to Enceladus (Saturnian icy moon) using a 6U CubeSat payload. The radioisotope system being proposed will be the integration of three sub-systems working together to achieve the overall mission. At the core of the system, stored thermal energy from radioisotope decay is transferred to a passing propellant to achieve high thrust – useful for quick orbital maneuvering. An auxiliary closed-loop Brayton cycle can be operated in parallel to the thrusting mode to provide short bursts of high power for high data-rate communications back to Earth. Additionally, a thermal photovoltaic (TPV) energy conversion system will use radiation heat losses from the core. This in turn can provide the electrical energy needed to utilize the efficiency of ion propulsion to achieve quick interplanetary transit times. The intelligent operation to handle all functions of this system under optimized conditions adds

  3. 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

  4. A new integrative methodology for desertification studies based on magnetic and short-lived radioisotope measurements

    International Nuclear Information System (INIS)

    Oldfield, F.; Higgitt, S.R.; Maher, B.A.; Appleby, P.G.; Scoullos, M.

    1986-01-01

    The use of mineral magnetic measurements and short-lived radioisotope studies with 210 Pb and 137 Cs is discussed within the ecosystem watershed conceptual framework. Used in conjunction with geomorphological, sedimentological, palaeoecological and geochemical techniques, these methods can form the core of an integrated multidisciplinary study of desertification and erosion processes on all relevant temporal and spatial scales. 30 refs.; 4 figs

  5. New anti-tumour therapies based on the use of radioisotopes; Nuevas terapias antitumorales con radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Rey, G.

    2009-07-01

    The fundamental limitation of radiotherapy lies in the need to confine its activity to the target organ or tissue, in order to prevent damage to nearby organs and a loss of efficiency due to dispersal throughout the organism. Now, new radioisotopes that allow these disadvantages to be avoided are being used. (Author)

  6. 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)

  7. Optimization Design and Simulation of a Multi-Source Energy Harvester Based on Solar and Radioisotope Energy Sources

    Directory of Open Access Journals (Sweden)

    Hao Li

    2016-12-01

    Full Text Available A novel multi-source energy harvester based on solar and radioisotope energy sources is designed and simulated in this work. We established the calculation formulas for the short-circuit current and open-circuit voltage, and then studied and analyzed the optimization thickness of the semiconductor, doping concentration, and junction depth with simulation of the transport process of β particles in a semiconductor material using the Monte Carlo simulation program MCNP (version 5, Radiation Safety Information Computational Center, Oak Ridge, TN, USA. In order to improve the efficiency of converting solar light energy into electric power, we adopted PC1D (version 5.9, University of New South Wales, Sydney, Australia to optimize the parameters, and selected the best parameters for converting both the radioisotope energy and solar energy into electricity. The results concluded that the best parameters for the multi-source energy harvester are as follows: Na is 1 × 1019 cm−3, Nd is 3.8 × 1016 cm−3, a PN junction depth of 0.5 μm (using the 147Pm radioisotope source, and so on. Under these parameters, the proposed harvester can achieve a conversion efficiency of 5.05% for the 147Pm radioisotope source (with the activity of 9.25 × 108 Bq and 20.8% for solar light radiation (AM1.5. Such a design and parameters are valuable for some unique micro-power fields, such as applications in space, isolated terrestrial applications, and smart dust in battlefields.

  8. Radioisotope camera

    International Nuclear Information System (INIS)

    Tausch, L.M.; Kump, R.J.

    1978-01-01

    The electronic ciruit corrects distortions caused by the distance between the individual photomultiplier tubes of the multiple radioisotope camera on one hand and between the tube configuration and the scintillator plate on the other. For this purpose the transmission characteristics of the nonlinear circuits are altered as a function of the energy of the incident radiation. By this means the threshold values between lower and higher amplification are adjusted to the energy level of each scintillation. The correcting circuit may be used for any number of isotopes to be measured. (DG) [de

  9. 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

  10. Circulation of cerebrospinal fluid. Anatomical bases and physiopathological conditions observed with radioisotopes

    International Nuclear Information System (INIS)

    Oberson, R.

    1975-01-01

    Cerebrospinal fluid circulation (tertiary circulation) was studied by lumbar or sub-occipital injection of radiotracers. The method is divided into three techniques which differ by the location of the injection and the space which is explored. Radio-isotopic cisternography is primarily concerned with the leptomeningitic space of the skull, and sub-occipital injection is preferred. Myelo-scintigraphy is the study principally of the rachidian leptomeningitic space and lumbar injection is preferred in this case. Radio-isotopic ventriculography explores the ependymal space, e.g. the ventricular system. The radiotracer is injected directly or indirectly by Rickham's reservoir, into a horn of a lateral ventricle; these three spaces communicate. Various radiotracers were utilized, the DTPA complex and sup(99m)Tc being preferred. The documents obtained are scintigrams from a scintillation camera [fr

  11. Simultaneous detection and removal of radioisotopes with modified alginate beads containing an azo-based probe using RGB coordinates

    International Nuclear Information System (INIS)

    Jo, Ara; Jang, Geunseok; Namgung, Ho; Kim, Choongho; Kim, Daigeun; Kim, Yujun; Kim, Jongho; Lee, Taek Seung

    2015-01-01

    Highlights: • Modified alginate with azo-based probe (ABO) was synthesized by a reaction between sodium alginate and azo-based probe (BO2). • BO2 was found to be a good probe molecule for radioisotopes using colorimetric analysis. • Detection of Co 2+ and Sr 2+ was mainly carried out via interaction between BO2 and metal ions. • Simultaneous removal of radioisotopes was assessed by the ion-exchange of carboxylate groups in sodium alginate. • The alginate beads with dual functions of detection and removal of metal ions are successfully accomplished. - Abstract: We prepared alginate beads that were modified with an azo-based probe molecule to monitor simultaneously the removal (by alginate) and probing (by the azo-probe molecule) of radioisotopes such as cobalt, strontium, and cesium ions. As an azo-probe molecule, Basic Orange 2 (BO2) was immobilized to the alginate bead. The BO2 in aqueous solution exhibited a slight red shift in absorption with a change in color from orange to dark orange upon addition of cobalt and strontium ions. In contrast, the color of BO2 did not change upon exposure to cesium ions. Thus, the covalently embedded BO2 in alginate beads could adsorb cobalt and strontium ions resulting in recognizable color change of the beads, which was induced by the formation of a complex between BO2 and metal ions. The color changes of the beads in the presence of metal ions were determined quantitatively using RGB color coordinate values. In addition to effectively removing metal ions, the colorimetric coordinate method provides a convenient and simple sensing technique for naked-eye metal ion detection.

  12. 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)

  13. 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

  14. Radioisotope Heater Unit-Based Stirling Power Convertor Development at NASA Glenn Research Center

    Science.gov (United States)

    Wilson, Scott D.; Geng, Steven M.; Penswick, Lawrence; Schmitz, Paul C.

    2017-01-01

    Stirling Radioisotope Power Systems (RPS) are being developed as an option to provide power on future space science missions where robotic spacecraft will orbit, flyby, land or rove. A variety of mission concepts have been studied by NASA and the U. S. Department of Energy that would utilize RPS for landers, probes, and rovers and only require milliwatts to tens of watts of power. These missions would contain science measuring instruments that could be distributed across planetary surfaces or near objects of interest in space solar flux insufficient for using solar cells. A low power Stirling convertor is being developed to provide an RPS option for future low power applications. Initial concepts convert heat available from several Radioisotope Heater Units to electrical power for spacecraft instruments and communication. Initial development activity includes defining and evaluating a variety of Stirling configurations and selecting one for detailed design, research of advanced manufacturing methods that could simplify fabrication, evaluating thermal interfaces, characterizing components and subassemblies to validate design codes, and preparing for an upcoming demonstration of proof of concept in a laboratory environment.

  15. 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

  16. 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

  17. Decontamination of medical radioisotopes from hard surfaces using peelable polymer-based decontamination agents

    International Nuclear Information System (INIS)

    Draine, Amanda E.; Walter, Ken J.; Johnson, Thomas E.

    2008-01-01

    Full text: Medical radioisotopes used to treat and diagnose patients often contaminate surfaces in patient treatment rooms. They are typically short-lived and decay within a matter of days or weeks. However, down time in a medical facility related to radioisotope contamination is costly and can impact patient care. Most liquid or solid spills can be contained and disposed in radioactive wastes fairly completely and quickly; however residual contamination may remain on the contacted surface. Although liquid decontamination agents can be used to address the issue of residual contamination, they often require multiple applications with attendant scrubbing and wiping. Liquid decontamination can also produce large volumes of low-level radioactive waste. To look at reducing radioactive waste volumes, research was conducted on the efficacy of three low-volume peel able decontamination agents. Testing was performed on hard surfaces, such as vinyl composition floor tiles and stainless steel, which are found in many hospitals, research laboratories, and universities. The tiles were contaminated with the medical use isotopes of 99m Tc, Tl-201, and I-131 and subsequently decontaminated with one of the three decontamination agents. Quantitative and qualitative data were obtained for each of three different peel able decontamination agent formulations. Quantitative data included environmental temperature and relative humidity, application thickness, dry time, contact time, and decontamination efficacy of the agents on the tested surfaces. Qualitative factors included ease of application and pee lability, as well as sag resistance and odor of each agent. Initial studies showed that under standard conditions there were reproducible differences in the decontamination efficacies among the three different decontamination formulations. (author)

  18. Radioisotope relay instrument

    International Nuclear Information System (INIS)

    Pozdnyakov, V.N.; Sazonov, O.L.; Taksar, I.M.; Tesnavs, Eh.R.; Yanushkovskij, V.A.

    1974-01-01

    The paper describes a radioisotope relay device containing a radiation source, a detector, an electronic relay block with a comparative threshold mechanism. The device differs from previously known ones in that, for the purpose of increasing stability and speed of action, the electronic relay block is a separate unit and contains two threshold pulse generators which are joined up, across series-connected ''and'' and ''or'' elements, with one of the inputs of the comparative threshold mechanism, whose second input is connected with a detector and whose outputs are connected with a relay element connected by feedback with the above-mentioned ''and'' elements. (author)

  19. High temperature radioisotope capsule

    International Nuclear Information System (INIS)

    Bradshaw, G.B.

    1976-01-01

    A high temperature radioisotope capsule made up of three concentric cylinders, with the isotope fuel located within the innermost cylinder is described. The innermost cylinder has hemispherical ends and is constructed of a tantalum alloy. The intermediate cylinder is made of a molybdenum alloy and is capable of withstanding the pressure generated by the alpha particle decay of the fuel. The outer cylinder is made of a platinum alloy of high resistance to corrosion. A gas separates the innermost cylinder from the intermediate cylinder and the intermediate cylinder from the outer cylinder

  20. Radioisotope electric propulsion of sciencecraft to the outer solar system and near-interstellar space

    International Nuclear Information System (INIS)

    Noble, R.J.

    1998-08-01

    Recent results are presented in the study of radioisotope electric propulsion as a near-term technology for sending small robotic sciencecraft to the outer Solar System and near-interstellar space. Radioisotope electric propulsion (REP) systems are low-thrust, ion propulsion units based on radioisotope electric generators and ion thrusters. Powerplant specific masses are expected to be in the range of 100 to 200 kg/kW of thrust power. Planetary rendezvous missions to Pluto, fast missions to the heliopause (100 AU) with the capability to decelerate an orbiter for an extended science program and prestellar missions to the first gravitational lens focus of the Sun (550 AU) are investigated

  1. 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.)

  2. Manual for reactor produced radioisotopes

    International Nuclear Information System (INIS)

    2003-01-01

    numerous new developments that have taken place since then. Hence in this manual it was decided to focus only on reactor produced radioisotopes. This manual contains procedures for 48 important reactor-produced isotopes. These were contributed by major radioisotope producers from different parts of the world and are based on their practical experience. In case of widely used radioisotopes such as 131 I, 32 P and 99 Mo, information from more than one centre is included so that the users can compare the procedures. As in the earlier two versions, a general introductory write-up is included covering basic information on related aspects such as target irradiation, handling facilities, radiation protection and transportation, but in less detail. Relevant IAEA publications on such matters, particularly related to radiation protection and transportation, should be referred to for guidelines. Similarly, the nuclear data contained in the manual are only indicative and the relevant databases should be referred to for more authentic values. It is hoped that the manual will be a useful source of information for those working in radioisotope production laboratories as well as those intending to initiate such activities

  3. 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)

  4. 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

  5. The Use of Redundancy to Improve Reliability of Deep Space Missions Using Stirling Radioisotope Generator Power Sources

    Science.gov (United States)

    Bolotin, Gary; Everline, Chet; Schmitz, Paul; Distefano, Sal

    2014-01-01

    This study will look at the 140 We class generator as originally envisioned for the ASRG and a larger generator that is scaled up to use four times the fuel. The results discussed below quantify the effect of the use of smaller generators and indicates that a scheme that makes use of several smaller generators enhances the system reliability and allows for more graceful degradation.

  6. 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

  7. 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

  8. Effect of updated data base and improved analysis on performance of radioisotope thermophotovoltaic converter

    International Nuclear Information System (INIS)

    Schock, A.; Or, C.T.

    1996-01-01

    Previous analyses of RTPV space power systems published by the authors were based on a number of approximations employed to permit early dissemination of preliminary results pending availability of fuller experimental data need3d to conduct more rigorous analyses. Among those approximations were: (1) the use of limited test data and optimistic projections of the spectral transmissivity of the RTPV's selective IR filters and of the spectral quantum efficiency of the GaSb PV cells; (2) the use of theoretical formulas instead of experimental measurements of the PV cell's open-circuit voltage, fill factor, and optimum voltage instead of its measured current-voltage characteristics; (3) rough estimates of the TPV converter's active-area fraction instead of computed values based on detailed designs; (4) inadequate accounting for the effect of radiation reflected by the IR filter and absorbed by the emitter in reducing the generator's required heat input; and (5) omission of the shadowing effect and ohmic losses caused by the PV cell's grid lines. The above-listed shortcomings of the previously published analyses are addressed in the present paper, which describes revised analyses based on recently obtained experimental data of IR filter reflectivities and PV cell quantum efficiencies and current-voltage characteristic, measured by EDTEK under an OSC-initiated subcontract to its ongoing DOE contract. Their test results show that EDTEK has been eminently successful in improving the reflectivities of the IR filters and in reproducing the quantum efficiencies of Boeing's best PV cells, but their initial (Dec-95) PV cell fell far short of matching the open-circuit voltages and fill factors predicted by theory

  9. Strategies toward the commercialization PZC-based Tc-99m generator in the Philippines

    International Nuclear Information System (INIS)

    Borras, Ma. Teresa L.; Sombrito, Elvira Z.; Dela Rosa, Alumanda M.; Osorio, Rizalina G.; Bulos, Adelina DM.

    2007-01-01

    Technetium-99m ( 99m Tc) is the most widely used radioisotope in nuclear medicine. It accounts for more than 80% of the total demand for radioisotopes. Alone or conjugated with other ligands, it is very useful in the imaging and scanning of various organs such as the brain, lungs, kidneys, liver, thyroid and bone and in the diagnosis of metabolic disorders. It is imported to the country as 99 Mo- 99m Tc generators. These commercial generators use fission molybdenum adsorbed onto alumina column. A Draft Business Plan for the Production of PZC 99 Mo- 99m Tc Generator in the Philippines was presented during the FNCA 2005 Workshop on the Utilization of Research Reactors, August 08-12, 2005. The Philippine Nuclear Research Institute (PNRI) proposed in the draft business plan, the commercial production of PZC generator through the establishment of a facility for the in-house production of 99 Mo- 99m Tc generators. The radioisotope laboratory of the Irradiation Services Unit will be renovated to house the PZC based 99 Mo- 99m Tc generator experiment/production facility. Since the research reactor is on extended shutdown, the supply of 99 Mo will be sourced out from neighboring countries. Information dissemination and promotions will be made in order to bring this PZC based 99 Mo- 99m Tc generator to the nuclear medicine users. (author)

  10. Elementary study on encapsulation reliability of radioisotope battery prototype based on 63Ni Radio-Voltaic effect

    International Nuclear Information System (INIS)

    Gao Hui; Zhang Huaming; Luo Shunzhong; Wang Heyi

    2012-01-01

    For isotope battery application, it is necessary to encapsulate in a certain method. After having accomplished selection of material composing and proportion, procedure and encapsulating process based on GD3217Y detector, the different types of device come from untouched, loaded by slip of stainless steel with or without 63 Ni isotope were encapsulated respectively. Despite necessary reliability of package was evaluated in the previous work, in view of specialty due to the incorporation of radioactive isotopes into device, the reliability issue must be further taken into account for actual application. Hence, we emphasize on the comparison about electrical capability of types of devices under the different situations, namely, before and after encapsulation, the natural aging and artificial accelerated aging. The results of the comparison indicate that the adoption of the method of the encapsulation supplies effectively stable electrical capability at the condition of ensuring safety of radioactive source besides improving environmental adaptability for device. Further, it offers technological support for the encapsulation of radioisotope battery based on β radio-voltaic effect. (authors)

  11. 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)

  12. High-Efficiency, Nanowire Based Thermoelectric Devices for Radioisotope Power Conversion, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — This SBIR Phase I proposal responds to topic S3.03 of the 2010 NASA SBIR solicitation, for Power Generation and Conversion. Thermoelectric devices offer a simple and...

  13. Radioisotope electric propulsion of sciencecraft to the outer Solar System and near-interstellar space

    International Nuclear Information System (INIS)

    Noble, R.J.

    1999-01-01

    Radioisotopes have been used successfully for more than 25 years to supply the heat for thermoelectric generators on various deep-space probes. Radioisotope electric propulsion (REP) systems have been proposed as low-thrust ion propulsion units based on radioisotope electric generators and ion thrusters. The perceived liability of radioisotope electric generators for ion propulsion is their high mass. Conventional radioisotope thermoelectric generators have a specific mass of about 200 kg/kW of electric power. Many development efforts have been undertaken with the aim of reducing the specific mass of radioisotope electric systems. Recent performance estimates suggest that specific masses of 50 kg/kW may be achievable with thermophotovoltaic and alkali metal thermal-to-electric conversion generators. Powerplants constructed from these near-term radioisotope electric generators and long-life ion thrusters will likely have specific masses in the range of 100 to 200 kg/kW of thrust power if development continues over the next decade. In earlier studies, it was concluded that flight times within the Solar System are indeed insensitive to reductions in the powerplant specific mass, and that a timely scientific program of robotic planetary rendezvous and near-interstellar space missions is enabled by primary electric propulsion once the powerplant specific mass is in the range of 100 to 200 kg/kW. Flight times can be substantially reduced by using hybrid propulsion schemes that combine chemical propulsion, gravity assist, and electric propulsion. Hybrid schemes are further explored in this article to illustrate how the performance of REP is enhanced for Pluto rendezvous, heliopause orbiter, and gravitational lens missions

  14. 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

  15. 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

  16. Development of an experimental radioisotope based process tomography system for research applications in a cold trickle bed column

    International Nuclear Information System (INIS)

    Sau, Madhusudan; Kumar, Pravesh; Kumar, Umesh; Acharya, Rajesh; Singh, Gursharan

    2009-01-01

    In chemical and petrochemical engineering applications, random and structured packing are used in process columns to enhance the heat and mass transfer between two phases. The packing used in such columns is meant to obtain a high specific interfacial area. It is of paramount importance for scale-up and design of trickle bed process columns, to understand and predict the complex multiphase fluid dynamics. In simplified terms, the phase holdup, solid packing distribution in terms of density and gas and liquid velocities among other important parameters need to be qualitatively and quantitatively understood. In the petrochemical industry, many processes are carried out using fixed bed reactors with concurrent upward and downward gas and liquid flows. In order to characterize the liquid and gas flow distribution through a mock-up column, data on planar and volume density distribution using computed tomographic measurements are very helpful. The paper describes the development efforts of a multi-detector 137 Cs radioisotope based in-situ tomography scanner suitable for 600mm dia. cold trickle bed reactor. The development work is at present in progress. The schematics and development of the scanner gantry is described in this paper. (author)

  17. Miniaturized radioisotope solid state power sources

    Science.gov (United States)

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

    2000-01-01

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

  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. 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

  20. 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

  1. Reducing Disparity in Radio-Isotopic and Astrochronology-Based Time Scales of the Late Eocene and Oligocene

    NARCIS (Netherlands)

    Sahy, Diana; Condon, Daniel J.; Hilgen, Frederik J.|info:eu-repo/dai/nl/102639876; Kuiper, Klaudia F.|info:eu-repo/dai/nl/258125772

    2017-01-01

    A significant discrepancy of up to 0.6 Myr exists between radio-isotopically calibrated and astronomically tuned time scales of the late Eocene-Oligocene. We explore the possible causes of this discrepancy through the acquisition of “high-precision” 206Pb/238U dating of zircons from 11 volcanic ash

  2. Buckling Analysis for the Shape of the Thin-tube Support of Radioisotope Thermoelectric Generator to investigate structure integrity

