Application for Renewal of License SNM-1039,Changing User & Adding More Detailed Description of Testing Procedures
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Ep 0548157 B1
Patentamt Europaisches || || 1 1| || || 1 1 1| || 1 1| || || (19) J European Patent Office Office europeen des brevets (1 1 ) EP 0 548 157 B1 (12) EUROPEAN PATENT SPECIFICATION (45) Date of publicationation and mention (51) |nt. CI.6: A61 K 47/48, A61 K 49/00 of the grant of the patent: 20.05.1998 Bulletin 1998/21 (86) International application number: PCT/EP91/01780 (21) Application number: 91916129.9 (87) International publication number: (22) Date of filing : 1 3.09.1 991 WO 92/04916 (02.04.1992 Gazette 1992/08) (54) USE OF PARTICULATE AGENTS VERWENDUNG VON SUBSTANZEN IN PARTIKELFORM UTILISATION D' AGENTS SOUS FORME DE PARTICULES (84) Designated Contracting States: (72) Inventor: FILLER, Aaron, Gershon AT BE CH DE DK ES FR GB GR IT LI LU NL SE London SW20 ONE (GB) (30) Priority: 14.09.1990 GB 9020075 (74) Representative: 30.10.1990 GB 9023580 Perry, Robert Edward et al 17.12.1990 GB 9027293 GILL JENNINGS & EVERY 07.01.1991 GB 9100233 Broadgate House 16.01.1991 GB 9100981 7 Eldon Street 31.01.1991 GB 9102146 London EC2M 7LH (GB) 20.05.1991 GB 9110876 30.07.1991 GB 9116373 (56) References cited: 19.08.1991 GB 9117851 WO-A-86/01112 WO-A-88/00060 30.08.1991 GB 9118676 WO-A-89/09625 WO-A-90/01295 (43) Date of publication of application: STN File Server, File Medline, accession no. 30.06.1993 Bulletin 1993/26 87239688; J.E. GALLAGHER et al.: "Sialic acid mediates the initial binding of positively charged (60) Divisional application: inorganic particles to alveolar macrophage 97119199.4 membranes" STN File Server, File Medline, accession no. -
HISTORY Nuclear Medicine Begins with a Boa Constrictor
HISTORY Nuclear Medicine Begins with a Boa Constrictor Marshal! Brucer J Nucl Med 19: 581-598, 1978 In the beginning, a boa constrictor defecated in and then analyzed the insoluble precipitate. Just as London and the subsequent development of nuclear he suspected, it was almost pure (90.16%) uric medicine was inevitable. It took a little time, but the acid. As a thorough scientist he also determined the 139-yr chain of cause and effect that followed was "proportional number" of 37.5 for urea. ("Propor inexorable (7). tional" or "equivalent" weight was the current termi One June week in 1815 an exotic animal exhibi nology for what we now call "atomic weight.") This tion was held on the Strand in London. A young 37.5 would be used by Friedrich Woehler in his "animal chemist" named William Prout (we would famous 1828 paper on the synthesis of urea. Thus now call him a clinical pathologist) attended this Prout, already the father of clinical pathology, be scientific event of the year. While he was viewing a came the grandfather of organic chemistry. boa constrictor recently captured in South America, [Prout was also the first man to use iodine (2 yr the animal defecated and Prout was amazed by what after its discovery in 1814) in the treatment of thy he saw. The physiological incident was common roid goiter. He considered his greatest success the place, but he was the only person alive who could discovery of muriatic acid, inorganic HC1, in human recognize the material. Just a year earlier he had gastric juice. -
Manganese-52M, a New Short-Lived,Generator-Produced Radionuclide: a Potential Tracer for Positron Tomography
