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New accelerator produced radiopharmaceuticals

Description: From 11th international annual Meeting of the German Society of Nuclear Medicine; Athens, Greece (24 8ep 1973). The use of multi-purpose, high-current linear accelerators in the production of radionuclides for the development of new radiopharmaceuticals is discussed. A listing of pertinent information regarding the method of production, rate of production, expected yields, and potential application for /sup 123/I, /sup 52/Fe, /sup 127/Xe, /sup 201/Tl, /sup 82/Rb, and /sup 97/Ru is presented. (DHM)
Date: January 1, 1973
Creator: Richards, P. & Lebowitz, E.
Partner: UNT Libraries Government Documents Department


Description: The 0-degree fragmentation products of {sup 16}O and {sup 12}C at 2.1-GeV/n and {sup 12}C at 1.05-GeV/n have been measured for targets ranging from H to Pb. They present a total of 464 partial-production cross sections for 35 isotopes. The cross sections are energy independent and can be factored into beam-fragment and target terms. The target factor, {gamma}{sub T} = A{sub T}{sup 1/4}, and other evidence, imply the isotopes are produced in peripheral interactions.
Date: February 1, 1975
Creator: Lindstrom, P.J.; Greiner, D.E.; Heckman, H.H.; Cork, Bruce & Bieser, F.S.
Partner: UNT Libraries Government Documents Department

Solution-reactor-produced Mo-99 using activated carbon to remore I-131

Description: The production of {sup 99}Mo in a solution reactor was explored. Activated charcoal was used to filter the {sup 131}I contaminant from an irradiated fuel solution. Gamma spectroscopy confirmed that the activated carbon trapped a significant amount of {sup 131}I, as well as notable amounts of {sup 133}Xe, {sup 105}Rb, and {sup 140}Ba; the carbon trapped a diminutive amount of {sup 99}Mo. The results promote the idea of solution-reactor-produced {sup 99}Mo. Solution reactors are favorable both energetically and environmentally. A solution reactor could provide enough {sup 99}Mo/{sup 99m}Te to support both the current and future radiopharmaceutical needs of the U.S.
Date: June 1, 1998
Creator: Kitten, S. & Cappiello, C.
Partner: UNT Libraries Government Documents Department

Radioisotope program at LAMPF

Description: From summer study group on practical applications of accelerators; Los Alamos, New Mexico, USA (27 Aug 1973). The status of the program at LAMPF for producing isotopes for research, diagnostic, and therapeutic applications in medicme by proton-induced spallation reactions is summarized. On the basis of cross section and yield measurements, yields of /sup 82/Sr, /sup 123/I, /sup 125/ I, /sup 129/Cs, and /sup 127/Xe from LAMPF are projected. The development of recovery procedures for each of these isotopes, except /sup 129/Cs has been completed to the extent that attention is now being focussed on scaling these procedures to hot cell operations. The Isotope Production Facility is briefly described. (WHK)
Date: January 1, 1973
Creator: O'Brien, H.A. Jr.
Partner: UNT Libraries Government Documents Department

Categorization of Radioxenon

Description: This report summarizes a study into some false positive issues in the use of radioxenon as a method to verify a clandestine nuclear weapons explosion. False positives arise due to similarities between the radioxenon signature generated in medical isotope production and that generated in a nuclear weapon explosion. This report also discusses how to categorize the radioxenon by levels of urgency for manual analysis and interpretation and recommends applying machine learning and time series analysis techniques in the automation of radioxenon characterization. The literature indicates that medical isotope production is a major contributor to atmospheric radioxenon and is the main source of confusion in determining the source of radioxenon. While radioxenon emissions from nuclear power plants can be distinguished from that from nuclear weapon explosions, emissions from medical isotope production generate signatures similar to certain nuclide ratios found in nuclear weapons explosions. Different techniques for analyzing nuclide concentrations and ratios as well as including other sensing modalities via sensor fusion are discussed.
Date: April 26, 2012
Creator: Keller, Paul E.
Partner: UNT Libraries Government Documents Department

Isotope Production Facility Conceptual Thermal-Hydraulic Design Review and Scoping Calculations

