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Lobao, A.S.T.; Araujo, B.F. de; Oliveira, C.A.L.; Matsuda, H.T.; Cohen, V.H.
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)1990
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)1990
AbstractAbstract
[en] Published in summary form only
Original Title
Viabilidade de implantacao de um processo para producao de 99Mo no IPEN - CNEN/SP
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Source
1990; 1 p
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Miscellaneous
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AbstractAbstract
[en] In this study, the decay form of 99Mo which is supplied by KAERI had been investigated from the analysis of γ-ray energy spectrum radiating from the radioactive element 99Mo. The γ-ray energy spectrum was obtained using NaI(T1) scintillation detector and multichannel pulse height analyser. The calibration curve and formula for γ-ray energy versus channel number were made from the two photopeaks of standard radioactive source 22Na, 140 and 314 channel corresponding to the γ-ray energy of 511 keV and 1275 keV, respectively. The γ-ray energies from 99Mo were detected at the same condition with the standard source, and compared with standard energies of 99Mo. Experimental results show that the γ-ray energies from the sample are in good agreement with the values of standard source within energy error of 2 keV, which means that the 99Mo supplied by the KAERI can be used as a standard radioactive source. (Author)
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Record Type
Journal Article
Journal
Journal of Basic Science, The Research Institute of Basic Sciences, Kon-Kuk University; CODEN JBASE; v. 13 p. 1-23
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Thornton, A.K.; Cerone, F.E.
Union Carbide Corp., New York (USA)1978
Union Carbide Corp., New York (USA)1978
AbstractAbstract
[en] The description is given of a rechargeable radioactive isotope generator having the following features: a box containing a transport shield, a shielded generator including elements for the absorption and holding of the parent isotope, an eluant tank, a first pipe causing this tank to communicate with the transport shield, a second pipe causing this transport shield to communicate with the shielded generator and a third pipe placing the shielded generator in communication with the outside of the unit. It also includes a shelf across the external front part of the unit a part of which is shielded by external components, a shielded elution flask in which the eluate is poured and a filter set at a point between the flask and the third pipe
[fr]
On decrit un groupe generateur d'isotope radio-actif rechargeable, caracterise en ce qu'il comprend: un boitier contenant un blindage de transport, un generateur blinde comportant des elements d'absorption et de retenue de l'isotope pere, un reservoir d'eluant, une premiere conduite faisant communiquer ce reservoir avec le blindage de transport, une seconde conduite faisant communiquer ce blindage de transport avec le generatuer blinde, et une troisieme conduite mettant en communication le generateur blinde avec l'exterieur du groupe. Il comprend egalement une tablette traversant la partie frontale exterieure du groupe dont une partie est blindee par des elements exterieurs, un flacon d'elution blinde dans lequel est deverse l'eluat, et un filtre place en un point se trouvant entre le flacon et la troisieme conduiteOriginal Title
Generateur rechargeable d'isotopes radioactifs
Primary Subject
Source
19 Jun 1978; 17 p; FR PATENT DOCUMENT 2395574/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 20 Jun 1977, US.
Record Type
Patent
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AbstractAbstract
[en] This Annex has been provided in its entirety by the University of Missouri Research Reactor as an example procedure. Alternatives to brand name products mentioned may be available. Detailed information on the special tools, equipment and reagents and procedure is given
Primary Subject
Source
International Atomic Energy Agency, Division of Nuclear Fuel Cycle and Waste Technology, Vienna (Austria); 188 p; ISBN 978-92-0-114713-4;
; Jan 2015; p. 163; ISSN 0074-1914;
; Also available on-line: http://www-pub.iaea.org/MTCD/Publications/PDF/trs478web-32777845.pdf; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books


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Book
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AbstractAbstract
[en] Radionuclide generators have been the main stay of diagnostic nuclear medicine and it is no exaggeration to state that the growth of nuclear medicine would not have happened to the present levels but for the availability of 99Mo/99mTc generator. This article provides a brief account of the various radionuclide generators currently in clinical use or which have made substantial progress or likely to be materialized in the foreseeable future to bring evolutional progress in nuclear medicine. Further, a brief outline on the regulatory challenges and impact on radionuclide generator technology with the emergence of professionally run central radiopharmacies have been provided. (author)
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Source
113 refs.
Record Type
Journal Article
Journal
Journal of Radioanalytical and Nuclear Chemistry; ISSN 0236-5731;
; CODEN JRNCDM; v. 302(3); p. 1053-1068

Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, DAYS LIVING RADIOISOTOPES, EVEN-ODD NUCLEI, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MOLYBDENUM ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, RADIOISOTOPES, TECHNETIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The ability to describe in a realistic way the biokinetics of radionuclides in the human body is an important requirement in order to get a reliable dose estimation after incorporation of radioactive substances. Recent experimental data have shown the need to introduce relevant modifications to the current model of the biokinetics of molybdenum adopted by ICRP. A new series of investigations, conducted on healthy human volunteers using stable isotopes of Mo as tracers, has been undertaken in order to improve the knowledge of some of the new features outlined in the preliminary investigations. In particular, the results presented here deal with the dependence of the biokinetic parameters on the mass of Mo administered and on its content in the body. The clearance of Mo from blood plasma is not influenced by the administration of different amounts of Mo; the opposite is true for urinary excretion, which is the process adopted by the organism to regulate the body content of Mo rapidly. This fact can be of some importance in deciding a proper intervention after an accidental incorporation of Mo radionuclides. (author)
Primary Subject
Source
Workshop on intakes of radionuclides: occupational and public exposure; Avignon (France); 15-18 Sep 1997; Available online at http://ntp.org.uk/; Country of input: South Africa
Record Type
Journal Article
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Conference
Journal
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Mestnik, S.A.C.; Silva, C.P.G. da.
Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, SP (Brazil)1989
Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, SP (Brazil)1989
AbstractAbstract
[en] A radiochemical method to isolate 99Mo from 132Te both produced in the fission of 235U has been developed. The methods is based on the formation of a cationic complex of tellerium with thiourea in acid medium which is retained (98.7 +- 0.5)% on a cation exchange resin (Dowex 50W-X8, 100 - 200 mesh) while (99.8 +- 0.05)% 99Mo passes through it, due to the non formation of such complex in the same experimental conditions. The radionuclidic purity of the separated 99Mo verified by using gamma spectrometry was found to be suitable for the preparation of 99Mo - 99 sup (m)Tc generators. The retention of 99Mo on an alumina column as function of ph was investigated. the best pH range for this purpose was found to be between 4.0 - 4.5. the 99Mo - 99mTc generator was prepared. the elution of99mTc was carried out with physiologic saline solution. The radionuclidic purity of the eluate was found suitable and the product can be used for Nuclear Medicine applications. (author)
[pt]
Desenvolveu-se um metodo radioquimico para a separacao de 99Mo do 132Te obtidos na fissao do 235U que se baseia na complexacao do telurio com tioureia, em meio acido. O telurio forma complexo cationico com a tioureia, enquanto que tal nao ocorre com o molibdenio nas mesmas condicoes experimentais. Os resultados obtidos mostraram que a retencao do complexo telurio-tioureia na resina cationica Dowex-50W-X8, 100-200 mesh e (98,7 ± 0,5)%, sendo que (99,8 ± 0,05)%, do 99Mo sao encontrados no efluente. O 99 Mo separado que foi analisado por espectrometria gama apresentou pureza radionuclidica satisfatoria pura uso na preparacao de geradores de 99Mo - 99mTc. Estudou-se tambem a retencao do 99Mo em colunas de alumina em funcao do ph observando-se que a retencao maxima ocorre no intervalo de Ph entre 4,0 e 4,5. Preparou-se o generador 99Mo - 99mTc e eluiu-se o 99mTc com solucao fisiologica. A pureza radionuclidica do eluido foi de 100% aproximadamente, estando de acordo com as Farmacopeias Internacionais para uso em aplicacoes medicas. (autor)Original Title
Separacao de 99Mo do 132Te usando tioureia como agente complexante. Aplicacao a separacao do 99Mo dos produtos de fissao
Source
Feb 1989; 29 p
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Report
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ANTITHYROID DRUGS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBONIC ACID DERIVATIVES, DAYS LIVING RADIOISOTOPES, DRUGS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, INTERMEDIATE MASS NUCLEI, ISOTOPES, MOLYBDENUM ISOTOPES, NUCLEI, ORGANIC COMPOUNDS, ORGANIC SULFUR COMPOUNDS, RADIOISOTOPES, TELLURIUM ISOTOPES, THIOUREAS
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Choi, Seung Rag; Lee, Jun Sig; Choi, Kang Hyuk; Park, Ul Jae; Son, Kwang Jae; Hong, Young Don
Proceedings of the KNS autumn meeting2011
Proceedings of the KNS autumn meeting2011
AbstractAbstract
[en] As an alternative technology of the currently available 99mTc generator, a generator is developed by using an activated 99Mo as the mother source of 99mTc. In the period of 2008 ∼ 2009, the world was suffered by the short supply of 99mTc for medical diagnosis because of the aging of the production plants in the world and no availability of an immediate solution. In this regard, it is expected to secure the supply of 99mTc at least certain portion of the total demand for 99mTc by developing an alternative technology such as producing 99mTc by activated 99Mo, cyclotron technology, etc. This research aims the development of a new 99mTc generator to relief suffer from the short supply of the generator produced by using Fission Moly. The developed generator will act as the emergency 99mTc resource until the ultimate solution becomes realistic. In this paper, the research progress from the basic study that has been performed during the last years will be presented
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2011; [2 p.]; 2011 autumn meeting of the KNS; Kyoungju (Korea, Republic of); 26-28 Oct 2011; Available from KNS, Daejeon (KR); 3 refs, 3 figs
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Miscellaneous
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Conference
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ACCELERATORS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CYCLIC ACCELERATORS, DAYS LIVING RADIOISOTOPES, EVEN-ODD NUCLEI, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MOLYBDENUM ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, RADIOISOTOPES, TECHNETIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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Bertsche, Kirk
SLAC National Accelerator Laboratory (United States). Funding organisation: US Department of Energy (United States)2010
SLAC National Accelerator Laboratory (United States). Funding organisation: US Department of Energy (United States)2010
AbstractAbstract
[en] Shortages of 99Mo, the most commonly used diagnostic medical isotope, have caused great concern and have prompted numerous suggestions for alternate production methods. A wide variety of accelerator-based approaches have been suggested. In this paper we survey and compare the various accelerator-based approaches.
Primary Subject
Source
25 Aug 2010; 3 p; IPAC 2010: 1. International Particle Accelerator Conference; Kyoto (Japan); 23-28 May 2010; AC02-76SF00515; Available from http://www.slac.stanford.edu/cgi-wrap/getdoc/slac-pub-14132.pdf; PURL: https://www.osti.gov/servlets/purl/1000331-2L08I8/
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Report
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AbstractAbstract
[en] Each of four prospective producers of molybdenum-99 says it can satisfy at least half of US demand for the short-lived substance
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(c) 2015 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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