Manganese-52m, A New Short-Lived,Generator-Produced Radionuclide: A Potential Tracer for Positron Tomography RobertW. ArnoldM.Friedman,JohnA. Huizenga,G.V. S. Rayudu,EdwardA. Sliverstein,andDavidA. Turner Argonne NatlonalLaboratory, Argonne, Ililnols, University ofRochester, Rochester, New York, and Rush University Medical Center, Chicago, Ililnols A new generator system has been developed using the Fe-52 —@Mn-52m par ent-daughter pair. Fe-52, half-lIfe 8.3 hr, is Isolated on an anion-exchange column, and Mn-52m is eluted in hydrochloric acid. Breakthrough is less than 0.01 % and the yield is 75%. The 21.1-mm half life of Mn-52m is ideal for use In sequential studies,butislongenoughtopermftradlochemlcaImanipulationstocontrolblodis tribution.AnImalstudiesIndIcatethat Mn-52mis an Idealnuclidefor myocardial Imaging, combining rapid blood clearance and high concentration in the myocar dlum. An added advantage is that Mn-52m decays 98 % by positron emission and Is useful for posftron computer tomography. J NuciMed 21: 565—569,1980 Interest in the use of nuclear medicine techniques ton (99.2%). Mn-52m decays by positron emission for dynamic or sequential studies has pointed out the (98.3%) with a 21.1-mm half-life. The positron energy limitations of Tc-99m. Its relatively long (6 hn) half-life, is 2.631 MeV. In addition to the annihilation radiation, reduces its applicability for studies in which the tracer Mn-52m emits a l434-keV gamma (98.3%). The re has a biological half-time on the order of minutes. mainder of the decay is by isomenictransition to Mn-52, The recent advances in three-dimensional imaging which has a 5.59 day half-life (Fig. -
Uses of Isotopic Neutron Sources in Elemental Analysis Applications
EG0600081 3rd Conference on Nuclear & Particle Physics (NUPPAC 01) 20 - 24 Oct., 2001 Cairo, Egypt USES OF ISOTOPIC NEUTRON SOURCES IN ELEMENTAL ANALYSIS APPLICATIONS A. M. Hassan Department of Reactor Physics Reactors Division, Nuclear Research Centre, Atomic Energy Authority. Cairo-Egypt. ABSTRACT The extensive development and applications on the uses of isotopic neutron in the field of elemental analysis of complex samples are largely occurred within the past 30 years. Such sources are used extensively to measure instantaneously, simultaneously and nondestruclively, the major, minor and trace elements in different materials. The low residual activity, bulk sample analysis and high accuracy for short lived elements are improved. Also, the portable isotopic neutron sources, offer a wide range of industrial and field applications. In this talk, a review on the theoretical basis and design considerations of different facilities using several isotopic neutron sources for elemental analysis of different materials is given. INTRODUCTION In principle there are two ways to use neutrons for elemental and isotopic abundance analysis in samples. One is the neutron activation analysis which we call it the "off-line" where the neutron - induced radioactivity is observed after the end of irradiation. The other one we call it the "on-line" where the capture gamma-rays is observed during the neutron bombardment. Actually, the sequence of events occurring during the most common type of nuclear reaction used in this analysis namely the neutron capture or (n, gamma) reaction, is well known for the people working in this field. The neutron interacts with the target nucleus via a non-elastic collision, a compound nucleus forms in an excited state. -
H*(10) Y Fluencias En Un Irradiador De Neutrones Con Una Fuente De Ra-Be