Description: The thermal-hydraulic design of the target for the Isotope Production Facility (IPF) is reviewed. In support of the technical review, scoping calculations are performed. The results of the review and scoping calculations are presented in this report.
Date: August 1, 1998
Creator: Pasamehmetoglu, K.O. & Shelton, J.D.
Partner: UNT Libraries Government Documents Department

Oak Ridge Isotope Products and Services - Current and Expected Supply and Demand

Description: Oak Ridge National Laboratory (ORNL) has been a major center of isotope production research, development, and distribution for over 50 years. Currently, the major isotope production activities include (1) the production of transuranium element radioisotopes, including 252 Cf; (2) the production of medical and industrial radioisotopes; (3) maintenance and expansion of the capabilities for production of enriched stable isotopes; and, (4) preparation of a wide range of custom-order chemical and physical forms of isotope products, particularly in accelerator physics research. The recent supply of and demand for isotope products and services in these areas, research and development (R&D), and the capabilities for future supply are described in more detail below. The keys to continuing the supply of these important products and services are the maintenance, improvement, and potential expansion of specialized facilities, including (1) the High Flux Isotope Reactor (HFIR), (2) the Radiochemical Engineering Development Center (REDC) and Radiochemical Development Laboratory (RDL) hot cell facilities, (3) the electromagnetic calutron mass separators and the plasma separation process equipment for isotope enrichment, and (4) the Isotope Research Materials Laboratory (IRML) equipment for preparation of specialized chemical and physical forms of isotope products. The status and plans for these ORNL isotope production facilities are also described below.
Date: August 29, 1999
Creator: Aaron, W.S.; Alexander, C.W.; Cline, R.L.; Collins, E.D.; Klein, J.A.; Knauer, J.B., Jr. et al.
Partner: UNT Libraries Government Documents Department

Overview of the APT high-energy beam transport and beam expanders

Description: The APT high energy beam transport (HEBT) and beam expanders convey the 1700-MeV, 100-mA cw proton beam from the linac to the tritium target/blanket assembly, or a tuning beam stop. The HEBT includes extensive beam diagnostics, collimators, and beam jitter correction, to monitor and control the 170-MW beam prior to expansion. A zero-degree beamline conveys the beam to the beam stop, and an achromatic bend conveys the beam to the tritium production target. Nonlinear beam expanders make use of higher-order multipole magnets and dithering dipoles to expand the beam to a uniform-density, 16-cm wide by 160-cm high rectangular profile on the tritium-production target. The overall optics design will be reviewed, and beam simulations will be presented.
Date: August 1, 1997
Creator: Shafer, R.E.; Blind, B. & Gray, E.R.
Partner: UNT Libraries Government Documents Department

Technology Development for the Accelerator Production of Tritium

Description: The ED and D described in this report provide technical data on the performance of all critical components of the APT facility. Results are compared with requirements given. This data will be utilized to establish confidence in the design, in the predicted plant availability, and to reduce cost when the data warrants design simplification. Thus, if at a later date it is decided to build the APT plant, this will allow the facility to be built correctly the first time, on schedule, without recourse to costly over-design. It should also speed the commissioning process and ensure that full capacity production is attained on schedule. The planning process used to develop the elements of the CTP has been described. This program is expected to provide the needed data within the projected schedule and resources. Specific schedules for delivery of data and descriptions of the needed data are contained in the Design Data Needs. The total cost of the ED and D program is on the order of 10% of the project cost and is considered a very good investment. The CTP will be judged a success when the data produced warrants design simplifications that allow reduction of design margins and cost. Present day contingency estimates for the project greatly exceed 10% and it is expected that CTP data will warrant reduction of those contingencies by more than the cost of data production. Even results that do not simplify the design or reduce cost are considered very important and successful if they firmly establish performance, so that the design is validated and the cost certified within the existing contingencies. Nevertheless, there is technical risk in some APT components that warrant careful attention. It is to be expected that some results could be disappointing and may require design changes that increase cost moderately ...
Date: March 1, 1999
Creator: Anderson, J.L.
Partner: UNT Libraries Government Documents Department