    International Nuclear Information System (INIS)

    Park, Jong Han; Son, Kwang Jae; Hong, Jintae; Kim, Jong Bum

    2016-01-01

    Radiation detection using scintillator light produced in materials is one of the oldest and most useful techniques for the detection of a variety of radiations. A detector using plastic scintillators is well known to have an easy operation because it consists of a chemically stable material. In general, a plastic scintillator using a polymer such as polymethylmethacrylate (PMMA), polyvinyltoluene (PVT) or polystyrene (PS) is added to an organic scintillator. As an organic scintillator, the first solute is p-terphenyl or 2.5-diphenyloxazole (PPO), and the second solute is 1,4-bis [5-phenyl-2-oxazol] benzene (POPOP). A method for preparing a plastic scintillator is a mixture of a polymer and organic scintillators used for thermal polymerization. In this study, we prepared a plastic scintillator whose manufacturing process is simple and can be freely shaped. A thin plate of the plastic scintillator was manufactured using epoxy resin as a polymer. The optimal mixture ratio to prepare the plastic scintillator was derived from the above results. Using the derived results, we made the large-area plastic scintillator which can quickly measure the contamination site and evaluated characteristics of the large-area plastic scintillator in the laboratory. A thin plate of a plastic scintillator with a simple preparation process can be freely shaped using epoxy resin and organic scintillators such as PPO and POPOP. PPO emits scintillation of light in the ultraviolet range, and POPOP is a wave shifter for moving the wavelength responsible for the PMT. The mixture ratio of PPO and POPOP was determined using their emission spectra. The optimal weight percentage of PPO and POPOP in an organic scintillator was determined to be 0.2 wt%:0.01 wt%. Based on the above results, the large-area plastic scintillator of the window size of a typical pancake-type surface contamination counter was prepared. We want to evaluate the characteristics of the large-area plastic scintillator. However

  3. Buckling Analysis for the Shape of the Thin-tube Support of Radioisotope Thermoelectric Generator to investigate structure integrity

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong Han; Son, Kwang Jae; Hong, Jintae; Kim, Jong Bum [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Radiation detection using scintillator light produced in materials is one of the oldest and most useful techniques for the detection of a variety of radiations. A detector using plastic scintillators is well known to have an easy operation because it consists of a chemically stable material. In general, a plastic scintillator using a polymer such as polymethylmethacrylate (PMMA), polyvinyltoluene (PVT) or polystyrene (PS) is added to an organic scintillator. As an organic scintillator, the first solute is p-terphenyl or 2.5-diphenyloxazole (PPO), and the second solute is 1,4-bis [5-phenyl-2-oxazol] benzene (POPOP). A method for preparing a plastic scintillator is a mixture of a polymer and organic scintillators used for thermal polymerization. In this study, we prepared a plastic scintillator whose manufacturing process is simple and can be freely shaped. A thin plate of the plastic scintillator was manufactured using epoxy resin as a polymer. The optimal mixture ratio to prepare the plastic scintillator was derived from the above results. Using the derived results, we made the large-area plastic scintillator which can quickly measure the contamination site and evaluated characteristics of the large-area plastic scintillator in the laboratory. A thin plate of a plastic scintillator with a simple preparation process can be freely shaped using epoxy resin and organic scintillators such as PPO and POPOP. PPO emits scintillation of light in the ultraviolet range, and POPOP is a wave shifter for moving the wavelength responsible for the PMT. The mixture ratio of PPO and POPOP was determined using their emission spectra. The optimal weight percentage of PPO and POPOP in an organic scintillator was determined to be 0.2 wt%:0.01 wt%. Based on the above results, the large-area plastic scintillator of the window size of a typical pancake-type surface contamination counter was prepared. We want to evaluate the characteristics of the large-area plastic scintillator. However

  4. Semantic attributes based texture generation

    Science.gov (United States)

    Chi, Huifang; Gan, Yanhai; Qi, Lin; Dong, Junyu; Madessa, Amanuel Hirpa

    2018-04-01

    Semantic attributes are commonly used for texture description. They can be used to describe the information of a texture, such as patterns, textons, distributions, brightness, and so on. Generally speaking, semantic attributes are more concrete descriptors than perceptual features. Therefore, it is practical to generate texture images from semantic attributes. In this paper, we propose to generate high-quality texture images from semantic attributes. Over the last two decades, several works have been done on texture synthesis and generation. Most of them focusing on example-based texture synthesis and procedural texture generation. Semantic attributes based texture generation still deserves more devotion. Gan et al. proposed a useful joint model for perception driven texture generation. However, perceptual features are nonobjective spatial statistics used by humans to distinguish different textures in pre-attentive situations. To give more describing information about texture appearance, semantic attributes which are more in line with human description habits are desired. In this paper, we use sigmoid cross entropy loss in an auxiliary model to provide enough information for a generator. Consequently, the discriminator is released from the relatively intractable mission of figuring out the joint distribution of condition vectors and samples. To demonstrate the validity of our method, we compare our method to Gan et al.'s method on generating textures by designing experiments on PTD and DTD. All experimental results show that our model can generate textures from semantic attributes.

  5. Radioisotopes in sedimentology

    International Nuclear Information System (INIS)

    Courtois, G.

    1967-01-01

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

  6. Radioisotopic Thermoelectric Generator (RTG) Surveillance

    Energy Technology Data Exchange (ETDEWEB)

    Mulford, Roberta Nancy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-29

    This lecture discusses stockpile stewardship efforts and the role surveillance plays in the process. Performance of the RTGs is described, and the question of the absence of anticipated He is addressed.

  7. 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.

  8. A Survey on the Usage and Demand of Medical Radioisotope and Radiopharmaceuticals in Malaysia

    International Nuclear Information System (INIS)

    Muhammad Fakhrurazi Ahmad Fadzil; Siti Selina Abdul Hamid; Siti Najila Mohd Janib; Azahari Kasbollah; Syed Asraf Fahlawi Wafa

    2016-01-01

    Medical radioisotope is a small quantity of radioactive substance used for the purpose of diagnostic and therapy of various diseases. In Malaysia, the emerging of new nuclear medicine centers or institutions in both government and private sectors rose abruptly for the past few years. Currently, there are no data available on the usage and demand of these medical radioisotope or radiopharmaceuticals. The aim of this study is to assess current medical radioisotopes and radiopharmaceuticals usage and also to provide data on current medical radioisotope and radiopharmaceuticals demand for both private and government hospitals or institutions in Malaysia. A survey for a period of 3 months was conducted across Malaysia. The survey was divided into five (5) main parts and it was distributed among health care professionals involved working with medical radioisotope and radiopharmaceuticals in private, government and university based hospitals or institutions and was distributed manually either by hand, mail or e-mail. Data is presented in either pie chart or bar chart. Survey results found out that the highest demand and the highest usage among all radioisotopes are Technetium-99m and radioiodine isotopes such as the iodine-131, iodine-131 MIBG, iodine-123 and iodine-123 MIBG. Technetium-99m is the backbone of nuclear medicine whereby more than 80 % of Nuclear Medicine services utilize this radioisotope. Technetium-99m supply chain is unstable globally and in coming future, two main reactors that produce 60 % of world Molybdenum-99 will shut down and the supply of molybdenum-99 will be disrupted. In radioiodine services, currently, Iodine-123 cannot be obtained in Malaysia and neighboring countries due to its short half-life. Iodine-123 is useful in diagnostic of thyroid related diseases. As for PET services, the highest demands are F-18 FDG and gallium-68 Generator. It is important for Malaysia to self-produced medical radioisotope and radiopharmaceuticals to meet the

  9. 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

  10. 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)

  11. Revealing smuggled nuclear material covered by a legitimate radioisotope shipment using CdTe-based gamma-ray spectrometry

    CERN Document Server

    Lakosi, L; Zsigrai, J; Safar, J

    2003-01-01

    Illicit trade of nuclear materials (NM) represents a serious challenge to radiation monitoring upon scenarios, when legitimate radioisotope shipments are used to obscure the weak radiation of NM. Planar and hemispherical Cd(Zn)Te detectors with a portable mini-multichannel analyzer were proven to be suitable, in measuring times of 10 min order, for revealing the presence of low-enriched or natural U-bearing reactor fuel pellets in amounts of kg order, placed beside transport containers of lead or depleted uranium, which contain high activity sup 6 sup 0 Co (10 GBq range) or sup 1 sup 9 sup 2 Ir (TBq range) radioisotope sources. Such a hand-held or portable device may help authorities combating illicit trafficking of nuclear materials.

  12. 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)

  13. Feasibility Study and System Architecture of Radioisotope Thermoelectric Generation Power Systems for USMC Forward Operating Bases

    Science.gov (United States)

    2013-06-01

    33 d. Initial Pure Mass to Produce 300W Power at EOL ...............33 e. Initial Compound Mass to Produce 300W Power at EOL ....34 f...Estimated Cost to Produce 300W Power at EOL ...................34 2. Estimated Cost and Weight Data...energy at beginning of life (BOL), and after 10 years ( EOL ) was calculated, along with the estimated cost associated with the purchase of each

  14. 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)

  15. 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

  16. Radioisotope production at PUSPATI - five year programme

    International Nuclear Information System (INIS)

    Yusof Azuddin Ali; Abdul Rahman Mohamad Ali.

    1983-01-01

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

  17. Micromotor-based energy generation.

    Science.gov (United States)

    Singh, Virendra V; Soto, Fernando; Kaufmann, Kevin; Wang, Joseph

    2015-06-01

    A micromotor-based strategy for energy generation, utilizing the conversion of liquid-phase hydrogen to usable hydrogen gas (H2), is described. The new motion-based H2-generation concept relies on the movement of Pt-black/Ti Janus microparticle motors in a solution of sodium borohydride (NaBH4) fuel. This is the first report of using NaBH4 for powering micromotors. The autonomous motion of these catalytic micromotors, as well as their bubble generation, leads to enhanced mixing and transport of NaBH4 towards the Pt-black catalytic surface (compared to static microparticles or films), and hence to a substantially faster rate of H2 production. The practical utility of these micromotors is illustrated by powering a hydrogen-oxygen fuel cell car by an on-board motion-based hydrogen and oxygen generation. The new micromotor approach paves the way for the development of efficient on-site energy generation for powering external devices or meeting growing demands on the energy grid. © 2015 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  18. 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.)

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

    International Nuclear Information System (INIS)

    1991-07-01

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

  20. Advanced radioisotope power source options for Pluto Express

    International Nuclear Information System (INIS)

    Underwood, M.L.

    1995-01-01

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

  1. 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?.

  2. 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)

  3. Radioisotope waste processing systems

    International Nuclear Information System (INIS)

    Machida, Tadashi

    1978-01-01

    The Atomic Energy Safety Bureau established the policy entitled ''On Common Processing System of Radioactive Wastes'' consulting with the Liaison Committee of Radioactive Waste Processing. Japan Atomic Energy Research Institute (JAERI) and Japan Radioisotope Association (JRIA) had been discussing the problems required for the establishment of the common disposal facilities based on the above policy, and they started the organization in spring, 1978. It is a foundation borrowing equipments from JAERI though installing newly some of them not available from JAERI, and depending the fund on JRIA. The operation expenses will be borne by those who want to dispose the wastes produced. The staffs are sent out from JAERI and JRIA. For animal wastes contaminated with RI, formaldehyde dipping should be abolished, but drying and freezing procedures will be taken before they are burnt up in a newly planned exclusive furnace with disposing capacity of 50 kg/hour. To settle the problems of other wastes, enough understanding and cooperation of users are to be requested. (Kobatake, H.)

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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...

  9. Radioisotopes in Industry

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-05-01

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

  10. 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. Stantardization problems in radioisotopic techniques for measuring rock density and humidity

    International Nuclear Information System (INIS)

    Golubin, O.V.; Pavlov, L.S.

    1977-01-01

    A description of the main technical characteristics is given of radioisotope densimeters and hydrometers taken as a base for the State Standard design for field radioisotope instruments for measuring density and moisture of the soil and rocks

  12. 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

  13. 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.

  14. 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)

  15. 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)

  16. 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

  17. 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

  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. 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

  20. 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.

  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. 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

  3. 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)

  4. 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)

  5. 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

  6. 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.

  7. 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

  8. Development of Radioisotope Tracer Technology

    International Nuclear Information System (INIS)

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

    2007-06-01

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

  9. [Intel random number generator-based true random number generator].

    Science.gov (United States)

    Huang, Feng; Shen, Hong

    2004-09-01

    To establish a true random number generator on the basis of certain Intel chips. The random numbers were acquired by programming using Microsoft Visual C++ 6.0 via register reading from the random number generator (RNG) unit of an Intel 815 chipset-based computer with Intel Security Driver (ISD). We tested the generator with 500 random numbers in NIST FIPS 140-1 and X(2) R-Squared test, and the result showed that the random number it generated satisfied the demand of independence and uniform distribution. We also compared the random numbers generated by Intel RNG-based true random number generator and those from the random number table statistically, by using the same amount of 7500 random numbers in the same value domain, which showed that the SD, SE and CV of Intel RNG-based random number generator were less than those of the random number table. The result of u test of two CVs revealed no significant difference between the two methods. Intel RNG-based random number generator can produce high-quality random numbers with good independence and uniform distribution, and solves some problems with random number table in acquisition of the random numbers.

  10. 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)

  11. 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

  12. 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).

  13. 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)

  14. 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.

  15. 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.

  16. 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

  17. Micro-battery Development using beta radioisotope

    International Nuclear Information System (INIS)

    Jung, H. K.; Cheong, Y. M.; Lee, N. H.; Choi, Y. S.; Joo, Y. S.; Lee, J. S.; Jeon, B. H.

    2007-06-01

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

  18. 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

  19. Safe Handling of Radioisotopes

    International Nuclear Information System (INIS)

    1958-01-01

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

  20. 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

  1. 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

  2. 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

  3. 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.

  4. Radioisotope electric propulsion for robotic science missions to near-interstellar space

    International Nuclear Information System (INIS)

    Noble, R.J.

    1994-10-01

    The use of radioisotope electric propulsion for sending small robotic probes on fast science missions several hundred astronomical units (AU) from the Sun is investigated. Such missions would address a large variety of solar, interstellar, galactic and cosmological science themes from unique vantage points at 100 to 600 AU, including parallax distance measurements for the entire Milky Way Galaxy, sampling of the interstellar medium and imaging of cosmological objects at the gravitational lens foci of the Sun (≥ 550 AU). Radioisotope electric propulsion (REP) systems are low-thrust, ion propulsion units based on multi-hundred watt, radioisotope electric generators and ion thrusters. In a previous work, the flight times for rendezvous missions to the outer planets (< 30 AU) using REP were found to be less than fifteen years. However fast prestellar missions to several hundred AU are not possible unless the probe's energy can be substantially increased in the inner Solar System so as to boost the final hyperbolic excess velocity. In this paper an economical hybrid propulsion scheme combining chemical propulsion and gravity assist in the inner Solar System and radioisotope electric propulsion in the outer Solar System is studied which enables fast prestellar missions. Total hyperbolic excess velocities of 15 AU/year and flight times to 550 AU of about 40 years are possible using REP technology that may be available in the next decade

  5. 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)

  6. Cardiovascular: radioisotopic angiocardiography

    International Nuclear Information System (INIS)

    Kriss, J.P.

    1975-01-01

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

  7. Radio-isotopic tracers

    International Nuclear Information System (INIS)

    Wolfangel, R.G.

    1976-01-01

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

  8. Radioisotopes for nuclear medicine: the future

    International Nuclear Information System (INIS)

    Carr, S.W.

    1998-01-01

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

  9. Radioisotope thermionic converters for space applications

    International Nuclear Information System (INIS)

    Miskolczy, G.; Lieb, D.P.

    1990-01-01

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

  10. 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.

  11. 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

  12. Comparison of RT-PCR-Dot blot hybridization based on radioisotope 32P with conventional RT-PCR and commercial ELISA Assays for blood screening of HIV-1

    International Nuclear Information System (INIS)

    Maria Lina R; Andi Yasmon

    2011-01-01

    There are many commercial ELISA and rapid test kits that have been used for blood screening; however, the kits can give false positive and negative results. Therefore, RT-PCR (Reverse Transcription Polymerase Chain Reaction) - Dot Blot Hybridization based on radioisotope 32 P (RDBR) method was developed in this research, to compare the method with the conventional RT-PCR and commercial ELISA Enzyme-Linked lmmunosorbent Assay) kit. This method is efficient for screening of large blood specimens and surveillance study. Eighty seven samples were used and serum of the samples were tested by ELISA to detect HIV-1. The HIV-l RNA genome was extracted from plasma samples and tested using the RT-PCR and RDBR methods. Of 87 samples that were tested, the rates of positive testing of the RT-PCR, the RDBR, and the ELISA were 71.26%, 74.71%, and 80.46%, respectively. The RDBR (a combination of RTPCR and dot blot hybridization) was more sensitive than conventional RT-PCR by showing 3.45% in increase number of positive specimens. The results showed that of 9 samples (10.34%) were negative RDBR and positive ELISA, while 4 samples (4.60%) were negative ELISA and positive RDBR. The two methods showed slightly difference in the results but further validation is still needed. However, RDBR has high potential as an alternative method for screening of blood in large quantities when compared to method of conventional RT-PCR and ELISA. (author)

  13. 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.)

  14. 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

  15. 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

  16. 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...

  17. Radioisotope indicator, type BETA 2

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  18. 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

  19. Medical application of radioisotopes

    International Nuclear Information System (INIS)

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

    2000-05-01

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

  20. Medical application of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-05-01

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

  1. 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)

  2. Health problems of industrial applications of radioisotopes

    International Nuclear Information System (INIS)

    Kudrna, J.

    1976-01-01

    Radiation hygiene problems of industrial radioisotope applications are discussed. The observance of regulations is emphasised. Radiation protection is based on the principle of preventing early radiation damage and limiting late radiation damage to an acceptable level. The basic requirement is that the cumulated dose should be as low as possible, i.e., as low as is practically feasible in considering economic and social aspects. Notices 59/72 and 65/72, Collection of Laws, rule that if the limit of 3/10 of the maximum permissible dose is likely to be reached, control zones should be defined and marked at places of work where radioisotopes are handled. The characteristics of such a control zone are listed and the measures to be taken in case of accident are outlined. (B.S.)

  3. 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)

  4. Developing a Free-Piston Stirling Convertor for advanced radioisotope space power systems

    Science.gov (United States)

    Qiu, Songgang; Augenblick, John E.; White, Maurice A.; Peterson, Allen A.; Redinger, Darin L.; Petersen, Stephen L.

    2002-01-01

    The Department of Energy (DOE) has selected Free-Piston Stirling Convertors as a technology for future advanced radioisotope space power systems. In August 2000, DOE awarded competitive Phase I, Stirling Radioisotope Generator (SRG) power system integration contracts to three major aerospace contractors, resulting in SRG conceptual designs in February 2001. All three contractors based their designs on the Technology Demonstration Convertor (TDC) developed by Stirling Technology Company (STC) for DOE. The contract award to a single system integration contractor for Phases II and III of the SRG program is anticipated in late 2001. The first potential SRG mission is targeted for a Mars rover. This paper provides a description of the Flight Prototype (FP) Stirling convertor design as compared to the previous TDC design. The initial flight prototype units are already undergoing performance tuning at STC. The new design will be hermetically scaled and will provide a weight reduction from approximately 4.8 kg to approximately 3.9 kg. .

  5. Steps of radioisotope separation in Japan

    International Nuclear Information System (INIS)

    Nakane, Ryohei; Kitamoto, Asashi; Shimizu, Masami

    1998-03-01

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

  6. Investigation of the present management status of calibration source based on the law concerning prevention of radiation hazards due to radioisotopes

    International Nuclear Information System (INIS)

    Takahashi, Yasuyuki; Igarashi, Hiroshi; Hirano, Kunihiro; Kawaharada, Yasuhiro; Igarashi, Hitoshi; Murase, Ken-ya; Mochizuki, Teruhito

    2007-01-01

    An amendment concerning the enforcement of the law on the prevention of radiation hazards due to radioisotopes, etc., and the medical service law enforcement regulations were promulgated on June 1, 2005. This amendment concerned international basic safety standards and the sealing of radiation sources. Sealed radiation sources ≤3.7 MBq, which had been excluded from regulation, were newly included as an object of regulation. Investigation of the single photon emission computed tomography (SPECT) system instituted in hospitals indicated that almost all institutions adhere to the new amendment, and the calibration source, the checking source, etc., corresponding to this amendment were maintained appropriately. Any institutions planning to return sealed radioisotopes should refer to this report. (author)

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

    International Nuclear Information System (INIS)

    1991-01-01

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

  8. 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

  9. 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)

  10. Status of the study on PZC based Tc-99m generator and potential of its commercial production in VIETNAM

    International Nuclear Information System (INIS)

    Dong, Duong Van

    2007-01-01

    Tc-99m is the most widely used radioisotope in nuclear medicine. It has been almost produced from the decay of its parent 99 Mo by using the (n,γ) nuclear reaction with natural molybdenum. The technology requirement for this processing is simple, and is used in the most developing countries operating research reactor. Under the framework of Forum for Nuclear Cooperation in Asia (FNCA) cooperation program, the PZC based technology for production of Tc-99m generator has been studied at Dalat Nuclear Research Institute (DNRI) in the past several years. Some main activities and results of the study on PZC based Tc-99m generator at DNRI so far are given, and the estimation of future applications of PZC-type Tc-99m generator in Vietnam is also discussed in this report. (author)

  11. Dose rate visualization of radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Schwarz, R.A.; Kessler, S.F.; Tomaszewski, T.A.