ISSSD 2020 ONLINE _________________________________________________________________________________ H*(10) y fluencias en un irradiador de neutrones con una fuente de 226Ra-Be Bedher O. Vega-Cabrera1,*, Héctor René Vega-Carrillo2, Víctor M. Viera Castillo1, César J. Guevara Pillaca1, Patrizia E., Pereyra Anaya1 María E. López Herrera1, Daniel F. Palacios Fernández1 1Pontificia Universidad Católica del Perú, Sección de Física. Av. Universitaria 1801, Apartado 1761, Lima – Perú. 2Universidad Autónoma de Zacatecas, Unidad Académica de Estudios Nucleares, C. Ciprés 10, Fracc. La Peñuela, 98068 Zacatecas, Zac. México. * E-mail: [email protected] Resumen Un irradiador de neutrones es un moderador con una fuente isotópica que es usado para enseñanza, entrenamiento y actividades de investigación. Normalmente, el moderador tiene puertos de irradiación radial y/o axial. Con el fin de utilizar el irradiador de neutrones de forma segura y óptima, deben conocerse los niveles de dosis y el espectro de la fluencia de neutrones. En este trabajo se utilizaron métodos Monte Carlo para estimar las fluencias de neutrones en tres rangos de energías: térmicos, epitérmicos y rápidos en siete puertos de un irradiador de neutrones con una fuente 226Ra-Be. El irradiador revestido de plomo contiene parafina wax como medio moderador de neutrones y sus puertos están asignados a diferentes distancias de la fuente de neutrones. El equivalente de dosis ambiental, debido a los neutrones, se estimó a 100 cm lateralmente y a 10 cm por encima del irradiador de neutrones. -
A Retrospective of Cobalt-60 Radiation Therapy: “The Atom Bomb That Saves Lives”
MEDICAL PHYSICS INTERNATIONAL Journal, Special Issue, History of Medical Physics 4, 2020 A RETROSPECTIVE OF COBALT-60 RADIATION THERAPY: “THE ATOM BOMB THAT SAVES LIVES” J. Van Dyk1, J. J. Battista1, and P.R. Almond2 1 Departments of Medical Biophysics and Oncology, Western University, London, Ontario, Canada 2 University of Texas, MD Anderson Cancer Center, Houston, Texas, United States Abstract — The first cancer patients irradiated with CONTENTS cobalt-60 gamma rays using external beam I. INTRODUCTION radiotherapy occurred in 1951. The development of II. BRIEF HISTORY OF RADIOTHERAPY cobalt-60 machines represented a momentous III. LIMITATIONS OF RADIATION THERAPY breakthrough providing improved tumour control UNTIL THE 1950s and reduced complications, along with much lower skin reactions, at a relatively low cost. This article IV. RADIOACTIVE SOURCE DEVELOPMENT provides a review of the historic context in which the V. THE RACE TO FIRST CANCER TREATMENTS advances in radiation therapy with megavoltage VI. COBALT TRUTHS AND CONSEQUENCES gamma rays occurred and describes some of the VII. COBALT TELETHERAPY MACHINE DESIGNS physics and engineering details of the associated VIII. GROWTH AND DECLINE OF COBALT-60 developments as well as some of the key locations and TELETHERAPY people involved in these events. It is estimated that IX. COBALT VERSUS LINAC: COMPETING over 50 million patients have benefited from cobalt-60 teletherapy. While the early growth in the use of MODALITIES cobalt-60 was remarkable, linear accelerators (linacs) X. OTHER USES OF COBALT-60 provided strong competition such that in the mid- XI. SUMMARY AND CONCLUSIONS 1980s, the number of linacs superseded the number of ACKNOWLEDGEMENTS cobalt machines. -
Radiation Safety Training