    1995-09-01

    Advanced visualization techniques can be used to investigate gamma ray and neutron dose rates around complex dose rate intensive operations. A method has been developed where thousands of dose points are calculated using the MCNP(Monte Carlo N-Particle) computer code and then displayed to create color contour plots of the dose rate for complex geometries. Once these contour plots are created, they are sequenced together creating an animation to dynamically show how the dose rate changes with changes in the geometry or source over time

  12. Berkeley Off-line Radioisotope Generator (BORG)

    CERN Document Server

    Sudowe, R

    2001-01-01

    Development of chemical separations for the transactinides has traditionally been performed with longer-lived tracer activities purchased commercially. With these long-lived tracers, there is always the potential problem that the tracer atoms are not always in the same chemical form as the short-lived atoms produced in on-line experiments. This problem is especially severe for elements in groups 4 and 5 of the periodic table, where hydrolysis is present. The long-lived tracers usually are stored with a complexing agent to prevent sorption or precipitation. Chemistry experiments performed with these long-lived tracers are therefore not analogous to those chemical experiments performed in on-line experiments. One way to eliminate the differences between off-line and on-line chemistry experiments is through the use of a sup 2 sup 5 sup 2 Cf fission fragment collection device. A sup 2 sup 5 sup 2 Cf fission fragment collection device has already been constructed [1]. This device is limited in its capabilities. A ...

  13. Berkeley Off-line Radioisotope Generator (BORG)

    International Nuclear Information System (INIS)

    Sudowe, Ralf; Patin, Joshua B.

    2001-01-01

    Development of chemical separations for the transactinides has traditionally been performed with longer-lived tracer activities purchased commercially. With these long-lived tracers, there is always the potential problem that the tracer atoms are not always in the same chemical form as the short-lived atoms produced in on-line experiments. This problem is especially severe for elements in groups 4 and 5 of the periodic table, where hydrolysis is present. The long-lived tracers usually are stored with a complexing agent to prevent sorption or precipitation. Chemistry experiments performed with these long-lived tracers are therefore not analogous to those chemical experiments performed in on-line experiments. One way to eliminate the differences between off-line and on-line chemistry experiments is through the use of a 252 Cf fission fragment collection device. A 252 Cf fission fragment collection device has already been constructed [1]. This device is limited in its capabilities. A new fission fragment device would allow the study of the chemical properties of the homologues of the heaviest elements. This new device would be capable of producing fission fragments for fast gas chemistry and aqueous chemistry experiments, long-lived tracers for model system development and neutrons for neutron activation. Fission fragment activities produced in this way should have the same chemical form as those produced in Cyclotron irradiations. The simple operation of this source will allow more rapid and reliable development of radiochemical separations with homologues of transactinide elements

  14. Dose rate visualization of radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Schwarz, R.A.; Kessler, S.F.; Tomaszewski, T.A.

    1996-01-01

    Advanced visualization techniques can be used to investigate gamma ray and neutron dose rates around complex dose rate intensive operations. A method has been developed where thousands of dose points are calculated using the MCNP (Monte Carlo N-Particle) computer code (Briesmeister 1993) and then displayed to create color contour plots of the dose rate for complex geometries. Once these contour plots are created, they are sequenced together creating an animation to dynamically show how the dose rate changes with changes in the geometry or source over time. copyright 1996 American Institute of Physics

  15. An efficient parallel pseudorandom bit generator based

    Indian Academy of Sciences (India)

    In this paper, an asymmetric coupled map lattice (CML) combining sawtooth map as a local map is presented and its chaotic behaviours are analysed. Based on this asymmetric CML, a pseudorandom bit generator (PRBG) is proposed. The specific parameters of the system that make complicated floating-point computation ...

  16. 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.

  17. 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)

  18. Radioisotope study of Eustachian tube

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  19. Radioisotopes in engineering and industry

    International Nuclear Information System (INIS)

    Castagnet, A.C.G.

    1986-01-01

    The applications of radioisotope techniques in engineering and materials quality control are shown. The inventory of mercury in electrolytical cells, the transit and residence time measurements in several processes and radiotracer control are studied. The radioactive tracers in hydrologycal problems is evaluated. (M.J.C.) [pt

  20. Radioisotopes point the way ahead

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  1. 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)

  2. 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

  3. Modeling thrombin generation: plasma composition based approach.

    Science.gov (United States)

    Brummel-Ziedins, Kathleen E; Everse, Stephen J; Mann, Kenneth G; Orfeo, Thomas

    2014-01-01

    Thrombin has multiple functions in blood coagulation and its regulation is central to maintaining the balance between hemorrhage and thrombosis. Empirical and computational methods that capture thrombin generation can provide advancements to current clinical screening of the hemostatic balance at the level of the individual. In any individual, procoagulant and anticoagulant factor levels together act to generate a unique coagulation phenotype (net balance) that is reflective of the sum of its developmental, environmental, genetic, nutritional and pharmacological influences. Defining such thrombin phenotypes may provide a means to track disease progression pre-crisis. In this review we briefly describe thrombin function, methods for assessing thrombin dynamics as a phenotypic marker, computationally derived thrombin phenotypes versus determined clinical phenotypes, the boundaries of normal range thrombin generation using plasma composition based approaches and the feasibility of these approaches for predicting risk.

  4. 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.

  5. 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

  6. Enhancing SAT-Based Test Pattern Generation

    Institute of Scientific and Technical Information of China (English)

    LIU Xin; XIONG You-lun

    2005-01-01

    This paper presents modeling tools based on Boolean satisfiability (SAT) to solve problems of test generation for combinational circuits. It exploits an added layer to maintain circuit-related information and value justification relations to a generic SAT algorithm. It dovetails binary decision graphs (BDD) and SAT techniques to improve the efficiency of automatic test pattern generation (ATPG). More specifically, it first exploits inexpensive reconvergent fanout analysis of circuit to gather information on the local signal correlation by using BDD learning, then uses the above learned information to restrict and focus the overall search space of SAT-based ATPG. Its learning technique is effective and lightweight. The experimental results demonstrate the effectiveness of the approach.

  7. 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)

  8. Waypoint Generation Based on Sensor Aimpoint

    Science.gov (United States)

    2009-03-01

    United States Government . AFIT/GAE/ENV/09-M01 WAYPOINT GENERATION BASED ON SENSOR AIMPOINT THESIS Presented to the Faculty Department of Aeronautical...BATCAM. Aviones physics parameters for the Procerus testbed, the Unicorn UAV, were provided by Procerus, which allowed another simulated MAV to 48 be...flown in the HIL tests. The AFIT Advanced Navigation Technologies (ANT) Center did not own a Unicorn UAV, so it could not be flown in flight tests

  9. 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.

  10. 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

  11. 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)

  12. Reliability Issues in Stirling Radioisotope Power Systems

    Science.gov (United States)

    Schreiber, Jeffrey; Shah, Ashwin

    2005-01-01

    Stirling power conversion is a potential candidate for use in a Radioisotope Power System (RPS) for space science missions because it offers a multifold increase in the conversion efficiency of heat to electric power and reduced requirement of radioactive material. Reliability of an RPS that utilizes Stirling power conversion technology is important in order to ascertain long term successful performance. Owing to long life time requirement (14 years), it is difficult to perform long-term tests that encompass all the uncertainties involved in the design variables of components and subsystems comprising the RPS. The requirement for uninterrupted performance reliability and related issues are discussed, and some of the critical areas of concern are identified. An overview of the current on-going efforts to understand component life, design variables at the component and system levels, and related sources and nature of uncertainties are also discussed. Current status of the 110 watt Stirling Radioisotope Generator (SRG110) reliability efforts is described. Additionally, an approach showing the use of past experience on other successfully used power systems to develop a reliability plan for the SRG110 design is outlined.

  13. System simulation on fractionation radiation doses and radioisotope handling in Nuclear medicine

    International Nuclear Information System (INIS)

    Dytz, Aline Guerra; Dullius, Marcos Alexandre; Gomes, Camila e Silva

    2008-01-01

    This paper describes the practical and theoretical learning of students from Medical Physics course at the Fundacao Universidade Federal do Rio Grande (FURG) on fractionation radiation doses, radioisotope handling and elution of molybdenum generators (Mo-99) / technetium (Tc -99m)

  14. Graph based techniques for tag cloud generation

    DEFF Research Database (Denmark)

    Leginus, Martin; Dolog, Peter; Lage, Ricardo Gomes

    2013-01-01

    Tag cloud is one of the navigation aids for exploring documents. Tag cloud also link documents through the user defined terms. We explore various graph based techniques to improve the tag cloud generation. Moreover, we introduce relevance measures based on underlying data such as ratings...... or citation counts for improved measurement of relevance of tag clouds. We show, that on the given data sets, our approach outperforms the state of the art baseline methods with respect to such relevance by 41 % on Movielens dataset and by 11 % on Bibsonomy data set....

  15. 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

  16. Determination of the radiological impact of radioisotope waste disposal

    International Nuclear Information System (INIS)

    1986-09-01

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

  17. 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

  18. Some results of radioisotope studies

    Energy Technology Data Exchange (ETDEWEB)

    Isamov, N.N.

    1974-10-01

    The accumulation of radioisotopes by brucellae depends on the consistency of the feed medium on which they are grown. The uptake of P-32 is a factor of 5 to 16 greater, and that of sulfur-35 in the form of sodium sulfate is a factor of 30 to 100 greater when grown on a complex solid agar than in a bouillion solution of the same ingredients. Brucellae are readily tagged with /sup 32/P and /sup 35/S simultaneously. These tagged brucellae were used to study in vitro storage under various temperature regimes. Brucellae actively incorporate iron. The uptake of methionine and cystine tagged with sulfur-35 by brucellae was investigated. Methionine is absorbed directly for the most part by brucellae, while the sulfur-35 in sodium sulfate is primarily transformed to cystine and cysteine. The uptake of various radioisotopes can be used to type various strains of brucellae. Isotopes are used to trace the course of various diseases in animals. (SJR)

  19. 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.

  20. 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.)

  1. Physical aspects of radioisotope brachytherapy

    International Nuclear Information System (INIS)

    1967-01-01

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

  2. 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)

  3. Background current of radioisotope manometer

    International Nuclear Information System (INIS)

    Vydrik, A.A.

    1987-01-01

    The technique for calculating the main component of the background current of radioisotopic monometers, current from direct collision of ionizing particles and a collector, is described. The reasons for appearance of background photoelectron current are clarified. The most effective way of eliminating background current components is collector protection from the source by a screen made of material with a high gamma-quanta absorption coefficient, such as lead, for example

  4. A draft plan for the routine production of PZC based 99mTc generator in the Vietnam

    International Nuclear Information System (INIS)

    Duong Van Dong

    2007-01-01

    This is an outline of the radioisotope production programme using a research reactor of 500 kW in Vietnam. Under the framework of Forum for Nuclear Cooperation in Asia (FNCA) cooperation program, the PZC based technology for production of 99m Tc-generator has been studied at Dalat Nuclear Research Institute (DNRI) as well as FNCA members countries in the past several years. The FNCA project has shown the feasibility of using a PZC column-reactor 99 Mo- 99m Tc-generator for commercial applications, citing mainly the cheaper cost of the PZC generator than the imported alumina column-fission 99 Mo generator and excellent technology achievement has been established and optimized by close cooperation between FNCA country members and KAKEN, JAERI. DNRI proposes in this draft business plan, the commercial production of PZC generator through the establishment of national project stage 2006-2008 for the routine production of 99 Mo- 99m Tc generator. In this national project the 99m Tc-generator will use PZC coming from KAKEN - Japan or locally synthesis as the column material, 99 Mo sourced from neighboring countries or irradiated at or reactor and the semi-automatic loading and adsorption machine will be studied, designed and installed in the hot cells available. Because the DNRI have facility 99m Tc-generator production line with two hot cells used production of the 99m Tc generator by using fission 99 Mo. The generator assembly will be designed and fabricated. (author)

  5. 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)

  6. The application of radioisotopes in the Argentine technology

    International Nuclear Information System (INIS)

    Baro, G.B.; Lazor, C.J.

    1976-10-01

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

  7. Component-Based Cartoon Face Generation

    Directory of Open Access Journals (Sweden)

    Saman Sepehri Nejad

    2016-11-01

    Full Text Available In this paper, we present a cartoon face generation method that stands on a component-based facial feature extraction approach. Given a frontal face image as an input, our proposed system has the following stages. First, face features are extracted using an extended Active Shape Model. Outlines of the components are locally modified using edge detection, template matching and Hermit interpolation. This modification enhances the diversity of output and accuracy of the component matching required for cartoon generation. Second, to bring cartoon-specific features such as shadows, highlights and, especially, stylish drawing, an array of various face photographs and corresponding hand-drawn cartoon faces are collected. These cartoon templates are automatically decomposed into cartoon components using our proposed method for parameterizing cartoon samples, which is fast and simple. Then, using shape matching methods, the appropriate cartoon component is selected and deformed to fit the input face. Finally, a cartoon face is rendered in a vector format using the rendering rules of the selected template. Experimental results demonstrate effectiveness of our approach in generating life-like cartoon faces.

  8. Investigation of Insulation Materials for Future Radioisotope Power Systems

    Science.gov (United States)

    Cornell, Peggy A.; Hurwitz, Frances I.; Ellis, David L.; Schmitz, Paul C.

    2013-01-01

    NASA's Radioisotope Power Systems (RPS) Technology Advancement Project is developing next generation high-temperature insulation materials that directly benefit thermal management and improve performance of RPS for future science missions. Preliminary studies on the use of multilayer insulation (MLI) for Stirling convertors used on the Advanced Stirling Radioisotope Generator (ASRG) have shown the potential benefits of MLI for space vacuum applications in reducing generator size and increasing specific power (W/kg) as compared to the baseline Microtherm HT (Microtherm, Inc.) insulation. Further studies are currently being conducted at NASA Glenn Research Center on candidate MLI foils and aerogel composite spacers. This paper presents the method of testing of foils and spacers and experimental results to date.

  9. Investigation of Insulation Materials for Future Radioisotope Power Systems (RPS)

    Science.gov (United States)

    Cornell, Peggy A.; Hurwitz, Frances I.; Ellis, David L.; Schmitz, Paul C.

    2013-01-01

    NASA's Radioisotope Power System (RPS) Technology Advancement Project is developing next generation high temperature insulation materials that directly benefit thermal management and improve performance of RPS for future science missions. Preliminary studies on the use of multilayer insulation (MLI) for Stirling convertors used on the Advanced Stirling Radioisotope Generator (ASRG) have shown the potential benefits of MLI for space vacuum applications in reducing generator size and increasing specific power (W/kg) as compared to the baseline Microtherm HT (Microtherm, Inc.) insulation. Further studies are currently being conducted at NASA Glenn Research Center (GRC) on candidate MLI foils and aerogel composite spacers. This paper presents the method of testing of foils and spacers and experimental results to date.

  10. Safe Handling of Radioisotopes. Health Physics Addendum

    International Nuclear Information System (INIS)

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

    1960-01-01

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

  11. Safe Handling of Radioisotopes. Health Physics Addendum

    Energy Technology Data Exchange (ETDEWEB)

    Appleton, G J; Krishnamoorthy, P N

    1960-07-15

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

  12. 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.

  13. Safe Handling of Radioisotopes. Medical Addendum

    International Nuclear Information System (INIS)

    Hercik, F.; Jammet, H.

    1960-01-01

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

  14. Stirling Convertor Performance Mapping Test Results for Future Radioisotope Power Systems

    Science.gov (United States)

    Qiu, Songgang; Peterson, Allen A.; Faultersack, Franklyn D.; Redinger, Darin L.; Augenblick, John E.

    2004-02-01

    Long-life radioisotope-fueled generators based on free-piston Stirling convertors are an energy-conversion solution for future space applications. The high efficiency of Stirling machines makes them more attractive than the thermoelectric generators currently used in space. Stirling Technology Company (STC) has been performance-testing its Stirling generators to provide data for potential system integration contractors. This paper describes the most recent test results from the STC RemoteGen™ 55 W-class Stirling generators (RG-55). Comparisons are made between the new data and previous Stirling thermodynamic simulation models. Performance-mapping tests are presented including variations in: internal charge pressure, cold end temperature, hot end temperature, alternator temperature, input power, and variation of control voltage.

  15. Clinical evaluation of Proscillaridin-A with radioisotopes

    International Nuclear Information System (INIS)

    Franco, P.D.A.; Cordovil, I.L.; Rocha, A.F.G.

    1976-01-01

    Thirty patients with cardiac insufficiency were evaluated under the use of Proscillaridin-A. The analysis was based on classic clinical parameters and 11 patients through the circulation time with the radioisotopic technique. The results obtained are analysed and discussed about the absence of side effects, considering as well the therapeutic use of the drug [pt

  16. 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

  17. 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

  18. 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.

  19. 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

  20. Economics of coal-based electricity generation

    Energy Technology Data Exchange (ETDEWEB)

    Hemming, D F; Johnston, R; Teper, M

    1979-01-01

    The report deals with base-load electricity generation from coal and compares the economics of four alternative technologies: conventional pulverised-fuel (PF) boiler with steam cycle; atmospheric fluidised-bed (AFB) boiler with steam cycle; pressurised fluidised-bed (PFB) boiler with combined cycle; and integrated air-blown coal gasification with combined cycle systems are compared for both a high sulphur (3.5%) coal with environmental regulations requiring 85% sulphur removal, and for a low sulphur coal without sulphur removal. The results indicate that there is no single clear 'winner' among the advanced technologies. The optimum system depends on coal price, required rate-of-return, sulphur content of the coal, taxation regime etc. (34 refs.) (Available from IEA Coal Research, Economic Assessment Service)

  1. The industrial application of radioisotopes

    International Nuclear Information System (INIS)

    Frevert, E.

    1991-01-01

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

  2. 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

  3. Radioisotope studies on coconut nutrition

    International Nuclear Information System (INIS)

    Ray, P.K.

    1979-01-01

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

  4. Artificial radioisotopes in hydrological investigation

    International Nuclear Information System (INIS)

    Plata-Bedmar, A.

    1988-01-01

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

  5. Problems of coal-based power generation

    International Nuclear Information System (INIS)

    Noskievic, P.

    1996-01-01

    Current problems of and future trends in coal-based power generation are discussed. The present situation is as follows: coal, oil and gas contribute to world fossil fuel resources 75%, 14%, and 11%, respectively, and if the current trend will continue, will be depleted in 240, 50, and 60 years, respectively; the maximum resource estimates (including resources that have not yet been discovered) are 50% higher for oil and 100% higher for gas, for coal such estimates have not been made. While the world prices of coal are expected to remain virtually constant, the prices of gas will probably increase to be twice as high in 2010. Thus, the role of coal may be higher in the next century than it is now, provided that due attention is paid to improving the efficiency of coal-fired power plants and reducing their adverse environmental effects. A comparison of economic data for coal-fired and gas-fired power plants is as follows: Investment cost (USD/kW): 1400, 800; fixed running cost (USD/kW.y): 33.67, 9.0; variable running cost (USD/kWh): 0.30, 0.15; power use (kJ/kWh): 10.29, 7.91; annual availability (%): 70, 50; fuel price (USD/GJ): 1.00, 4.30; power price (USD/kWh): 4.28, 5.52. The investment cost for coal-fired plants covers new construction including flue gas purification. The integrated gasification combined cycle (IGCC) seems to be the future of coal-based power generation. The future problems to be addressed include ways to reduce air pollution, improving the efficiency of the gas-steam cycle, and improving the combustion process particularly with a view to reducing substantially its environmental impact. (P.A.). 4 figs., 4 tabs., 9 refs

  6. 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

  7. Production capabilities in US nuclear reactors for medical radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-11-01

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

  8. The regulations for enforcing the law concerning prevention from radiation hazards due to radioisotopes

    International Nuclear Information System (INIS)

    1978-01-01

    These provisions are established on the basis of and to enforce the ''Law for the prevention of radiation hazards due to radioisotopes'' and the Enforcement Order for the ''Law concerning the prevention of radiation hazards due to radioisotopes''. The Regulation includes the definitions of terms, applications for the permission of the use of radioisotopes, standards on usage, obligation of measurement, persons in charge of radiation, etc. Terms are explained, such as persons engaging in radiation works, persons who enter at any time the control areas, radiation facilities, maximum permissible exposure dose, cumulative dose, maximum permissible cumulative dose, maximum permissible concentration in the air, maximum permissible concentration in water and maximum permissible surface density. The applications for permission in written forms are required for the use, sale and abandonment of radioisotopes. Radioisotopes or the apparatuses for generating radiation shall be used in the using facilities. The measurement of radiation dose rate, particle flux density and contamination due to radioisotopes shall be made with radiation-measuring instruments. At least one person shall be chosen as the chief radiation-handling person in each factory, establishment, selling office or abandoning establishment by a user, a trademan or a person engaged in abandonment of radioisotopes. The forms for the application for permission, etc. are attached. (Okada, K.)

  9. 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)

  10. 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

  11. 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)

  12. 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

  13. 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)

  14. 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.)

  15. Proposed Brookhaven accelerator-based neutron generator

    International Nuclear Information System (INIS)

    Grand, P.; Batchelor, K.; Chasman, R.; Rheaume, R.

    1976-01-01

    The d-Li Neutron Source concept, which includes a high-current dueteron linac, is an outgrowth of attempts made to use the BNL, 200-MeV proton linac BLIP facility to do radiation damage studies. It included a 100 mA, 30-MeV deuteron linear accelerator and a fast-flowing liquid lithium jet as the target. The latest design is not very different, except that the current is now 200 mA and the linac energy has been raised to 35 MeV. Both parameters, were changed to optimize the effectiveness of the facility with respect to flux, experimental volume and match to 14 MeV neutron-radiation-damage effects. The proposed Brookhaven Accelerator-based Neutron Generator is described with particular emphasis on the linear accelerator. The proposed facility is a practical and efficient way of producing the intense, high energy neutron beams needed for CTR material studies. The accelerator and liquid-metal technologies are well proven, state-of-the-art technologies. The fact that no new technology is required guarantees the possibility of meeting construction schedules, and more importantly, guarantees a high level of operational reliability

  16. 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

  17. A rule-based software test data generator

    Science.gov (United States)

    Deason, William H.; Brown, David B.; Chang, Kai-Hsiung; Cross, James H., II

    1991-01-01

    Rule-based software test data generation is proposed as an alternative to either path/predicate analysis or random data generation. A prototype rule-based test data generator for Ada programs is constructed and compared to a random test data generator. Four Ada procedures are used in the comparison. Approximately 2000 rule-based test cases and 100,000 randomly generated test cases are automatically generated and executed. The success of the two methods is compared using standard coverage metrics. Simple statistical tests showing that even the primitive rule-based test data generation prototype is significantly better than random data generation are performed. This result demonstrates that rule-based test data generation is feasible and shows great promise in assisting test engineers, especially when the rule base is developed further.

  18. Generative Inferences Based on Learned Relations

    Science.gov (United States)

    Chen, Dawn; Lu, Hongjing; Holyoak, Keith J.

    2017-01-01

    A key property of relational representations is their "generativity": From partial descriptions of relations between entities, additional inferences can be drawn about other entities. A major theoretical challenge is to demonstrate how the capacity to make generative inferences could arise as a result of learning relations from…

  19. The state of enforcement of the Law Concerning Prevention from Radiation Hazards Due to Radioisotopes, etc

    International Nuclear Information System (INIS)

    1978-01-01

    In recent years, the uses of radioisotopes and radiation generators have advanced remarkably in Japan. The establishments utilizing them are on rapid increase in industries, medicine, research and education. Furthermore, since the types of usage are more diversified, the kinds of radioisotopes and their quantities are also increasing. In this connection, The Law Concerning Prevention from Radiation Hazards Due to Radioisotopes, etc. has been in force for about twenty years. Under the current situation in this field, importance of the administration concerning enforcement of The Law is ever rising. In the Science and Technology Agency, in view of the occurrence of accidents in certain enterprises, starting in fiscal 1974, various measures have been taken. As the state of enforcement of The Law, the following matters are presented; the establishments using, selling and disposing of radioisotopes, etc. up to fiscal 1977 (in tables); and variety of governmental measures taken by the Agency. (Mori, K.)

  20. Radioisotopic studies in renal transplantation

    International Nuclear Information System (INIS)

    Levasseur, A.; Robillard, R.; Lemieux, R.; Dandavino, R.; Girard, R.

    1981-01-01

    Radioisotopic evaluation of kidney graft function has greatly reduced the need for more invasive studies such as arteriography, retrograde pyelograpy and graft biopsy. The schedule of sequential studies beginning the day after transplant may be modified according to the patient's clinical or biochemical status. The combined use of I 131 Hippuran and sup(99m)Tc DTPA allows early detection of graft rejection and its differentiation from tubular necrosis. Scintigraphic images may have a characteristic appearance in cases of arterial, venous or urinary obstruction, urinary fistule, infarction, abcess and lymphocele. This non-invasive diagnostic study requiring only an intravenous injection is simple, rapid, accurate and may be repeated as often as necessary. (auth) [fr

  1. 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

  2. Radioisotope tracer applications in industry

    International Nuclear Information System (INIS)

    Rao, S.M.

    1987-01-01

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

  3. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Birks, J L [Singleton Hospital, Swansea (UK)

    1976-06-01

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

  5. Radioisotopic Studies of Brain Uptake

    International Nuclear Information System (INIS)

    Oldendorf, W. H.

    1970-01-01

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

  6. 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

  7. 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.

  8. 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

  9. 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.

  10. Rule-based Test Generation with Mind Maps

    Directory of Open Access Journals (Sweden)

    Dimitry Polivaev

    2012-02-01

    Full Text Available This paper introduces basic concepts of rule based test generation with mind maps, and reports experiences learned from industrial application of this technique in the domain of smart card testing by Giesecke & Devrient GmbH over the last years. It describes the formalization of test selection criteria used by our test generator, our test generation architecture and test generation framework.

  11. 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)

  12. 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.

  13. 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

  14. 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.)

  15. Neutron generator based on adiabatic trap

    International Nuclear Information System (INIS)

    Golovin, I.N.; Zhil'tsov, V.A.; Panov, D.A.; Skovoroda, A.A.; Shatalov, G.E.; Shcherbakov, A.G.

    1988-01-01

    A possibility of 14 MeV neutron generator (NG) production on the basis of axial-symmetric adiabatic trap with MHD cusped armature for the testing of materials and elements of the DT reactor first wall and blanket structure is discussed. General requirements to NG are formulated. It is shown that the NG variant discussed meets the requirements formulated. Approximate calculation of the NG parameters has shown that total energy consumption by the generator does not exceed 220 MW at neutron flux specific capacity of 2.5 MW/m 2 and radiation test area of 5-6 m 2

  16. 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

  17. 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

  18. Distributed Graph-Based State Space Generation

    NARCIS (Netherlands)

    Blom, Stefan; Kant, Gijs; Rensink, Arend; De Lara, J.; Varro, D.

    LTSMIN provides a framework in which state space generation can be distributed easily over many cores on a single compute node, as well as over multiple compute nodes. The tool works on the basis of a vector representation of the states; the individual cores are assigned the task of computing all

  19. Parylene-based electret power generators

    International Nuclear Information System (INIS)

    Lo, Hsi-wen; Tai, Yu-Chong

    2008-01-01

    An electret power generator is developed using a new electret made of a charged parylene HT® thin-film polymer. Here, parylene HT® is a room-temperature chemical-vapor-deposited thin-film polymer that is MEMS and CMOS compatible. With corona charge implantation, the surface charge density of parylene HT® is measured as high as 3.69 mC m −2 . Moreover, it is found that, with annealing at 400 °C for 1 h before charge implantation, both the long-term stability and the high-temperature reliability of the electret are improved. For the generator, a new design of the stator/rotor is also developed. The new micro electret generator does not require any sophisticated gap-controlling structure such as tethers. With the conformal coating capability of parylene HT®, it is also feasible to have the electret on the rotors, which is made of either a piece of metal or an insulator. The maximum power output, 17.98 µW, is obtained at 50 Hz with an external load of 80 MΩ. For low frequencies, the generator can harvest 7.7 µW at 10 Hz and 8.23 µW at 20 Hz

  20. Automatic Tamil lyric generation based on ontological interpretation ...

    Indian Academy of Sciences (India)

    In this work, we use an ontology to determine the semantic information from ... Hence, to study the context-based lyric generation process, we referred to ...... Mann C W and Moore A J 1981 Computer Generation of Multiparagraph English text.

  1. 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.

  2. 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

  3. 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

  4. Stability improvement of induction generator-based wind turbine systems

    DEFF Research Database (Denmark)

    Chen, Zhe; Hu, Y.; Blaabjerg, Frede

    2007-01-01

    The stability improvement of induction-generator-based wind turbine systems under power system fault conditions has been studied. Two types of generators are considered, namely rotor short-circuited induction generators and dynamic slip-controlled wound rotor induction generators. The factors...... affecting the stability are analysed. The characteristics of the induction-generator-based wind turbines are described, and possible methods of improving stability of the wind generators are discussed. The system modelling is presented, and then the discussed methods of improving stability are investigated...

  5. Recovery of hafnium radioisotopes from a proton irradiated tantalum target

    International Nuclear Information System (INIS)

    Taylor, W.A.; Garcia, J.G.; Hamilton, V.T.; Heaton, R.C.; Jamriska, D.J.; Ott, M.A.; Philips, D.R.; Radzinski, S.D.

    1998-01-01

    The 178m2 Hf nucleus, with its long half-life (31 y) and high-spin isomeric state (16 + ) is desired for new and exotic nuclear physics studies. The Los Alamos Radioisotope Program irradiated a kilogram of natural tantalum at the Los Alamos Meson Physics Facility in early 1981. After fifteen years of decay, this target was ideal for the recovery of 178m2 Hf. There was more than a millicurie of 178m2 Hf produced during this irradiation and there has been a sufficient period of time for most of the other hafnium radioisotopes to decayed away. Traditionally, separation techniques for recovering hafnium isotopes from tantalum targets employ solvent extractions with reagents that are considered hazardous. These techniques are no longer condoned because they generate a mixed-waste (radioactive and hazardous components) that can not be treated for disposal. In this paper we describe a new and unique procedure for the recovery of hafnium radioisotopes from a highly radioactive, proton irradiated, tantalum target using reagents that do not contribute a hazardous waste component. (author)

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

    International Nuclear Information System (INIS)

    Castagnet, A.C.G.

    1976-01-01

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

  7. 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.

  8. Radioisotope Concentration in Lake Sediments of Maracaibo, Venezuela

    International Nuclear Information System (INIS)

    Salas, A. Rangel; Viloria, T.; Sajo-Bohus, L.; Barros, H.; Greaves, E. D.; Palacios, D.

    2007-01-01

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

  9. 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.)

  10. 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)

  11. 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

  12. 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)

  13. Current status of radio-isotopes utilization

    Energy Technology Data Exchange (ETDEWEB)

    Singh, M [Banaras Hindu Univ. (India)

    1974-08-01

    Utilization of radioisotopes were reviewed briefly in a categorized manner. In plant biochemistry, long lived radioactive carbon ,/sup 14/C, was applied to clarify such metabolic processes as photosynthesis, respiration and protein synthesis, etc., while radioactive oxygen ,/sup 18/O, was used to study the O/sub 2/ generation mechanism. Radioactive phosphorus ,/sup 32/P, was used to detect the amount, grain size of phosphatic fertilizer as well as the time and depth for better utilization. Radioactive sulphur ,/sup 35/S, and nitrogen ,/sup 15/N, could be of use in studies of protein metabolism in plants. Radioactive tracers of other minerals such as N, P, K, Ca, Mg, Zn, Mo, B, and Co were also used to detect their specific role in plants. Use of radioactive isotopes in protein synthesis and transfer of genetic information was described. Radioactive iodine ,/sup 131/I, binding capacity of milk proteins, and radio trace studies in the iodine turn over in the use of radioactive iodine were summarized.

  14. Prospect of radioisotopes and radiation utilization

    International Nuclear Information System (INIS)

    Tabata, Yoneho

    1994-01-01

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

  15. Implanted artificial heart with radioisotope power source

    Energy Technology Data Exchange (ETDEWEB)

    Shumakov, V I; Griaznov, G M; Zhemchuzhnikov, G N; Kiselev, I M; Osipov, A P

    1983-02-01

    An atomic artificial heart for orthotopic implantation was developed with the following characteristics: volume, 1.2 L; weight, 1.5 kg; radioisotope power, 45 W; operating life, up to 5 years; hemodynamics, similar to natural hemodynamics. The artificial heart includes a thermal drive with systems for regulating power, feeding steam into the cylinders, return of the condensate to the steam generator, and delivery of power to the ventricles and heat container. The artificial heart is placed in an artificial pericardium partially filled with physiologic solution. It uses a steam engine with two operating cylinders that separately drive the left and right ventricles. There is no electronic control system in the proposed design. The operation of the heat engine is controlled, with preservation of autoregulation by the vascular system of the body. The separate drives for the ventricles is of primary importance as it provides for operation of the artificial heart through control of cardiac activity by venous return. Experimental testing on a hydromechanical bench demonstrated effective autoregulation.

  16. Early radioisotope uses in Mexico

    International Nuclear Information System (INIS)

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

    1991-10-01

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

  17. 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

  18. Artificial radioisotopes in food chains

    International Nuclear Information System (INIS)

    Binnerts, W.T.; Faber, K.; Klijn, N.; Lemmens, C.; Wissink, M.

    1986-01-01

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

  19. Development of radioisotope tracer technology

    International Nuclear Information System (INIS)

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

    2000-04-01

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

  20. Early radioisotope uses in Mexico

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-10-15

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

  1. Estimating evaporative vapor generation from automobiles based on parking activities

    International Nuclear Information System (INIS)

    Dong, Xinyi; Tschantz, Michael; Fu, Joshua S.

    2015-01-01

    A new approach is proposed to quantify the evaporative vapor generation based on real parking activity data. As compared to the existing methods, two improvements are applied in this new approach to reduce the uncertainties: First, evaporative vapor generation from diurnal parking events is usually calculated based on estimated average parking duration for the whole fleet, while in this study, vapor generation rate is calculated based on parking activities distribution. Second, rather than using the daily temperature gradient, this study uses hourly temperature observations to derive the hourly incremental vapor generation rates. The parking distribution and hourly incremental vapor generation rates are then adopted with Wade–Reddy's equation to estimate the weighted average evaporative generation. We find that hourly incremental rates can better describe the temporal variations of vapor generation, and the weighted vapor generation rate is 5–8% less than calculation without considering parking activity. - Highlights: • We applied real parking distribution data to estimate evaporative vapor generation. • We applied real hourly temperature data to estimate hourly incremental vapor generation rate. • Evaporative emission for Florence is estimated based on parking distribution and hourly rate. - A new approach is proposed to quantify the weighted evaporative vapor generation based on parking distribution with an hourly incremental vapor generation rate

  2. Potential Applications for Radioisotope Power Systems in Support of Human Exploration Missions

    Science.gov (United States)

    Cataldo, Robert L.; Colozza, Anthony J.; Schmitz, Paul C.

    2013-01-01

    Radioisotope power systems (RPS) for space applications have powered over 27 U.S. space systems, starting with Transit 4A and 4B in 1961, and more recently with the successful landing of the Mars Science Laboratory rover Curiosity in August 2012. RPS enable missions with destinations far from the Sun with faint solar flux, on planetary surfaces with dense or dusty atmospheres, and at places with long eclipse periods where solar array sizes and energy storage mass become impractical. RPS could also provide an enabling capability in support of human exploration activities. It is envisioned that with the higher power needs of most human mission concepts, a high efficiency thermal-to-electric technology would be required such as the Advanced Stirling Radioisotope generator (ASRG). The ASRG should be capable of a four-fold improvement in efficiency over traditional thermoelectric RPS. While it may be impractical to use RPS as a main power source, many other applications could be considered, such as crewed pressurized rovers, in-situ resource production of propellants, back-up habitat power, drilling, any mobile or remote activity from the main base habitat, etc. This paper will identify potential applications and provide concepts that could be a practical extension of the current ASRG design in providing for robust and flexible use of RPS on human exploration missions.

  3. Radioisotope applications for troubleshooting and optimizing industrial processes

    International Nuclear Information System (INIS)

    2002-03-01

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

  4. Cold flow study of liquid cooled pebble bed reactor (LC-PBR) through radioisotope techniques

    International Nuclear Information System (INIS)

    Verma, Rupesh; Upadhyay, Rajesh K.; Pant, H.J.

    2017-01-01

    As the world's demand for energy continues to increase burning of coal, oil and natural gases continue to increase which will eventually cause build-up in emission of greenhouse gasses. To overcome this challenge worldwide effort is in progress to develop an economical, more efficient and safer nuclear power. Higher thermal efficiency and enhances safety feature of Generation IV liquid cooled pebble bed reactor (LC-PBR) makes it viable option to replace existing nuclear reactor. However, this reactor is still in research stage and need detailed study before commercialization. In current work, hydrodynamics of LC-PBR is studied by using radioisotope based techniques, radioactive particle tracking and gamma-ray densitometry. Pebble flow profile and distribution are measured for different operating conditions. Optimal operating parameters are identified for operating LC-PBR based on hydrodynamics. (author)

  5. Efficient pseudorandom generators based on the DDH assumption

    NARCIS (Netherlands)

    Rezaeian Farashahi, R.; Schoenmakers, B.; Sidorenko, A.; Okamoto, T.; Wang, X.

    2007-01-01

    A family of pseudorandom generators based on the decisional Diffie-Hellman assumption is proposed. The new construction is a modified and generalized version of the Dual Elliptic Curve generator proposed by Barker and Kelsey. Although the original Dual Elliptic Curve generator is shown to be

  6. Optical Generation of Fuzzy-Based Rules

    Science.gov (United States)

    Gur, Eran; Mendlovic, David; Zalevsky, Zeev

    2002-08-01

    In the last third of the 20th century, fuzzy logic has risen from a mathematical concept to an applicable approach in soft computing. Today, fuzzy logic is used in control systems for various applications, such as washing machines, train-brake systems, automobile automatic gear, and so forth. The approach of optical implementation of fuzzy inferencing was given by the authors in previous papers, giving an extra emphasis to applications with two dominant inputs. In this paper the authors introduce a real-time optical rule generator for the dual-input fuzzy-inference engine. The paper briefly goes over the dual-input optical implementation of fuzzy-logic inferencing. Then, the concept of constructing a set of rules from given data is discussed. Next, the authors show ways to implement this procedure optically. The discussion is accompanied by an example that illustrates the transformation from raw data into fuzzy set rules.

  7. Thermoelectric Generators Based on Ionic Liquids

    Science.gov (United States)

    Laux, Edith; Uhl, Stefanie; Jeandupeux, Laure; López, Pilar Pérez; Sanglard, Pauline; Vanoli, Ennio; Marti, Roger; Keppner, Herbert

    2018-06-01

    Looking at energy harvesting using body or waste heat for portable electronic or on-board devices, Ionic liquids are interesting candidates as thermoactive materials in thermoelectric generators (TEGs) because of their outstanding properties. Two different kinds of ionic liquid, with alkylammonium and choline as cations, were studied, whereby different anions and redox couples were combined. This study focussed on the intention to find non-hazardous and environmentally friendly ionic liquids for TEGs to be selected among the thousands that can potentially be used. Seebeck coefficients (SEs) as high as - 15 mV/K were measured, in a particular case for an electrode temperature difference of 20 K. The bottleneck of our TEG device is still the abundance of negative SE liquids matching the internal resistance with the existing positive SE-liquids at series connections. In this paper, we show further progress in finding increased negative SE liquids. For current extraction from the TEG, the ionic liquid must be blended with a redox couple, allowing carrier exchange in a cyclic process under a voltage which is incuced by the asymmetry of the generator in terms of hot and cold electrodes. In our study, two types of redox pairs were tested. It was observed that a high SE of an ionic liquid/redox blend is not a sufficient condition for high power output. It appears that more complex effects between the ionic liquid and the electrode determine the magnitude of the final current/power output. The physico-chemical understanding of such a TEG cell is not yet available.

  8. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs.

  9. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1994-12-01

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs

  10. 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

  11. Model Based Analysis and Test Generation for Flight Software

    Science.gov (United States)

    Pasareanu, Corina S.; Schumann, Johann M.; Mehlitz, Peter C.; Lowry, Mike R.; Karsai, Gabor; Nine, Harmon; Neema, Sandeep

    2009-01-01

    We describe a framework for model-based analysis and test case generation in the context of a heterogeneous model-based development paradigm that uses and combines Math- Works and UML 2.0 models and the associated code generation tools. This paradigm poses novel challenges to analysis and test case generation that, to the best of our knowledge, have not been addressed before. The framework is based on a common intermediate representation for different modeling formalisms and leverages and extends model checking and symbolic execution tools for model analysis and test case generation, respectively. We discuss the application of our framework to software models for a NASA flight mission.