Radiation Safety Training …it concerns your health! 8/30/2006 Charlie Freeman, RSO Slide #1 SUNY Genseseo Atomic Structure Nucleus Orbiting Electrons – Contains Protons and – “Cloud” of orbiting Neutrons electrons surrounds nucleus – Cloud is relatively large – Small Size (~1E-14 m) (~1E-10 m) – Relatively Large Mass – Low mass – Extremely Large Density – Small amount of Stored – Large amount of Stored Energy Energy – Responsible for Chemical Bonds 8/30/2006 Charlie Freeman, RSO Slide #2 SUNY Genseseo Nomenclature • Element Designation A – “X” = Element Symbol X – “Z” = # protons in nucleus Z • “Atomic #” (each element has a unique Z, see periodic For Example table) 16 – “N” = # neutrons 8 O = O-16 = Oxygen 16 – Atomic mass # = “A” 17 • A = Z + N 8 O = O-17 = Oxygen 17 • Isotope: same Z, different N 197 and A 79 Au = Au-197 = Gold 197 8/30/2006 Charlie Freeman, RSO Slide #3 SUNY Genseseo Example: P-32 • 15 protons 32 • 17 neutrons P • A = 32 15 • Z =15 8/30/2006 Charlie Freeman, RSO Slide #4 SUNY Genseseo Ion • In an electrically neutral atom or molecule, the number of electrons equals the number of protons • Any atom or molecule with an imbalance in electrical charge is called an ion • Ions are chemically unstable, and will seek electrical neutrality by reacting with other atoms or molecules. 8/30/2006 Charlie Freeman, RSO Slide #5 SUNY Genseseo Radioactivity • Definition: A collection of unstable atoms that undergo spontaneous transformation that result in new elements. The degree of radioactivity is given by the number of decays that occur per unit time (decays per minute) • Units of measure: – Dpm, dps – Curie (Ci): 1 Ci = 3.7E10 dps – Bequerel (Bq): 1 Bq = 1dps 8/30/2006 Charlie Freeman, RSO Slide #6 SUNY Genseseo Half-Life & Decay Law • The activity of a sample of radioactive 225 200 atoms decreases over 175 150 time 125 100 75 Activity (Curies) • Half-life: how long it 50 25 takes for activity of 0 0 1 2 3 4 5 6 7 sample to decrease by Time (hours) a factor of ½. -
Operation of Finnish Nuclear Power Plants
/if STUK-B-YTO 135 Operation of Finnish nuclear power plants Quarterly report 1st quarter, 1995 Kirsti Tossavainen (Ed.) SEPTEMBER 1995 STUK-B-YTO 135 SEPTEMBER 1995 Operation of Finnish nuclear power plants Quarterly report 1st quarter, 1995 Kirsti Tossavainen (Ed.) Nuclear Safety Department FINNISH CENTRE FOR RADIATION AND NUCLEAR SAFETY P.O.BOX 14, FIN-00881 HELSINKI FINLAND Tel. +358 0 759881 Translation. Original text in Finnish. ISBN 951-712-062-1 ISSN 0781-2884 Painatuskeskus Oy Helsinki 1995 FINNISH CENTRE FOR RADIATION STUK-B-YTO 135 AND NUCLEAR SAFETY TOSSAVAINEN, Kirsti (ed.). Operation of Finnish Nuclear Power Plants. Quarterly Report, 1st quarter. 1995. STUK-B-YTO 135. Helsinki 1995, 24 pp. + apps. 2 pp. ISBN 951-712-062-1 ISSN 0781-2884 Keywords PWR type reactor, BWR type reactor, NPP operating experience ABSTRACT Quarterly Reports on die operation of Finnish nuclear power plants describe events and observations related to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and of the environment, and tabulated data on the plants' production and load factors are also given. Finnish nuclear power plant units were in power operation in the first quarter of 1995, except for two shutdowns at Loviisa 2, and shutdowns at both TVO units. The shutdowns at Loviisa 2 were due to an abnormal rise in the coolant outlet temperatures of certain fuel bundles. -
Activation Analysis - Nuclear Chemical Research * Radiochemical Separations