  12. Automatic Tamil lyric generation based on ontological interpretation ...

    Indian Academy of Sciences (India)

    This system proposes an -gram based approach to automatic Tamil lyric generation, by the ontological semantic interpretation of the input scene. The approach is based on identifying the semantics conveyed in the scenario, thereby making the system understand the situation and generate lyrics accordingly. The heart of ...

  13. The Reliability of Randomly Generated Math Curriculum-Based Measurements

    Science.gov (United States)

    Strait, Gerald G.; Smith, Bradley H.; Pender, Carolyn; Malone, Patrick S.; Roberts, Jarod; Hall, John D.

    2015-01-01

    "Curriculum-Based Measurement" (CBM) is a direct method of academic assessment used to screen and evaluate students' skills and monitor their responses to academic instruction and intervention. Interventioncentral.org offers a math worksheet generator at no cost that creates randomly generated "math curriculum-based measures"…

  14. Mechanically based generative laws of morphogenesis

    International Nuclear Information System (INIS)

    Beloussov, Lev V

    2008-01-01

    A deep (although at the first glance naïve) question which may be addressed to embryonic development is why during this process quite definite and accurately reproduced successions of precise and complicated shapes are taking place, or why, in several cases, the result of development is highly precise in spite of an extensive variability of intermediate stages. This problem can be attacked in two different ways. One of them, up to now just slightly employed, is to formulate robust macroscopic generative laws from which the observed successions of shapes could be derived. Another one, which dominates in modern embryology, regards the development as a succession of highly precise 'micropatterns', each of them arising due to the action of specific factors, having, as a rule, nothing in common with each other. We argue that the latter view contradicts a great bulk of firmly established data and gives no satisfactory answers to the main problems of development. Therefore we intend to follow the first way. By doing this, we regard developing embryos as self-organized systems transpierced by feedbacks among which we pay special attention to those linked with mechanical stresses (MS). We formulate a hypothesis of so-called MS hyper-restoration as a common basis for the developmentally important feedback loops. We present a number of examples confirming this hypothesis and use it for reconstructing prolonged chains of developmental events. Finally, we discuss the application of the same set of assumptions to the first steps of egg development and to the internal differentiation of embryonic cells

  15. 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

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

    International Nuclear Information System (INIS)

    Angeles C, D.E.

    1976-01-01

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

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

    International Nuclear Information System (INIS)

    Stang, L.G. Jr.

    1963-01-01

    'special' radioisotopes and tagged beads available from Brookhaven are reviewed very briefly, including recent unpublished work concerned with the successful development of an Al 28 ''generator'', the production of Sc 47 , the increase in Mg 28 specific activity to 40 mc/g, and the use of Li 6 H 2 to effect (n, particle) reactions. (author) [fr

  18. 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.

  19. Career opportunities in the applications of radiation and radioisotopes

    International Nuclear Information System (INIS)

    Morganstern, K.H.

    1975-01-01

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

  20. Amplitude-to-frequency converter of radioisotope instruments

    International Nuclear Information System (INIS)

    Demchenkov, V.P.; Korobkov, I.N.

    1988-01-01

    An amplitude-to-frequency converter designed for signal processing of radioisotope relay devices is descibed. The basic elements of the converter are a scaling amplifier, an analog-to-digital converter, a code-to-frequency converter, a null-organ, a delay unit and a clock-pulse generator. The designed amplitude-to-frequency converter takes into account a prior information about the signal shape of the energy spectrum. The converter processes input pulses of 0.10 V amplitude and duration more than 2μs. The energy channel number is 64

  1. Conceptual study on deep-underground energy generation base

    International Nuclear Information System (INIS)

    Hayano, M.; Okawa, T.

    1992-01-01

    Mitsubishi Atomic Power Industries, Inc. (MAPI) and Taisei Corporation have started a conceptual study on a deep-underground energy generation base for future cities in the 21st century around the metropolitan area, which will be increasingly important from viewpoints of the autonomy and sharing of the energy supply to the future cities. The energy generation base consists of a gas cooled reactor with naturally safety features as the energy source, an electric generation base using the Alkali Metal Thermo-electric Converter (AMTEC), a hydrogen production plant with the Solid Polymer Electrolyte (SPE), a hydrogen storage plant with the Metal Hydride (MH), and a desalination plant. This paper describes a concept of the energy generation base and the structure in the deep-underground, in soft soil, then the basic system of each plant, and finally discusses the feasibility of the deep-underground energy generation base. (author)

  2. Radioisotope detection with tandem electrostatic accelerators

    Energy Technology Data Exchange (ETDEWEB)

    Gove, H E; Elmore, D; Ferraro, R [Rochester Univ., NY (USA). Nuclear Structure Research Lab.; Beukens, R P; Chang, K H; Kilius, L R; Lee, H W; Litherland, A E [Toronto Univ., Ontario (Canada). Dept. of Physics; Purser, K H [General Ionex Corp., Newburyport, MA (USA)

    1980-01-01

    An MP tandem Van de Graaff accelerator at the University of Rochester has been employed since May 1977 to detect /sup 14/C in terrestrial samples, /sup 36/Cl in terrestrial and extraterrestrial samples and /sup 10/Be and /sup 26/Al in samples produced by reactor and accelerator irradiation. The sample sizes ranged from about 10 to less than 1 mg and the ratio of the radioisotope to the stable isotopes approached one part in 10/sup 16/ for /sup 14/C and /sup 36/Cl and one part in 10/sup 14/ for /sup 10/Be and /sup 26/Al. /sup 14/C has been measured in a number of samples of geological and archaelogical interest. /sup 36/Cl has been measured in various groundwater samples as well as samples at Antarctic meteorites and ice. Dedicated systems for /sup 14/C dating and geological measurements based on the tandem electrostatic accelerator principle are presently under construction for laboratories in the U.S.A., U.K. and Canada.

  3. Radioisotopes investigations of copper ore dressing processes

    International Nuclear Information System (INIS)

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

    1992-01-01

    This paper describes radioisotope applications in the copper industry, mainly for the examination of comminution, classification, and flotation processes for selected physical parameters. Measurements were performed by a mobile laboratory containing the electronics for experiment control and data recording and processing using special computer software. This system makes it possible to determine measurements in an industrial environment. The data acquisition system provides 24 spectrometric channels, consisting of scintillation probes, high-voltage (HV) power supplies, and pulse-height analyzers, as well as an analog-to-digital (A/D) converter interfaced to the IBM personal computer. The sampling time is fully programmable and interrupt based and can vary from 1 ms to hours and may be set separately for each channel. The milli-second sampling time technique has been applied to high-resolution flow velocity measurements. On the other hand, longer sampling time enables the system to be left unattended for days to monitor, for example, copper ore concentration or efficiency of the flotation process

  4. Loss Minimizing Operation of Doubly Fed Induction Generator Based Wind Generation Systems Considering Reactive Power Provision

    DEFF Research Database (Denmark)

    Baohua, Zhang; Hu, Weihao; Chen, Zhe

    2014-01-01

    The paper deals with control techniques for minimizing the operating loss of doubly fed induction generator based wind generation systems when providing reactive power. The proposed method achieves its goal through controlling the rotor side q-axis current in the synchronous reference frame...

  5. 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

  6. Advanced Stirling Convertor Control Unit Testing at NASA Glenn Research Center in the Radioisotope Power Systems System Integration Laboratory

    Science.gov (United States)

    Dugala, Gina M.; Taylor, Linda M.; Kussmaul, Michael; Casciani, Michael; Brown, Gregory; Wiser, Joel

    2017-01-01

    Future NASA missions could include establishing Lunar or Martian base camps, exploring Jupiters moons and travelling beyond where generating power from sunlight may be limited. Radioisotope Power Systems (RPS) provide a dependable power source for missions where inadequate sunlight or operational requirements make other power systems impractical. Over the past decade, NASA Glenn Research Center (GRC) has been supporting the development of RPSs. The Advanced Stirling Radioisotope Generator (ASRG) utilized a pair of Advanced Stirling Convertors (ASC). While flight development of the ASRG has been cancelled, much of the technology and hardware continued development and testing to guide future activities. Specifically, a controller for the convertor(s) is an integral part of a Stirling-based RPS. For the ASRG design, the controller maintains stable operation of the convertors, regulates the alternating current produced by the linear alternator of the convertor, provides a specified direct current output voltage for the spacecraft, synchronizes the piston motion of the two convertors in order to minimize vibration as well as manage and maintain operation with a stable piston amplitude and hot end temperature. It not only provides power to the spacecraft but also must regulate convertor operation to avoid damage to internal components and maintain safe thermal conditions after fueling. Lockheed Martin Coherent Technologies has designed, developed and tested an Engineering Development Unit (EDU) Advanced Stirling Convertor Control Unit (ACU) to support this effort. GRC used the ACU EDU as part of its non-nuclear representation of a RPS which also consists of a pair of Dual Advanced Stirling Convertor Simulator (DASCS), and associated support equipment to perform a test in the Radioisotope Power Systems System Integration Laboratory (RSIL). The RSIL was designed and built to evaluate hardware utilizing RPS technology. The RSIL provides insight into the electrical

  7. 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

  8. 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

  9. Diffusion of Implanted Radioisotopes in Solids

    CERN Multimedia

    2002-01-01

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

  10. 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)

  11. Aggregated wind power generation probabilistic forecasting based on particle filter

    International Nuclear Information System (INIS)

    Li, Pai; Guan, Xiaohong; Wu, Jiang

    2015-01-01

    Highlights: • A new method for probabilistic forecasting of aggregated wind power generation. • A dynamic system is established based on a numerical weather prediction model. • The new method handles the non-Gaussian and time-varying wind power uncertainties. • Particle filter is applied to forecast predictive densities of wind generation. - Abstract: Probability distribution of aggregated wind power generation in a region is one of important issues for power system daily operation. This paper presents a novel method to forecast the predictive densities of the aggregated wind power generation from several geographically distributed wind farms, considering the non-Gaussian and non-stationary characteristics in wind power uncertainties. Based on a mesoscale numerical weather prediction model, a dynamic system is established to formulate the relationship between the atmospheric and near-surface wind fields of geographically distributed wind farms. A recursively backtracking framework based on the particle filter is applied to estimate the atmospheric state with the near-surface wind power generation measurements, and to forecast the possible samples of the aggregated wind power generation. The predictive densities of the aggregated wind power generation are then estimated based on these predicted samples by a kernel density estimator. In case studies, the new method presented is tested on a 9 wind farms system in Midwestern United States. The testing results that the new method can provide competitive interval forecasts for the aggregated wind power generation with conventional statistical based models, which validates the effectiveness of the new method

  12. 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)

  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. 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. Thyroiditis: Radioisotope Scan Findings and Clinical Significance

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Chae; Han, Duck Sup; Park, Jung Suck; Kim, Se Jong; Park, Byung Lan; Kim, Byoung Geun [Kwangju Christian Hospital, Kwangju (Korea, Republic of)

    1991-07-15

    We analyzed Radioisotope scan findings of 46 patients of thyroiditis which were proven pathologically at K.C.H. The results were as follows 1) 45 patients were female, one was male and average age of patients was 37 years old. 2) The lesion site was predominant in both lobe (67%) Hashimoto's thyroiditis showed enlarged thyroid (85%) with cold nodule (20%), diffuse decreased activity (10%), while subacute thyroiditis was presented absent activity (53%), poor visualization (20%) or cold nodule (7%). 4) Radioisotope scan was valuable in evaluating function of thyroid gland and detection of lesion but there was a limit of pathological nature.

  16. 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.

  17. A microcomputer-based waveform generator for Moessbauer spectrometers

    International Nuclear Information System (INIS)

    Huang Jianping; Chen Xiaomei

    1995-01-01

    A waveform generator for Moessbauer spectrometers based on 8751 single chip microcomputer is described. The reference wave form with high linearity is generated with a 12 bit DAC, and its amplitude is controlled with a 8 bit DAC. Because the channel advance and synchronous signals can be delayed arbitrarily, excellent folded spectra can be acquired. This waveform generator can be controlled with DIP switches on faceplate or series interface of the IBM-PC microcomputer

  18. 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

  19. 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

  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

  1. A price based automatic generation control using unscheduled ...

    African Journals Online (AJOL)

    In this paper, a model for price based automatic generation control is presented. A modified control scheme is proposed which will prevent unintended unscheduled interchanges among the participants. The proposed scheme is verified by simulating it on a model of isolated area system having four generators. It has been ...

  2. Potentialities of radioisotope aniocardiography in diagnosis of acquired heart diseases

    International Nuclear Information System (INIS)

    Malov, G.A.; Mikaelyan, R.S.; Dumpe, A.N.

    1980-01-01

    On the base of the examination of 40 patients with acquired heart diseases and 5 people without heart diseases for control determined are the most charactreristic signs of the acquired heart disease of visual observation on RPP transit (albumin of human serum labelled by sup(99m)Tc) through the heart cavities and magistral vessels. It is shown that there is a close connection between central and intracardial hemodynamics which permjts to judge on the cardiac output on the base of mean circulation time (MCT). Radioisotopic angiocardiography permits to find redistribution of lung blood flow in patients with acquired heart diseases, which can serve as indirect index of long hypertension

  3. Status of NASA's Advanced Radioisotope Power Conversion Technology Research and Development

    Science.gov (United States)

    Wong, Wayne A.; Anderson, David J.; Tuttle, Karen L.; Tew, Roy C.

    2006-01-01

    NASA s Advanced Radioisotope Power Systems (RPS) development program is funding the advancement of next generation power conversion technologies that will enable future missions that have requirements that can not be met by either the ubiquitous photovoltaic systems or by current Radioisotope Power Systems (RPS). Requirements of advanced radioisotope power systems include high efficiency and high specific power (watts/kilogram) in order to meet mission requirements with less radioisotope fuel and lower mass. Other Advanced RPS development goals include long-life, reliability, and scalability so that these systems can meet requirements for a variety of future space applications including continual operation surface missions, outer-planetary missions, and solar probe. This paper provides an update on the Radioisotope Power Conversion Technology Project which awarded ten Phase I contracts for research and development of a variety of power conversion technologies consisting of Brayton, Stirling, thermoelectrics, and thermophotovoltaics. Three of the contracts continue during the current Phase II in the areas of thermoelectric and Stirling power conversion. The accomplishments to date of the contractors, project plans, and status will be summarized.

  4. 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)

  5. Development of Kabila rocket: A radioisotope heated thermionic plasma rocket engine

    Directory of Open Access Journals (Sweden)

    Kalomba Mboyi

    2015-04-01

    Full Text Available A new type of plasma rocket engine, the Kabila rocket, using a radioisotope heated thermionic heating chamber instead of a conventional combustion chamber or catalyst bed is introduced and it achieves specific impulses similar to the ones of conventional solid and bipropellant rockets. Curium-244 is chosen as a radioisotope heat source and a thermal reductive layer is also used to obtain precise thermionic emissions. The self-sufficiency principle is applied by simultaneously heating up the emitting material with the radioisotope decay heat and by powering the different valves of the plasma rocket engine with the same radioisotope decay heat using a radioisotope thermoelectric generator. This rocket engine is then benchmarked against a 1 N hydrazine thruster configuration operated on one of the Pleiades-HR-1 constellation spacecraft. A maximal specific impulse and power saving of respectively 529 s and 32% are achieved with helium as propellant. Its advantages are its power saving capability, high specific impulses and simultaneous ease of storage and restart. It can however be extremely voluminous and potentially hazardous. The Kabila rocket is found to bring great benefits to the existing spacecraft and further research should optimize its geometric characteristics and investigate the physical principals of its operation.

  6. Nanocluster metal films as thermoelectric material for radioisotope mini battery unit

    International Nuclear Information System (INIS)

    Borisyuk, P.V.; Krasavin, A.V.; Tkalya, E.V.; Lebedinskii, Yu.Yu.; Vasiliev, O.S.; Yakovlev, V.P.; Kozlova, T.I.; Fetisov, V.V.

    2016-01-01

    The paper is devoted to studying the thermoelectric and structural properties of films based on metal nanoclusters (Au, Pd, Pt). The experimental results of the study of single nanoclusters’ tunneling conductance obtained with scanning tunneling spectroscopy are presented. The obtained data allowed us to evaluate the thermoelectric power of thin film consisting of densely packed individual nanoclusters. It is shown that such thin films can operate as highly efficient thermoelectric materials. A scheme of miniature thermoelectric radioisotope power source based on the thorium-228 isotope is proposed. The efficiency of the radioisotope battery using thermoelectric converters based on nanocluster metal films is shown to reach values up to 1.3%. The estimated characteristics of the device are comparable with the parameters of up-to-date radioisotope batteries based on nickel-63.

  7. 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

  8. Pseudo-random bit generator based on Chebyshev map

    Science.gov (United States)

    Stoyanov, B. P.

    2013-10-01

    In this paper, we study a pseudo-random bit generator based on two Chebyshev polynomial maps. The novel derivative algorithm shows perfect statistical properties established by number of statistical tests.

  9. Random number generation based on digital differential chaos

    KAUST Repository

    Zidan, Mohammed A.; Radwan, Ahmed G.; Salama, Khaled N.

    2012-01-01

    In this paper, we present a fully digital differential chaos based random number generator. The output of the digital circuit is proved to be chaotic by calculating the output time series maximum Lyapunov exponent. We introduce a new post processing

  10. Stirling Radioisotope Power System as an Alternative for NASAs Deep Space Missions

    Science.gov (United States)

    Shaltens, R. K.; Mason, L. S.; Schreiber, J. G.

    2001-01-01

    The NASA Glenn Research Center (GRC) and the Department of Energy (DOE) are developing a free-piston Stirling convertor for a Stirling Radioisotope Power System (SRPS) to provide on-board electric power for future NASA deep space missions. The SRPS currently being developed provides about 100 watts and reduces the amount of radioisotope fuel by a factor of four over conventional Radioisotope Thermoelectric Generators (RTG). The present SRPS design has a specific power of approximately 4 W/kg which is comparable to an RTG. GRC estimates for advanced versions of the SRPS with improved heat source integration, lightweight Stirling convertors, composite radiators, and chip-packaged controllers improves the specific mass to about 8 W/kg. Additional information is contained in the original extended abstract.

  11. The form and interpretation of clearance curves for injected radioisotopes based on negative power laws, especially for 47Ca and estimated bone accretion rate

    International Nuclear Information System (INIS)

    Wise, M.E.

    1978-01-01

    Many hundreds of clearance curves for plasma and urine after a single injection of tracer are well fitted by y=Σsub(i=1)sup(r)Asub(i)exp(-Bsub(i)t),r=2 or 3, based on models with homogeneous compartments. Reanalyzing such sums as in a plot of log y versus log t shows that many of the original curves would fit y=Atsup(-α) or Atsup(-α)exp(-βt) over wide ranges of time and specific activity. Results of such reanalyses for a complete published series for serum albumin 131 I are given, and an outline of those for various compounds in the human body labeled by 3 H. For radiocalcium two such power laws can be fitted in one curve, with a transition between about 1 and 3 days, so that much of the log y versus log t plot consists of two straight lines. These lines are used for starting a numerical analysis that splits the curve into 2 non-linear components, plus a third one that is negligible after 5 min from injection. An outline of the iteration method is given. The components are interpreted physiologically and used to predict total bone activities by (de)convolution, and these are compared with observed ankle activities and with excretion rates. The bone accretion rate is obtained mainly from the middle component and comes to 2 to 3 g Ca/day, while return of 47 Ca from bone to plasma begins at about 1/2 day. These results seem incompatible while any based on compartments. The concept of biological half-life then needs to be reconsidered. (Auth.)

  12. 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

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    1982-09-01

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

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

    International Nuclear Information System (INIS)

    Burlison, J.S.

    1981-08-01

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

  15. COSINE software development based on code generation technology

    International Nuclear Information System (INIS)

    Ren Hao; Mo Wentao; Liu Shuo; Zhao Guang

    2013-01-01

    The code generation technology can significantly improve the quality and productivity of software development and reduce software development risk. At present, the code generator is usually based on UML model-driven technology, which can not satisfy the development demand of nuclear power calculation software. The feature of scientific computing program was analyzed and the FORTRAN code generator (FCG) based on C# was developed in this paper. FCG can generate module variable definition FORTRAN code automatically according to input metadata. FCG also can generate memory allocation interface for dynamic variables as well as data access interface. FCG was applied to the core and system integrated engine for design and analysis (COSINE) software development. The result shows that FCG can greatly improve the development efficiency of nuclear power calculation software, and reduce the defect rate of software development. (authors)

  16. Design of the Chaotic Signal Generator Based on LABVIEW

    Directory of Open Access Journals (Sweden)

    Jian-Guo Zhang

    2014-01-01

    Full Text Available We introduces a new method that can achieve the generation of Colpitts chaotic signal The system is based on virtual instrument platform and combined with MATLAB calculation to achieve the generation of Colpitts chaotic signal and making it analysis with autocorrelation and power spectrum at the same time. Signal channel output of chaotic signal was realized through USB-6009 acquisition module extending DA5405 high-speed DAC (Digital-to-Analog Converter chip. The system can adjust parameters based on customers’ requirements to achieve different frequency chaotic signal generation. Compared with the traditional autonomy Colpitts chaotic signal generator, this generator is simple and clear in structure, simple to operate, strong stability, easy to achieve etc.

  17. Method to implement the CCD timing generator based on FPGA

    Science.gov (United States)

    Li, Binhua; Song, Qian; He, Chun; Jin, Jianhui; He, Lin

    2010-07-01

    With the advance of the PFPA technology, the design methodology of digital systems is changing. In recent years we develop a method to implement the CCD timing generator based on FPGA and VHDL. This paper presents the principles and implementation skills of the method. Taking a developed camera as an example, we introduce the structure, input and output clocks/signals of a timing generator implemented in the camera. The generator is composed of a top module and a bottom module. The bottom one is made up of 4 sub-modules which correspond to 4 different operation modes. The modules are implemented by 5 VHDL programs. Frame charts of the architecture of these programs are shown in the paper. We also describe implementation steps of the timing generator in Quartus II, and the interconnections between the generator and a Nios soft core processor which is the controller of this generator. Some test results are presented in the end.

  18. The industrial application of radioisotopes in Australia

    International Nuclear Information System (INIS)

    Easey, J.F.

    1987-01-01

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

  19. How to find out in radioisotope methodology

    International Nuclear Information System (INIS)

    Evers, C.

    1976-01-01

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

  20. 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

  1. 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.

  2. Radioisotopes - their applications in industrial radiography

    International Nuclear Information System (INIS)

    Rao, H.R.S.

    1977-01-01

    The nature of radioisotopes and their industrial applications with special reference to industrial radiography are outlined. The various aspects of industrial radiography such as source size, source containers, films, density of radiography, radiographic quality and applications are discussed in brief. (M.G.B.)

  3. Radioisotopes and food preservation against insects

    International Nuclear Information System (INIS)

    Hachem Ahmad, M.S.

    1998-01-01

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

  4. Radioisotope techniques used in breast cancer

    International Nuclear Information System (INIS)

    Au-Yong Ting Kun

    2001-01-01

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

  5. Radioisotope licence application: Fixed nuclear gauges

    International Nuclear Information System (INIS)

    1995-09-01

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

  6. Application of artificial radioisotopes in hydrological studies

    International Nuclear Information System (INIS)

    Jacob, Noble; Shivanna, K.

    2009-01-01

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

  7. The control of radioisotopes in Canada

    International Nuclear Information System (INIS)

    Hamel, P.E.

    1980-01-01

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

  8. Radiological characterization of liquid effluent hold up tank for generating data base for future decommissioning

    International Nuclear Information System (INIS)

    Sapkal, Jyotsna A.; Singh, Pratap; Verma, Amit; Yadav, R.K.B.; Thakare, S.V.

    2018-01-01

    Operations at Radiological laboratory facilities are involved in fabrication of high activity radioactive sources like 60 Co, 192 1r and 137 Cs, handling of long lived radionuclides like 137 Cs/ 90 Sr, radiochemical processing and production of short-lived radioisotopes for medical diagnosis and treatment of patients. Typical liquid waste management feature at any Radiological Laboratory facility primarily consists of effluent tanks which store the liquid effluent wastes generated during radiochemical processing and fabrication of reactor produced radioisotopes. The liquid waste generated from various laboratories are collected to low level sump tanks from where it is transferred to hold up tanks. The liquid waste is transferred to centralized effluent treatment plant, analysis and characterization of the same is carried out. This paper explains the characterization study of samples drawn from the liquid effluent tank which would be helpful for planning for decontamination as well as for decommissioning and in management of radioactive wastes. In this study the crud deposited at the bottom of tank was collected for gamma spectrometry analysis. Radiation field was measured, at the bottom of the tank for correlating the activity present and the radiation field

  9. 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

  10. 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

  11. 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

  12. 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.

  13. International codes concerning the security of radioisotopes

    International Nuclear Information System (INIS)

    Kusama, Keiji

    2013-01-01

    Explained is the title subject with international and Japanese official argument or publications and actions, where the security is defined as protection of sealed and unsealed radioisotopes (RI) from malicious acts. IAEA worked out the Code of Conduct on the Safety and Security of Radioactive Sources in 2004 based on its preceding argument and with the turning point of the terrorism 3.11 (2001), and Nuclear Security Recommendations on radioactive material and associated facilities (2011), for whose prerequisite, Security of radioactive sources: implementing guide (2009) and Security in the transport of radioactive material (2008) had been drawn up. The Code of Conduct indicates the security system to regulate the sealed sources that each nation has to build up through legislation, setup of regulatory agency, registration of the sources, provision of concerned facilities with radiation protection, etc. For attaining this purpose, IAEA defined Guidance on the Import and Export of Radioactive Sources (2005, 2012), Categorization of radioactive sources (2005) and Dangerous quantities of radioactive material (D-VALUES) (2006). For updating the related matters, IAEA holds international conferences somewhere in the world every year. The Nuclear Security Recommendations indicate the nation's responsibility of building up and maintaining the security system above with well-balanced measures between the safe and secure use of RI without the invalid inhibition of their usage. Japan government worked out the concept essential for ensuring the nuclear security in Sep. 2011, in which for RI, defined were the risk and benefit in use and security, and securing role of the present legal systems concerning the safety handling and objective RI involved in their registration system. Securing measures of RI in such usage as medical and industrial aids must be of advanced usefulness and safety in harmony with activities of other countries. (T.T)

  14. 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

  15. Synchronous Generator Model Parameter Estimation Based on Noisy Dynamic Waveforms

    Science.gov (United States)

    Berhausen, Sebastian; Paszek, Stefan

    2016-01-01

    In recent years, there have occurred system failures in many power systems all over the world. They have resulted in a lack of power supply to a large number of recipients. To minimize the risk of occurrence of power failures, it is necessary to perform multivariate investigations, including simulations, of power system operating conditions. To conduct reliable simulations, the current base of parameters of the models of generating units, containing the models of synchronous generators, is necessary. In the paper, there is presented a method for parameter estimation of a synchronous generator nonlinear model based on the analysis of selected transient waveforms caused by introducing a disturbance (in the form of a pseudorandom signal) in the generator voltage regulation channel. The parameter estimation was performed by minimizing the objective function defined as a mean square error for deviations between the measurement waveforms and the waveforms calculated based on the generator mathematical model. A hybrid algorithm was used for the minimization of the objective function. In the paper, there is described a filter system used for filtering the noisy measurement waveforms. The calculation results of the model of a 44 kW synchronous generator installed on a laboratory stand of the Institute of Electrical Engineering and Computer Science of the Silesian University of Technology are also given. The presented estimation method can be successfully applied to parameter estimation of different models of high-power synchronous generators operating in a power system.

  16. Methods and means of the radioisotope flaw detection of the nuclear power reactors components

    International Nuclear Information System (INIS)

    Dekopov, A.S.; Majorov, A.N.; Firsov, V.G.

    1979-01-01

    Methods and means are considered for the radioisotopic flaw detection of the nuclear reactors pressure vessels and structural components of the reactor circuit. Methods of control are described as in the technological process of fabrication of the power reactors assemblies as during the systematic-preventive repair of the nuclear power station equipment during exploitation. Methodological base is given of the technology of radiation control of welded joints of the pressure vessel branch piper of the WWER-440 and WWER-1000 reactors in the process of assembling and exploitation and joining pipes with the pipe-plate of the steamgenerator in the process of fabrication. Methods of the radioisotope flaw detection in the process of exploitation take into consideration the influence of the radioisotope background, and ensure obtaining of the demanded by the rules of control, sensitivity. Methods of control of welded joints of the steamgenerator of nuclear power plants are based on the simultaneous examination of all joints with application of the shaped radiographic plate-holders. Special gamma-flaw-detection equipment is developed for control of the welded joints of the main branch-pipes. Design peculiarities are given of the installation for flaw detection. These installations are equipped with the system for emergency return of the radiation source into the storage position from the position for exposure. They have automatic exposure-meters for determination of the exposure time. Successfull exploitation of such installations in the Finland during assembling equipment for the nuclear reactor of the nuclear power plant ''Loviisa-1'' and in the USSR on the Novovoronezh nuclear power plant has shown possibility for detection of flaws having dimensions about 1% of the equipment used. For control of welded joints of pipes with pipe-plates at the steam generators, portable flaw-detectors are used. Sensitivity of these flaw-detectors towards detection of the wire standards has

  17. A method for performance assessment of medical radioisotope equipment

    International Nuclear Information System (INIS)

    Kerin, T.; Slavtchev, Ath.; Nedeltchev, M.; Kjurktchiev, T.

    1984-01-01

    A variety of tests and procedures exist for the performance assessment of radioisotope diagnostic equipment. The complex performance index which has been introduced to date is based on an heuristic approach. The present work tries to interconnect algorithmically the most important factors as the influence of the measurement geometry, the statistic peculiarities for lower activities and the information loss at high count rates. All this is reflected in a criterion which integrates the spatial resolution, the effective detector's field of vision, the radionuclide's sensitivity, the background count rate and the effective dead-time of the system under investigation. (Auth.)

  18. BEAT: A Web-Based Boolean Expression Fault-Based Test Case Generation Tool

    Science.gov (United States)

    Chen, T. Y.; Grant, D. D.; Lau, M. F.; Ng, S. P.; Vasa, V. R.

    2006-01-01

    BEAT is a Web-based system that generates fault-based test cases from Boolean expressions. It is based on the integration of our several fault-based test case selection strategies. The generated test cases are considered to be fault-based, because they are aiming at the detection of particular faults. For example, when the Boolean expression is in…

  19. Novel Radioisotope Applications in Industry Promoted by the IAEA

    International Nuclear Information System (INIS)

    Thereska, J.

    2001-01-01

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

  20. Hydrogen-based power generation from bioethanol steam reforming

    Energy Technology Data Exchange (ETDEWEB)

    Tasnadi-Asztalos, Zs., E-mail: tazsolt@chem.ubbcluj.ro; Cormos, C. C., E-mail: cormos@chem.ubbcluj.ro; Agachi, P. S. [Babes-Bolyai University, Faculty of Chemistry and Chemical Engineering, 11 Arany Janos, Postal code: 400028, Cluj-Napoca (Romania)

    2015-12-23

    This paper is evaluating two power generation concepts based on hydrogen produced from bioethanol steam reforming at industrial scale without and with carbon capture. The power generation from bioethanol conversion is based on two important steps: hydrogen production from bioethanol catalytic steam reforming and electricity generation using a hydrogen-fuelled gas turbine. As carbon capture method to be assessed in hydrogen-based power generation from bioethanol steam reforming, the gas-liquid absorption using methyl-di-ethanol-amine (MDEA) was used. Bioethanol is a renewable energy carrier mainly produced from biomass fermentation. Steam reforming of bioethanol (SRE) provides a promising method for hydrogen and power production from renewable resources. SRE is performed at high temperatures (e.g. 800-900°C) to reduce the reforming by-products (e.g. ethane, ethene). The power generation from hydrogen was done with M701G2 gas turbine (334 MW net power output). Hydrogen was obtained through catalytic steam reforming of bioethanol without and with carbon capture. For the evaluated plant concepts the following key performance indicators were assessed: fuel consumption, gross and net power outputs, net electrical efficiency, ancillary consumptions, carbon capture rate, specific CO{sub 2} emission etc. As the results show, the power generation based on bioethanol conversion has high energy efficiency and low carbon footprint.

  1. Hydrogen-based power generation from bioethanol steam reforming

    International Nuclear Information System (INIS)

    Tasnadi-Asztalos, Zs.; Cormos, C. C.; Agachi, P. S.

    2015-01-01

    This paper is evaluating two power generation concepts based on hydrogen produced from bioethanol steam reforming at industrial scale without and with carbon capture. The power generation from bioethanol conversion is based on two important steps: hydrogen production from bioethanol catalytic steam reforming and electricity generation using a hydrogen-fuelled gas turbine. As carbon capture method to be assessed in hydrogen-based power generation from bioethanol steam reforming, the gas-liquid absorption using methyl-di-ethanol-amine (MDEA) was used. Bioethanol is a renewable energy carrier mainly produced from biomass fermentation. Steam reforming of bioethanol (SRE) provides a promising method for hydrogen and power production from renewable resources. SRE is performed at high temperatures (e.g. 800-900°C) to reduce the reforming by-products (e.g. ethane, ethene). The power generation from hydrogen was done with M701G2 gas turbine (334 MW net power output). Hydrogen was obtained through catalytic steam reforming of bioethanol without and with carbon capture. For the evaluated plant concepts the following key performance indicators were assessed: fuel consumption, gross and net power outputs, net electrical efficiency, ancillary consumptions, carbon capture rate, specific CO 2 emission etc. As the results show, the power generation based on bioethanol conversion has high energy efficiency and low carbon footprint

  2. Hydrogen-based power generation from bioethanol steam reforming

    Science.gov (United States)

    Tasnadi-Asztalos, Zs.; Cormos, C. C.; Agachi, P. S.

    2015-12-01

    This paper is evaluating two power generation concepts based on hydrogen produced from bioethanol steam reforming at industrial scale without and with carbon capture. The power generation from bioethanol conversion is based on two important steps: hydrogen production from bioethanol catalytic steam reforming and electricity generation using a hydrogen-fuelled gas turbine. As carbon capture method to be assessed in hydrogen-based power generation from bioethanol steam reforming, the gas-liquid absorption using methyl-di-ethanol-amine (MDEA) was used. Bioethanol is a renewable energy carrier mainly produced from biomass fermentation. Steam reforming of bioethanol (SRE) provides a promising method for hydrogen and power production from renewable resources. SRE is performed at high temperatures (e.g. 800-900°C) to reduce the reforming by-products (e.g. ethane, ethene). The power generation from hydrogen was done with M701G2 gas turbine (334 MW net power output). Hydrogen was obtained through catalytic steam reforming of bioethanol without and with carbon capture. For the evaluated plant concepts the following key performance indicators were assessed: fuel consumption, gross and net power outputs, net electrical efficiency, ancillary consumptions, carbon capture rate, specific CO2 emission etc. As the results show, the power generation based on bioethanol conversion has high energy efficiency and low carbon footprint.

  3. Assess and Predict Automatic Generation Control Performances for Thermal Power Generation Units Based on Modeling Techniques

    Science.gov (United States)

    Zhao, Yan; Yang, Zijiang; Gao, Song; Liu, Jinbiao

    2018-02-01

    Automatic generation control(AGC) is a key technology to maintain real time power generation and load balance, and to ensure the quality of power supply. Power grids require each power generation unit to have a satisfactory AGC performance, being specified in two detailed rules. The two rules provide a set of indices to measure the AGC performance of power generation unit. However, the commonly-used method to calculate these indices is based on particular data samples from AGC responses and will lead to incorrect results in practice. This paper proposes a new method to estimate the AGC performance indices via system identification techniques. In addition, a nonlinear regression model between performance indices and load command is built in order to predict the AGC performance indices. The effectiveness of the proposed method is validated through industrial case studies.

  4. Chaos-based Pseudo-random Number Generation

    KAUST Repository

    Barakat, Mohamed L.

    2014-04-10

    Various methods and systems related to chaos-based pseudo-random number generation are presented. In one example, among others, a system includes a pseudo-random number generator (PRNG) to generate a series of digital outputs and a nonlinear post processing circuit to perform an exclusive OR (XOR) operation on a first portion of a current digital output of the PRNG and a permutated version of a corresponding first portion of a previous post processed output to generate a corresponding first portion of a current post processed output. In another example, a method includes receiving at least a first portion of a current output from a PRNG and performing an XOR operation on the first portion of the current PRNG output with a permutated version of a corresponding first portion of a previous post processed output to generate a corresponding first portion of a current post processed output.

  5. The guitar chord-generating algorithm based on complex network

    Science.gov (United States)

    Ren, Tao; Wang, Yi-fan; Du, Dan; Liu, Miao-miao; Siddiqi, Awais

    2016-02-01

    This paper aims to generate chords for popular songs automatically based on complex network. Firstly, according to the characteristics of guitar tablature, six chord networks of popular songs by six pop singers are constructed and the properties of all networks are concluded. By analyzing the diverse chord networks, the accompaniment regulations and features are shown, with which the chords can be generated automatically. Secondly, in terms of the characteristics of popular songs, a two-tiered network containing a verse network and a chorus network is constructed. With this network, the verse and chorus can be composed respectively with the random walk algorithm. Thirdly, the musical motif is considered for generating chords, with which the bad chord progressions can be revised. This method can make the accompaniments sound more melodious. Finally, a popular song is chosen for generating chords and the new generated accompaniment sounds better than those done by the composers.

  6. A Prediction-based Smart Meter Data Generator

    DEFF Research Database (Denmark)

    Iftikhar, Nadeem; Liu, Xiufeng; Nordbjerg, Finn Ebertsen

    2016-01-01

    With the prevalence of cloud computing and In-ternet of Things (IoT), smart meters have become one of the main components of smart city strategy. Smart meters generate large amounts of fine-grained data that is used to provide useful information to consumers and utility companies for decision......, mainly due to privacy issues. This paper proposes a smart meter data generator that can generate realistic energy consumption data by making use of a small real-world dataset as seed. The generator generates data using a prediction-based method that depends on historical energy consumption patterns along......-making. Now-a-days, smart meter analytics systems consist of analytical algorithms that process massive amounts of data. These analytics algorithms require ample amounts of realistic data for testing and verification purposes. However, it is usually difficult to obtain adequate amounts of realistic data...

  7. Chaos-based Pseudo-random Number Generation

    KAUST Repository

    Barakat, Mohamed L.; Mansingka, Abhinav S.; Radwan, Ahmed Gomaa Ahmed; Salama, Khaled N.

    2014-01-01

    Various methods and systems related to chaos-based pseudo-random number generation are presented. In one example, among others, a system includes a pseudo-random number generator (PRNG) to generate a series of digital outputs and a nonlinear post processing circuit to perform an exclusive OR (XOR) operation on a first portion of a current digital output of the PRNG and a permutated version of a corresponding first portion of a previous post processed output to generate a corresponding first portion of a current post processed output. In another example, a method includes receiving at least a first portion of a current output from a PRNG and performing an XOR operation on the first portion of the current PRNG output with a permutated version of a corresponding first portion of a previous post processed output to generate a corresponding first portion of a current post processed output.

  8. Advanced Stirling Convertor Dual Convertor Controller Testing at NASA Glenn Research Center in the Radioisotope Power Systems System Integration Laboratory

    Science.gov (United States)

    Dugala, Gina M.; Taylor, Linda M.; Bell, Mark E.; Dolce, James L.; Fraeman, Martin; Frankford, David P.

    2015-01-01

    NASA Glenn Research Center developed a nonnuclear representation of a Radioisotope Power System (RPS) consisting of a pair of Advanced Stirling Convertors (ASCs), Dual Convertor Controller (DCC) EMs (engineering models) 2 and 3, and associated support equipment, which were tested in the Radioisotope Power Systems System Integration Laboratory (RSIL). The DCC was designed by the Johns Hopkins University Applied Physics Laboratory (JHU/APL) to actively control a pair of ASCs. The first phase of testing included a Dual Advanced Stirling Convertor Simulator (DASCS), which was developed by JHU/APL and simulates the operation and electrical behavior of a pair of ASCs in real time via a combination of hardware and software. RSIL provides insight into the electrical interactions between a representative radioisotope power generator, its associated control schemes, and realistic electric system loads. The first phase of integration testing included the following spacecraft bus configurations: capacitive, battery, and super-capacitor. A load profile, created based on data from several missions, tested the RPS's and RSIL's ability to maintain operation during load demands above and below the power provided by the RPS. The integration testing also confirmed the DCC's ability to disconnect from the spacecraft when the bus voltage dipped below 22 volts or exceeded 36 volts. Once operation was verified with the DASCS, the tests were repeated with actual operating ASCs. The goal of this integration testing was to verify operation of the DCC when connected to a spacecraft and to verify the functionality of the newly designed RSIL. The results of these tests are presented in this paper.

  9. Dynamic Frames Based Generation of 3D Scenes and Applications

    Directory of Open Access Journals (Sweden)

    Danijel Radošević

    2015-05-01

    Full Text Available Modern graphic/programming tools like Unity enables the possibility of creating 3D scenes as well as making 3D scene based program applications, including full physical model, motion, sounds, lightning effects etc. This paper deals with the usage of dynamic frames based generator in the automatic generation of 3D scene and related source code. The suggested model enables the possibility to specify features of the 3D scene in a form of textual specification, as well as exporting such features from a 3D tool. This approach enables higher level of code generation flexibility and the reusability of the main code and scene artifacts in a form of textual templates. An example of the generated application is presented and discussed.

  10. Sodium Variable Conductance Heat Pipe for Radioisotope Stirling Systems

    Science.gov (United States)

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

    2009-01-01

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

  11. Radioisotope power sources in the terrestrial and marine environment

    International Nuclear Information System (INIS)

    Holleman, T.J.; Wahlquist, E.J.

    1976-01-01

    In response to user agency needs, the Energy Research and Development Administration (ERDA), Division of Nuclear Research and Applications (NRA), has undertaken a variety of research and development efforts to insure the availability of highly reliable, long-lived nuclear power sources for special purpose terrestrial missions planned for the late 1970's and early 1980's. One such effort currently being pursued is the development of a 1kW(e) Stirling Radioisotope Power System for integration into an Unmanned Free Swimming Submersible (UFSS) demonstration vehicle now under development by the Naval Research Laboratory. Another important effort which NRA has undertaken is a study to evaluate both isotope fueled and non-isotope fueled unattended power systems in the 2kW(e) range for application in cold regions. In the lower power ranges of Radioisotope Thermoelectric Generators, NRA continues to support new development efforts and new application areas. The Division is providing assistance to the Navy on a 1 / 2 W(e) RTG for use in various underwater applications. The various efforts are briefly discussed

  12. THz generation from a nanocrystalline silicon-based photoconductive device

    International Nuclear Information System (INIS)

    Daghestani, N S; Persheyev, S; Cataluna, M A; Rose, M J; Ross, G

    2011-01-01

    Terahertz generation has been achieved from a photoconductive switch based on hydrogenated nanocrystalline silicon (nc-Si:H), gated by a femtosecond laser. The nc-Si:H samples were produced by a hot wire chemical vapour deposition process, a process with low production costs owing to its higher growth rate and manufacturing simplicity. Although promising ultrafast carrier dynamics of nc-Si have been previously demonstrated, this is the first report on THz generation from a nc-Si:H material

  13. Novel power saving architecture for FBG based OCDMA code generation

    Science.gov (United States)

    Osadola, Tolulope B.; Idris, Siti K.; Glesk, Ivan

    2013-10-01

    A novel architecture for generating incoherent, 2-dimensional wavelength hopping-time spreading optical CDMA codes is presented. The architecture is designed to facilitate the reuse of optical source signal that is unused after an OCDMA code has been generated using fiber Bragg grating based encoders. Effective utilization of available optical power is therefore achieved by cascading several OCDMA encoders thereby enabling 3dB savings in optical power.

  14. Encouraging the next generation into land-based industries.

    Science.gov (United States)

    Rowarth, Js

    2008-12-01

    Members of the Y-Generation (born between approximately 1978 and 1994) have expectations of careers, rewards and 'work-life balance' that are very different from those of previous generations. This paper discusses these differences, how the land-based industries can position in order to offer 'the career path of choice', and how doing so will be of benefit not only to employers but also to New Zealand.

  15. Random number generation based on digital differential chaos

    KAUST Repository

    Zidan, Mohammed A.

    2012-07-29

    In this paper, we present a fully digital differential chaos based random number generator. The output of the digital circuit is proved to be chaotic by calculating the output time series maximum Lyapunov exponent. We introduce a new post processing technique to improve the distribution and statistical properties of the generated data. The post-processed output passes the NIST Sp. 800-22 statistical tests. The system is written in Verilog VHDL and realized on Xilinx Virtex® FPGA. The generator can fit into a very small area and have a maximum throughput of 2.1 Gb/s.

  16. MEMS-Based Power Generation Techniques for Implantable Biosensing Applications

    Directory of Open Access Journals (Sweden)

    Jonathan Lueke

    2011-01-01

    Full Text Available Implantable biosensing is attractive for both medical monitoring and diagnostic applications. It is possible to monitor phenomena such as physical loads on joints or implants, vital signs, or osseointegration in vivo and in real time. Microelectromechanical (MEMS-based generation techniques can allow for the autonomous operation of implantable biosensors by generating electrical power to replace or supplement existing battery-based power systems. By supplementing existing battery-based power systems for implantable biosensors, the operational lifetime of the sensor is increased. In addition, the potential for a greater amount of available power allows additional components to be added to the biosensing module, such as computational and wireless and components, improving functionality and performance of the biosensor. Photovoltaic, thermovoltaic, micro fuel cell, electrostatic, electromagnetic, and piezoelectric based generation schemes are evaluated in this paper for applicability for implantable biosensing. MEMS-based generation techniques that harvest ambient energy, such as vibration, are much better suited for implantable biosensing applications than fuel-based approaches, producing up to milliwatts of electrical power. High power density MEMS-based approaches, such as piezoelectric and electromagnetic schemes, allow for supplemental and replacement power schemes for biosensing applications to improve device capabilities and performance. In addition, this may allow for the biosensor to be further miniaturized, reducing the need for relatively large batteries with respect to device size. This would cause the implanted biosensor to be less invasive, increasing the quality of care received by the patient.

  17. MEMS-based power generation techniques for implantable biosensing applications.

    Science.gov (United States)

    Lueke, Jonathan; Moussa, Walied A

    2011-01-01

    Implantable biosensing is attractive for both medical monitoring and diagnostic applications. It is possible to monitor phenomena such as physical loads on joints or implants, vital signs, or osseointegration in vivo and in real time. Microelectromechanical (MEMS)-based generation techniques can allow for the autonomous operation of implantable biosensors by generating electrical power to replace or supplement existing battery-based power systems. By supplementing existing battery-based power systems for implantable biosensors, the operational lifetime of the sensor is increased. In addition, the potential for a greater amount of available power allows additional components to be added to the biosensing module, such as computational and wireless and components, improving functionality and performance of the biosensor. Photovoltaic, thermovoltaic, micro fuel cell, electrostatic, electromagnetic, and piezoelectric based generation schemes are evaluated in this paper for applicability for implantable biosensing. MEMS-based generation techniques that harvest ambient energy, such as vibration, are much better suited for implantable biosensing applications than fuel-based approaches, producing up to milliwatts of electrical power. High power density MEMS-based approaches, such as piezoelectric and electromagnetic schemes, allow for supplemental and replacement power schemes for biosensing applications to improve device capabilities and performance. In addition, this may allow for the biosensor to be further miniaturized, reducing the need for relatively large batteries with respect to device size. This would cause the implanted biosensor to be less invasive, increasing the quality of care received by the patient.

  18. 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.

  19. 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

  20. Optimal Output of Distributed Generation Based On Complex Power Increment

    Science.gov (United States)

    Wu, D.; Bao, H.

    2017-12-01

    In order to meet the growing demand for electricity and improve the cleanliness of power generation, new energy generation, represented by wind power generation, photovoltaic power generation, etc has been widely used. The new energy power generation access to distribution network in the form of distributed generation, consumed by local load. However, with the increase of the scale of distribution generation access to the network, the optimization of its power output is becoming more and more prominent, which needs further study. Classical optimization methods often use extended sensitivity method to obtain the relationship between different power generators, but ignore the coupling parameter between nodes makes the results are not accurate; heuristic algorithm also has defects such as slow calculation speed, uncertain outcomes. This article proposes a method called complex power increment, the essence of this method is the analysis of the power grid under steady power flow. After analyzing the results we can obtain the complex scaling function equation between the power supplies, the coefficient of the equation is based on the impedance parameter of the network, so the description of the relation of variables to the coefficients is more precise Thus, the method can accurately describe the power increment relationship, and can obtain the power optimization scheme more accurately and quickly than the extended sensitivity method and heuristic method.

  1. Osmosis-Based Pressure Generation: Dynamics and Application

    Science.gov (United States)

    Li, Suyi; Billeh, Yazan N.; Wang, K. W.; Mayer, Michael

    2014-01-01

    This paper describes osmotically-driven pressure generation in a membrane-bound compartment while taking into account volume expansion, solute dilution, surface area to volume ratio, membrane hydraulic permeability, and changes in osmotic gradient, bulk modulus, and degree of membrane fouling. The emphasis lies on the dynamics of pressure generation; these dynamics have not previously been described in detail. Experimental results are compared to and supported by numerical simulations, which we make accessible as an open source tool. This approach reveals unintuitive results about the quantitative dependence of the speed of pressure generation on the relevant and interdependent parameters that will be encountered in most osmotically-driven pressure generators. For instance, restricting the volume expansion of a compartment allows it to generate its first 5 kPa of pressure seven times faster than without a restraint. In addition, this dynamics study shows that plants are near-ideal osmotic pressure generators, as they are composed of many small compartments with large surface area to volume ratios and strong cell wall reinforcements. Finally, we demonstrate two applications of an osmosis-based pressure generator: actuation of a soft robot and continuous volume delivery over long periods of time. Both applications do not need an external power source but rather take advantage of the energy released upon watering the pressure generators. PMID:24614529

  2. Osmosis-based pressure generation: dynamics and application.

    Science.gov (United States)

    Bruhn, Brandon R; Schroeder, Thomas B H; Li, Suyi; Billeh, Yazan N; Wang, K W; Mayer, Michael

    2014-01-01

    This paper describes osmotically-driven pressure generation in a membrane-bound compartment while taking into account volume expansion, solute dilution, surface area to volume ratio, membrane hydraulic permeability, and changes in osmotic gradient, bulk modulus, and degree of membrane fouling. The emphasis lies on the dynamics of pressure generation; these dynamics have not previously been described in detail. Experimental results are compared to and supported by numerical simulations, which we make accessible as an open source tool. This approach reveals unintuitive results about the quantitative dependence of the speed of pressure generation on the relevant and interdependent parameters that will be encountered in most osmotically-driven pressure generators. For instance, restricting the volume expansion of a compartment allows it to generate its first 5 kPa of pressure seven times faster than without a restraint. In addition, this dynamics study shows that plants are near-ideal osmotic pressure generators, as they are composed of many small compartments with large surface area to volume ratios and strong cell wall reinforcements. Finally, we demonstrate two applications of an osmosis-based pressure generator: actuation of a soft robot and continuous volume delivery over long periods of time. Both applications do not need an external power source but rather take advantage of the energy released upon watering the pressure generators.

  3. Osmosis-based pressure generation: dynamics and application.

    Directory of Open Access Journals (Sweden)

    Brandon R Bruhn

    Full Text Available This paper describes osmotically-driven pressure generation in a membrane-bound compartment while taking into account volume expansion, solute dilution, surface area to volume ratio, membrane hydraulic permeability, and changes in osmotic gradient, bulk modulus, and degree of membrane fouling. The emphasis lies on the dynamics of pressure generation; these dynamics have not previously been described in detail. Experimental results are compared to and supported by numerical simulations, which we make accessible as an open source tool. This approach reveals unintuitive results about the quantitative dependence of the speed of pressure generation on the relevant and interdependent parameters that will be encountered in most osmotically-driven pressure generators. For instance, restricting the volume expansion of a compartment allows it to generate its first 5 kPa of pressure seven times faster than without a restraint. In addition, this dynamics study shows that plants are near-ideal osmotic pressure generators, as they are composed of many small compartments with large surface area to volume ratios and strong cell wall reinforcements. Finally, we demonstrate two applications of an osmosis-based pressure generator: actuation of a soft robot and continuous volume delivery over long periods of time. Both applications do not need an external power source but rather take advantage of the energy released upon watering the pressure generators.

  4. '99Mo/99mTc Generator Based on High Radionuclidic Pure Zirconium Molybdate Gel

    International Nuclear Information System (INIS)

    Amin, M.; Mostafa, M.; El-Amir, M.A.; El-Absy, M.A.; Mohamed, O.I.; Farag, A.B.

    2014-01-01

    99 Mo / 99 mTc radioisotope generator was prepared using in-situ precipitated zirconium molybdate chromatographic column. Zirconium molybdate gel matrix was synthesized by precipitation of neutron activation molybdenum-99 from its solution after variety purification processes to prevent contamination of the 99m Tc eluate with cross-contaminants. Greeter than 82.7 ± 0.4 % of the generated 99m Tc was immediately and reproducible eluted by passing 10 ml 0.9 % NaCl solution through the 1 g zirconium molybdate- 99 Mo column matrix at a flow rate of 0.5 ml / min and room temperature with high chemical, radionuclide ( ≥ 99.9 % 99m Tc) and radiochemical purity ( ≥ 97.7 % % as 99 mTcO 4 - ) with ph value suitable for medical uses.

  5. SE-72/AS-72 generator system based on Se extraction/ As reextraction

    Science.gov (United States)

    Fassbender, Michael Ernst; Ballard, Beau D

    2013-09-10

    The preparation of a .sup.72Se/.sup.72As radioisotope generator involves forming an acidic aqueous solution of an irradiated alkali bromide target such as a NaBr target, oxidizing soluble bromide in the solution to elemental bromine, removing the elemental bromine, evaporating the resulting solution to a residue, removing hydrogen chloride from the residue, forming an acidic aqueous solution of the residue, adding a chelator that selectively forms a chelation complex with selenium, and extracting the chelation complex from the acidic aqueous solution into an organic phase. As the .sup.72Se generates .sup.72As in the organic phase, the .sup.72As may be extracted repeatedly from the organic phase with an aqueous acid solution.

  6. A Survey on the Usage and Demand of Medical Radioisotope and Radiopharmaceuticals in Malaysia

    International Nuclear Information System (INIS)

    Muhammad Fakhrurazi Ahmad Fadzil; Siti Selina Abdul Hamid; Siti Najila Mohd Janib; Azahari Kasbollah; Syed Asraf Fahlawi Wafa

    2015-01-01

    Medical radioisotope is a small quantity of radioactive substance used in safe, cost effective, for the purpose of diagnostic and therapy of various diseases. In Malaysia, the emerging of new nuclear medicine centers or institutions in both government and private sectors rose abruptly for the past few years. Currently, there are no data available on the usage and demand of medical radioisotope or radiopharmaceuticals. Understanding the usage trending and demand of radiopharmaceuticals and medical radioisotope is essential when related to technology changes in order to meet the market size of these radiopharmaceuticals. Survey result found out that the highest demand and the highest usage among all radioisotopes are Technetium-99m and Radioiodine isotopes such as the Iodine-1331, Iodine131 MIBG, Iodine-123 and Iodine-123 MIBG. Currently, most of the medical isotopes and radiopharmaceuticals are currently imported. Technetium-99m is the backbone of nuclear medicine whereby more than 80 % of Nuclear Medicine services utilize this radioisotope. Technetium-99m supply chain is unstable globally and in coming future, two main reactors (Canada and Holland) that produces 60 % of world Molybdenum-99 will shut down the operation and supply of Molybdenum-99 will be disrupted. As for radioiodine services, currently, Iodine-123 can't be obtained in Malaysia and neighboring countries due to its short half-life, Iodine-123 is useful in diagnostic of thyroid related diseases. As for PET services, the highest demands are F-18 FDG and Gallium-68 Generator for the moment. However the survey data still did not include most of the PET centers in the Klang Valley, northern area (Penang) and the new upcoming PET center in Southern Region (Malacca and Johor). It is important for Malaysia to self-produced medical radioisotope and radiopharmaceuticals to meet the market and local demand of these medical isotopes. (author)

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

    International Nuclear Information System (INIS)

    1971-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Tsechanski, A. [Ben-Gurion University of the Negev, Department of Nuclear Engineering, P.O. Box 653, Beer-Sheva 84105 (Israel); Bielajew, A.F. [Department of Nuclear Engineering and Radiological Sciences, The University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109 (United States); Archambault, J.P.; Mainegra-Hing, E. [National Research Council of Canada, Ionizing Radiation Standards Laboratory, Ottawa, ON K1A 0R6 (Canada)

    2016-01-01

    A new “one-stage” approach for production of {sup 99}Mo and other radioisotopes by means of an electron linear accelerator is described. It is based on using a molybdenum target both as a bremsstrahlung converter and as a radioisotope producing target for the production of {sup 99}Mo via the photoneutron reaction {sup 100}Mo(γ,n){sup 99}Mo. Bremsstrahlung characteristics, such as bremsstrahlung efficiency, angular distribution, and energy deposition for molybdenum targets were obtained by means of the EGSnrc Monte Carlo simulation code system. As a result of our simulations, it is concluded that a 60 MeV electron beam incident on a thick Mo target will have greater bremsstrahlung efficiency than the same thickness (in units of r{sub 0}) W target, for target thickness z > 1.84r{sub 0}, where r{sub 0} is the electron range. A 50 MeV electron beam incident on a Mo target will result in greater bremsstrahlung efficiency than the same thickness W target (in units of r{sub 0}) for target thickness case: z ⩾ 2.0r{sub 0}. It is shown for the one-stage approach with thicknesses of (1.84–2.0)r{sub 0}, that the {sup 99}Mo-production bremsstrahlung efficiency of a molybdenum target is greater by ∼100% at 30 MeV and by ∼70% at 60 MeV compared to the values for tungsten of the same thickness (in units of the appropriate r{sub 0}) in the traditional two-stage approach (W converter and separate {sup 99}Mo producing target). This advantage of the one-stage approach arises from the fact that the bremsstrahlung produced is attenuated only once from attenuation in the molybdenum converter/target. In the traditional, two-stage approach, the bremsstrahlung generated in the W-converter/target is attenuated both in the converter in the {sup 99}Mo-producing molybdenum target. The photoneutron production yield of molybdenum and tantalum (as a substitute for tungsten) target was calculated by means of the MCNP5 transport code. On the basis of these data, the specific activity

  9. Formal Specification Based Automatic Test Generation for Embedded Network Systems

    Directory of Open Access Journals (Sweden)

    Eun Hye Choi

    2014-01-01

    Full Text Available Embedded systems have become increasingly connected and communicate with each other, forming large-scaled and complicated network systems. To make their design and testing more reliable and robust, this paper proposes a formal specification language called SENS and a SENS-based automatic test generation tool called TGSENS. Our approach is summarized as follows: (1 A user describes requirements of target embedded network systems by logical property-based constraints using SENS. (2 Given SENS specifications, test cases are automatically generated using a SAT-based solver. Filtering mechanisms to select efficient test cases are also available in our tool. (3 In addition, given a testing goal by the user, test sequences are automatically extracted from exhaustive test cases. We’ve implemented our approach and conducted several experiments on practical case studies. Through the experiments, we confirmed the efficiency of our approach in design and test generation of real embedded air-conditioning network systems.

  10. Photonic arbitrary waveform generator based on Taylor synthesis method

    DEFF Research Database (Denmark)

    Liao, Shasha; Ding, Yunhong; Dong, Jianji

    2016-01-01

    Arbitrary waveform generation has been widely used in optical communication, radar system and many other applications. We propose and experimentally demonstrate a silicon-on-insulator (SOI) on chip optical arbitrary waveform generator, which is based on Taylor synthesis method. In our scheme......, a Gaussian pulse is launched to some cascaded microrings to obtain first-, second- and third-order differentiations. By controlling amplitude and phase of the initial pulse and successive differentiations, we can realize an arbitrary waveform generator according to Taylor expansion. We obtain several typical...... waveforms such as square waveform, triangular waveform, flat-top waveform, sawtooth waveform, Gaussian waveform and so on. Unlike other schemes based on Fourier synthesis or frequency-to-time mapping, our scheme is based on Taylor synthesis method. Our scheme does not require any spectral disperser or large...

  11. Pulsed corona generation using a diode-based pulsed power generator

    Science.gov (United States)

    Pemen, A. J. M.; Grekhov, I. V.; van Heesch, E. J. M.; Yan, K.; Nair, S. A.; Korotkov, S. V.

    2003-10-01

    Pulsed plasma techniques serve a wide range of unconventional processes, such as gas and water processing, hydrogen production, and nanotechnology. Extending research on promising applications, such as pulsed corona processing, depends to a great extent on the availability of reliable, efficient and repetitive high-voltage pulsed power technology. Heavy-duty opening switches are the most critical components in high-voltage pulsed power systems with inductive energy storage. At the Ioffe Institute, an unconventional switching mechanism has been found, based on the fast recovery process in a diode. This article discusses the application of such a "drift-step-recovery-diode" for pulsed corona plasma generation. The principle of the diode-based nanosecond high-voltage generator will be discussed. The generator will be coupled to a corona reactor via a transmission-line transformer. The advantages of this concept, such as easy voltage transformation, load matching, switch protection and easy coupling with a dc bias voltage, will be discussed. The developed circuit is tested at both a resistive load and various corona reactors. Methods to optimize the energy transfer to a corona reactor have been evaluated. The impedance matching between the pulse generator and corona reactor can be significantly improved by using a dc bias voltage. At good matching, the corona energy increases and less energy reflects back to the generator. Matching can also be slightly improved by increasing the temperature in the corona reactor. More effective is to reduce the reactor pressure.

  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. Application state of radioisotopes for medical use

    International Nuclear Information System (INIS)

    Nakajima, Tomoyoshi

    1979-01-01

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

  14. 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.

  15. 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)

  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. Mathematical models and accuracy of radioisotope gauges

    International Nuclear Information System (INIS)

    Urbanski, P.

    1989-01-01

    Mathematical expressions relating the variance and mean value of the intrinsic error with the parameters of one and multi-dimensional mathematical models of radioisotope gauges are given. Variance of the intrinsic error at the model's output is considered as a sum of the variances of the random error which is created in the first stages of the measuring chain and the random error of calibration procedure. The mean value of the intrinsic error (systematic error) appears always for nonlinear models. It was found that the optimal model of calibration procedure not always corresponds to the minimal value of the intrinsic error. The derived expressions are applied for the assessment of the mathematical models of some of the existing gauges (radioisotope belt weigher, XRF analyzer and coating thickness gauge). 7 refs., 5 figs., 1 tab. (author)

  18. Substrate metabolism in isolated rat jejunal epithelium. Analysis using 14C-radioisotopes

    International Nuclear Information System (INIS)

    Mallet, R.T.

    1986-01-01

    The jejunal epithelium absorbs nutrients from the intestinal lumen and is therefore the initial site for metabolism of these compounds. The purpose of this investigation is to analyze substrate metabolism in a preparation of jejunal epithelium relatively free of other tissues. Novel radioisotopic labelling techniques allow quantitation of substrate metabolism in the TCA cycle, Embden-Meyerhof (glycolytic) pathway, and hexose monophosphate shunt. For example, ratios of 14 CO 2 production from pairs of 14 C-pyruvate, and 14 C-succinate radioisotopes (CO 2 ratios) indicate the probability of TCA cycle intermediate efflux to generate compounds other than CO 2 . With (2,3- 14 C)succinate as tracer, the ratio of 14 C in carbon 4 + 5 versus carbon 2 + 3 of citrate, the citrate labelling ratio, equals the probability of TCA intermediate flux to the acetyl CoA-derived portion of citrate versus flux to the oxaloacetate-derived portion. The principal metabolic substrates for the jejunal epithelium are glucose and glutamine. CO 2 ratios indicate that glutamine uptake and metabolism is partially Na + -independent, and is saturable, with a half-maximal rate at physiological plasma glutamine concentrations. Glucose metabolism in the jejunal epithelium proceeds almost entirely via the Embden-Meyerhof pathway. Conversion of substrates to multi-carbon products in this tissue allows partial conservation of reduced carbon for further utilization in other tissues. In summary, metabolic modeling based on 14 C labelling ratios is a potentially valuable technique for analysis of metabolic flux patterns in cell preparations

  19. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    Energy Technology Data Exchange (ETDEWEB)

    Caffrey, Gus J. [Idaho National Laboratory, Idaho Falls, ID (United States); Egger, Ann E. [Idaho National Laboratory, Idaho Falls, ID (United States); Krebs, Kenneth M. [Idaho National Laboratory, Idaho Falls, ID (United States); Milbrath, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jordan, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Warren, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilmer, N. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—Osiris—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  20. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    International Nuclear Information System (INIS)

    Caffrey, Gus J.; Egger, Ann E.; Krebs, Kenneth M.; Milbrath, B. D.; Jordan, D. V.; Warren, G. A.; Wilmer, N. G.

    2015-01-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy-Osiris-software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  1. Visualization of Radioisotope Detectability Over Time.

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-02-01

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

  2. 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)

  3. Utilization of radioisotopes in the agriculture

    International Nuclear Information System (INIS)

    Cerri, C.C.

    1987-01-01

    Some aspects of radioisotopes utilization in the agriculture, such as, the use of gamma radiation for genetic improvement of plants; the use of C 14 as tracer for comprehension of the vegetable physiology; the use of nitrogen and phosphorus isotopes in soil fertilization and plant nutrition; the use of radiation for inset sterelization and, measurement of the humidity and density of soils by neutron moderation and attenuation of gamma radiation, are presented. (M.C.K.) [pt

  4. Lethality of radioisotopes in early mouse embryos

    International Nuclear Information System (INIS)

    Macqueen, H.A.

    1979-01-01

    The development of pre-implantation mouse embryos was found to be prevented by exposure of the embryos to [ 35 S]methionine, but not to [ 3 H]methionine. Such embryos have also been shown to be highly sensitive to [ 3 H]thymidine. These observations are discussed with reference to the path lengths and energies of electrons emitted from the different radioisotopes. (author)

  5. Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1994-12-01

    Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs

  6. Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs.

  7. DNA-based random number generation in security circuitry.

    Science.gov (United States)

    Gearheart, Christy M; Arazi, Benjamin; Rouchka, Eric C

    2010-06-01

    DNA-based circuit design is an area of research in which traditional silicon-based technologies are replaced by naturally occurring phenomena taken from biochemistry and molecular biology. This research focuses on further developing DNA-based methodologies to mimic digital data manipulation. While exhibiting fundamental principles, this work was done in conjunction with the vision that DNA-based circuitry, when the technology matures, will form the basis for a tamper-proof security module, revolutionizing the meaning and concept of tamper-proofing and possibly preventing it altogether based on accurate scientific observations. A paramount part of such a solution would be self-generation of random numbers. A novel prototype schema employs solid phase synthesis of oligonucleotides for random construction of DNA sequences; temporary storage and retrieval is achieved through plasmid vectors. A discussion of how to evaluate sequence randomness is included, as well as how these techniques are applied to a simulation of the random number generation circuitry. Simulation results show generated sequences successfully pass three selected NIST random number generation tests specified for security applications.

  8. Capacity expansion model of wind power generation based on ELCC

    Science.gov (United States)

    Yuan, Bo; Zong, Jin; Wu, Shengyu

    2018-02-01

    Capacity expansion is an indispensable prerequisite for power system planning and construction. A reasonable, efficient and accurate capacity expansion model (CEM) is crucial to power system planning. In most current CEMs, the capacity of wind power generation is considered as boundary conditions instead of decision variables, which may lead to curtailment or over construction of flexible resource, especially at a high renewable energy penetration scenario. This paper proposed a wind power generation capacity value(CV) calculation method based on effective load-carrying capability, and a CEM that co-optimizes wind power generation and conventional power sources. Wind power generation is considered as decision variable in this model, and the model can accurately reflect the uncertainty nature of wind power.

  9. Medical Radioisotope Scanning. Proceedings of a Seminar

    International Nuclear Information System (INIS)

    1959-01-01

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

  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. 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.

  12. 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.)

  13. Medical Radioisotope Scanning. Proceedings of a Seminar

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-01

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

  14. 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

  15. Current status and recent developments of industrial radioisotope applications in Japan

    International Nuclear Information System (INIS)

    Tominaga, Hiroshi

    1985-01-01

    The current status of application of radioisotopes to industry in Japan is briefly reviewed. Radioisotope gauges are widely used in industry, but most of the radioactive tracer applications are performed in laboratories. as for the recent developments, it is noted that the majority of them are related to high technologies in industry. Some typical examples are described. They include: high accuracy coke moisture guage--dual channel gauging on-line analyzers based on 252 Cf, simultaneous neutron and gamma radiography; tracer techniques in civil engineering field, electronics industry, automobile industry and iron and steel industry.(M.G.B.)

  16. Automatic Structure-Based Code Generation from Coloured Petri Nets

    DEFF Research Database (Denmark)

    Kristensen, Lars Michael; Westergaard, Michael

    2010-01-01

    Automatic code generation based on Coloured Petri Net (CPN) models is challenging because CPNs allow for the construction of abstract models that intermix control flow and data processing, making translation into conventional programming constructs difficult. We introduce Process-Partitioned CPNs...... (PP-CPNs) which is a subclass of CPNs equipped with an explicit separation of process control flow, message passing, and access to shared and local data. We show how PP-CPNs caters for a four phase structure-based automatic code generation process directed by the control flow of processes....... The viability of our approach is demonstrated by applying it to automatically generate an Erlang implementation of the Dynamic MANET On-demand (DYMO) routing protocol specified by the Internet Engineering Task Force (IETF)....

  17. 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.

  18. Distributed network generation based on preferential attachment in ABS

    NARCIS (Netherlands)

    K. Azadbakht (Keyvan); N. Bezirgiannis (Nikolaos); F.S. de Boer (Frank)

    2017-01-01

    textabstractGeneration of social networks using Preferential Attachment (PA) mechanism is proposed in the Barabasi-Albert model. In this mechanism, new nodes are introduced to the network sequentially and they attach to the existing nodes preferentially where the preference can be based on the

  19. Real Time Engineering Analysis Based on a Generative Component Implementation

    DEFF Research Database (Denmark)

    Kirkegaard, Poul Henning; Klitgaard, Jens

    2007-01-01

    The present paper outlines the idea of a conceptual design tool with real time engineering analysis which can be used in the early conceptual design phase. The tool is based on a parametric approach using Generative Components with embedded structural analysis. Each of these components uses the g...

  20. Balanced Civilization Map Generation based on Open Data

    DEFF Research Database (Denmark)

    Barros, Gabriella; Togelius, Julian

    2015-01-01

    This work investigates how to incorporate real-world data into game content so that the content is playable and enjoyable while not misrepresenting the data. We propose a method for generating balanced Civilization maps based on Open Data, describing how to acquire, transform and integrate...

  1. Stirling based micro co-generation system for single households

    Energy Technology Data Exchange (ETDEWEB)

    Ribberink, J.S.; Zutt, J.G.M.; Rabou, L.P.L.M.; Beckers, G.J.J. [ECN Clean Fossil Fuels, Petten (Netherlands); Baijens, C.A.W.; Luttikholt, J.J.M. [ATAG Verwarming, Lichtenvoorde (Netherlands)

    2000-04-01

    This paper describes the progress made in the ENATEC development program for a free piston Stirling engine based micro co-generation system that serves the supply of up to 1 kW{sub e} and up to 24 kW heat for domestic heating and/or for hot tap water production for single households at overall system efficiencies of 96%. Experiments show that the free piston Stirling engines from Stirling Technology Company run very reliably and controllably, and that the efficiency targets for the 1 kW{sub e} micro co-generation system are feasible. A ceramic foam burner with good heat transfer characteristics and low NOx emissions was developed. A demonstration micro co-generation unit was built and successfully presented. A 1 kW{sub e} free piston Stirling engine for the European market was developed. High efficiencies at full load and at part load, low emissions, low noise, and minimum maintenance make the Stirling engine based micro co-generation system an attractive candidate for the next generation of domestic boilers in Europe. 5 refs.

  2. Generation of Quasi-Gaussian Pulses Based on Correlation Techniques

    Directory of Open Access Journals (Sweden)

    POHOATA, S.

    2012-02-01

    Full Text Available The Gaussian pulses have been mostly used within communications, where some applications can be emphasized: mobile telephony (GSM, where GMSK signals are used, as well as the UWB communications, where short-period pulses based on Gaussian waveform are generated. Since the Gaussian function signifies a theoretical concept, which cannot be accomplished from the physical point of view, this should be expressed by using various functions, able to determine physical implementations. New techniques of generating the Gaussian pulse responses of good precision are approached, proposed and researched in this paper. The second and third order derivatives with regard to the Gaussian pulse response are accurately generated. The third order derivates is composed of four individual rectangular pulses of fixed amplitudes, being easily to be generated by standard techniques. In order to generate pulses able to satisfy the spectral mask requirements, an adequate filter is necessary to be applied. This paper emphasizes a comparative analysis based on the relative error and the energy spectra of the proposed pulses.

  3. Customer based distributed generation: Economics and policy issues

    International Nuclear Information System (INIS)

    Maribu, Karl Magnus

    2005-01-01

    This paper presents a model for finding distributed generation systems that maximizes the economic benefits for buildings with electricity, heat and cooling loads. Important factors for profitability are identified using simulated data for a standard health care and office building in California. Under the assumed time of use (TOU) prices demand charges are critical factors for the profitability. Systems with lower reliability than promised can infer large losses to the developer. The outage risk is a diversifiable risk hence demands charges should not be a barrier to distributed generation adoption in a well functioning market. In a variety of natural gas and electricity price scenarios the optimal decision is to install distributed generation units with heat recovery and absorption cooling. The benefit maximizing solution reduces building carbon emissions in most scenarios. Low natural gas price scenarios have the highest carbon emissions. An introduction of a carbon tax can further reduce emissions. Small photovoltaic systems gets profitable at prices around 2.4 $/W and larger systems from prices around 1.8-2 $/W if they are analyzed independently from gas fueled generators. In competition with natural gas fueled equipment both the break-even cost and the installed capacity is reduced in both buildings. It is possible to find a profitable solution for real discount rates up to 20 percent under the base case solution for the health care building. High discount rates favor small less capital intensive base load generation systems with heat recovery. (Author)

  4. Market based generation: A promising market management option

    International Nuclear Information System (INIS)

    Siddiqi, R.

    1992-01-01

    It is proposed to ease the tension between demand management and supply side management at electric utilities through the introduction of a concept called market management. Market management provides a framework for developing and evaluating the attractiveness of new products and services such as dispersed generation hardware, implementation services, and complementary pricing structures. A market management strategy is the definition of market segments, creating products for those segments, evaluation of the profitability of the product-segment combinations, commitment of resources to those segments, and development of product and marketing plans for those segments. A brief analysis of backup generation is presented as an example of market management. In this example, the customer that is backed up shares some portion of the capital and maintenance costs of the backup unit through priority service rates; the utility and customers that are not backed up can obtain the use of the generating resource but pay only a portion of its costs. Backup generation programs have been found to provide utilities with the ability to meet peak load requirements more cheaply than by investing in peaking capacity. Other benefits for utilities include protection of market share, more efficient rates, and a new source of revenues. With the advances in the technology of small-scale generation, utilities can examine bundling various pricing options with market based generation to offer alternative value-added service options to customer segments with demand characteristics that make these technologies attractive. 3 figs

  5. Generation of short electrical pulses based on bipolar transistorsny

    Directory of Open Access Journals (Sweden)

    M. Gerding

    2004-01-01

    Full Text Available A system for the generation of short electrical pulses based on the minority carrier charge storage and the step recovery effect of bipolar transistors is presented. Electrical pulses of about 90 ps up to 800 ps duration are generated with a maximum amplitude of approximately 7V at 50Ω. The bipolar transistor is driven into saturation and the base-collector and base-emitter junctions become forward biased. The resulting fast switch-off edge of the transistor’s output signal is the basis for the pulse generation. The fast switching of the transistor occurs as a result of the minority carriers that have been injected and stored across the base-collector junction under forward bias conditions. If the saturated transistor is suddenly reverse biased the pn-junction will appear as a low impedance until the stored charge is depleted. Then the impedance will suddenly increase to its normal high value and the flow of current through the junction will turn to zero, abruptly. A differentiation of the output signal of the transistor results in two short pulses with opposite polarities. The differentiating circuit is implemented by a transmission line network, which mainly acts as a high pass filter. Both the transistor technology (pnp or npn and the phase of the transfer function of the differentating circuit influence the polarity of the output pulses. The pulse duration depends on the transistor parameters as well as on the transfer function of the pulse shaping network. This way of generating short electrical pulses is a new alternative for conventional comb generators based on steprecovery diodes (SRD. Due to the three-terminal structure of the transistor the isolation problem between the input and the output signal of the transistor network is drastically simplified. Furthermore the transistor is an active element in contrast to a SRD, so that its current gain can be used to minimize the power of the driving signal.

  6. Development of an externally controllable sealed isotope generator.

    Science.gov (United States)

    Sasaki, Toru; Aoki, Katsumi; Yamashita, Ryosuke; Hori, Kensuke; Kato, Taiga; Saito, Misaki; Niisawa, Kazuhiro; Nagatsu, Kotaro; Nozaki, Tadashi

    2018-03-01

    An externally controllable sealed isotope generator has been proposed for radiation education activities. Column ( 68 Ge- 68 Ga and 137 Cs- 137m Ba) and solvent extraction ( 68 Ge- 68 Ga)-based isotope generators were applied as radioactive sources. These generators showed high milking efficiencies and low breakthrough after repeated uses, and are expected to promote the use of isotope generators without radioactive contamination or the emission of radioactive waste. This isotope generator provides a new concept for sealed radioisotope sources. Copyright © 2017 Elsevier Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

    Hardy, C.J.

    1987-01-01

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

  8. CAMAC based Test Signal Generator using Re-configurable device

    International Nuclear Information System (INIS)

    Sharma, Atish; Raval, Tushar; Srivastava, Amit K; Reddy, D Chenna

    2010-01-01

    There are many different types of signal generators, with different purposes and applications (and at varying levels of expense). In general, no device is suitable for all possible applications. Hence the selection of signal generator is as per requirements. For SST-1 Data Acquisition System requirements, we have developed a CAMAC based Test Signal Generator module using Re-configurable device (CPLD). This module is based on CAMAC interface but can be used for testing both CAMAC and PXI Data Acquisition Systems in SST-1 tokamak. It can also be used for other similar applications. Unlike traditional signal generators, which are embedded hardware, it is a flexible hardware unit, programmable through Graphical User Interface (GUI) developed in LabVIEW application development tool. The main aim of this work is to develop a signal generator for testing our data acquisition interface for a large number of channels simultaneously. The module front panel has various connectors like LEMO and D type connectors for signal interface. The module can be operated either in continuous signal generation mode or in triggered mode depending upon application. This can be done either by front panel switch or through CAMAC software commands (for remote operation). Similarly module reset and trigger generation operation can be performed either through front panel push button switch or through software CAMAC commands. The module has the facility to accept external TTL level trigger and clock through LEMO connectors. The module can also generate trigger and the clock signal, which can be delivered to other devices through LEMO connectors. The module generates two types of signals: Analog and digital (TTL level). The analog output (single channel) is generated from Digital to Analog Converter through CPLD for various types of waveforms like Sine, Square, Triangular and other wave shape that can vary in amplitude as well as in frequency. The module is quite useful to test up to 32 channels

  9. Pseudo-random bit generator based on lag time series

    Science.gov (United States)

    García-Martínez, M.; Campos-Cantón, E.

    2014-12-01

    In this paper, we present a pseudo-random bit generator (PRBG) based on two lag time series of the logistic map using positive and negative values in the bifurcation parameter. In order to hidden the map used to build the pseudo-random series we have used a delay in the generation of time series. These new series when they are mapped xn against xn+1 present a cloud of points unrelated to the logistic map. Finally, the pseudo-random sequences have been tested with the suite of NIST giving satisfactory results for use in stream ciphers.

  10. Realistic generation of natural phenomena based on video synthesis

    Science.gov (United States)

    Wang, Changbo; Quan, Hongyan; Li, Chenhui; Xiao, Zhao; Chen, Xiao; Li, Peng; Shen, Liuwei

    2009-10-01

    Research on the generation of natural phenomena has many applications in special effects of movie, battlefield simulation and virtual reality, etc. Based on video synthesis technique, a new approach is proposed for the synthesis of natural phenomena, including flowing water and fire flame. From the fire and flow video, the seamless video of arbitrary length is generated. Then, the interaction between wind and fire flame is achieved through the skeleton of flame. Later, the flow is also synthesized by extending the video textures using an edge resample method. Finally, we can integrate the synthesized natural phenomena into a virtual scene.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  12. 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

  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. 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)

  15. 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

  16. Clouds, airplanes, trucks and people: carrying radioisotopes to and across Mexico.

    Science.gov (United States)

    Mateos, Gisela; Suárez-Díaz, Edna

    2015-01-01

    The aim of this paper is to describe the early stages of Mexican nuclearization that took place in contact with radioisotopes. This history requires a multilayered narrative with an emphasis in North-South asymmetric relations, and in the value of education and training in the creation of international asymmetrical networks. Radioisotopes were involved in exchanges with the United States since the late 1940s, but also with Canada. We also describe the context of implementation of Eisenhower's Atoms for Peace initiative in Mexico that opened the door to training programs at both the Comisión Nacional de Energía Nuclear and the Universidad Nacional Autónoma de México. Radioisotopes became the best example of the peaceful applications of atomic energy, and as such they fitted the Mexican nuclearization process that was and still is defined by its commitment to pacifism. In 1955 Mexico became one of the 16 members of the atomic fallout network established by the United Nations. As part of this network, the first generation of Mexican (women) radio-chemists was trained. By the end of the 1960s, radioisotopes and biological markers were being produced in a research reactor, prepared and distributed by the CNEN within Mexico. We end up this paper with a brief reflection on North-South nuclear exchanges and the particularities of the Mexican case.

  17. Image-Based Geometric Modeling and Mesh Generation

    CERN Document Server

    2013-01-01

    As a new interdisciplinary research area, “image-based geometric modeling and mesh generation” integrates image processing, geometric modeling and mesh generation with finite element method (FEM) to solve problems in computational biomedicine, materials sciences and engineering. It is well known that FEM is currently well-developed and efficient, but mesh generation for complex geometries (e.g., the human body) still takes about 80% of the total analysis time and is the major obstacle to reduce the total computation time. It is mainly because none of the traditional approaches is sufficient to effectively construct finite element meshes for arbitrarily complicated domains, and generally a great deal of manual interaction is involved in mesh generation. This contributed volume, the first for such an interdisciplinary topic, collects the latest research by experts in this area. These papers cover a broad range of topics, including medical imaging, image alignment and segmentation, image-to-mesh conversion,...

  18. 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

  19. 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.

  20. 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