DEPARTMENT OF CHEMISTRY UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN . ACTIVATION ANALYSIS - NUCLEAR CHEMICAL RESEARCH * RADIOCHEMICAL SEPARATIONS PROGRESS REPORT 9 November 1, 1960 Supported by DEPARTMENT OF CHEMISTRY MICHIGAN MEMORIAL-PHOENIX PROJECT UNITED ST ATES ATOMIC ENERGY COMMISSION PROJECT NO. 7, CONTRACT NO. AT (11-1)-70 DEPARTMENT OF CHEMISTRY U N I V E R S I T Y O F M I C H I G A N Ann Arbor, Michigan PROGRESS REPORT 9 November 1959 - October 1960 ACTIVATION ANALYSIS NUCLEAR CHEMICAL RESEARCH RADIOCHEMICAL SEPARATIONS Edited by R. S. Maddock and W. W. Meinke, (Project Director) November 1, 1960 Supported by Department of Chemistry Michigan-Memorial Phoenix Project Project No. 7 Contract No. AT(ll-1)-70 U. S. Atomic Energy Commission The following is a report of the work completed on Project No. 7, Contract No. AT(ll-1)-70 during the year of November 1, 1959 to October 31, 1960. Previous progress reports are listed below: Progress Report 1 Novemb er 1952 Progress Report 2 November 1953 Progress Report 3 November 1954 Progress Report 4 (AECU-3116) November 1955 Progress Report 5 (AECU-3375) November 1956 Progress Report 6 (AEcU-3641) November 1957 Progress Report 7 (AEcu.-3887) November 1958 Progress Report 8 (AECU-4438) November 1959 ii FOREWARD A word is perhaps in order about the philosophy of these progress reports which are issued yearly from our laboratories. In any research program a large amount of information is obtained and techniques developed which never find their way into the literature. This includes the "negative results" which are so disappointing and unspectacular but which can often save others considerable work. -
AN34 Application Note Experiment 17 Neutron Activation Analysis
® ORTEC AN34 Experiment 17 Neutron Activation Analysis (Slow Neutrons) Equipment Needed from ORTEC colorimetric, spectrographic, or mass spectroscopy, its sensitivity is usually shown to be better by a factor of 10 than that of other • 113 Scintillation Preamplifier methods. Activation analysis is used extensively in such fields as • 266 Photomultiplier Tube Base geology, medicine, agriculture, electronics, metallurgy, • 4006 or 4001A/4002D Bin and Power Supply criminology, and the petroleum industry. • 556 High Voltage Power Supply • 575A Amplifier The Neutron Source • 905-3 2-in. x 2-in. or 905-4 3-in. x 3-in. NaI(Tl) Detector and PM This experiment is described using 1 Ci of Am-Be for the Tube neutron source, with the source located in the center of a • Easy-MCA 2k System including a USB cable, a suitable PC paraffin howitzer. The samples are irradiated at a point ~4 cm and MAESTRO-32 software (other ORTEC MCAs may be from the source by the neutrons whose energies have been substituted) moderated by the paraffin between that point and the source. • Coaxial Cables and Adapters: Any of the commonly found isotopic neutron sources can be • One C-24-1/2 RG-62A/U 93-Ω coaxial cable with BNC plugs used for this experiment. on both ends, 15-cm (1/2-ft) length. Neutron Activation Equations Ω • One C-24-12 RG-62A/U 93- coaxial cable with BNC plugs Assume that the sample has been activated in the howitzer. At on both ends, 3.7-m (12-ft) length. the instant when the activation has been terminated, (tc = 0), the • Two C-24-4 RG-62A/U 93-Ω coaxial cables with BNC plugs activity of the sample is given by the following expression: on both ends, 1.2-m (4-ft) length. -
Antennas Fabrication for Rfid Uhf and Microwave Passive
TAÏP CHÍ PHAÙT TRIEÅN KH&CN, TAÄP 20, SOÁ T2- 2017 Design and evaluation of neutron howitzer design for the research and education using MCNP5 program Truong Van Minh Dong Nai University Nguyen Ngoc Anh Ho Huu Thang Nguyen Xuan Hai Dalat Nuclear Research Institute Dinh Tien Hung Military Institute of Chemical and Environmental Engineering (Received on 25 th November 2016, accepted on 22 th May 2017) ABSTRACT In this paper, the design evaluation of a cover which is made from steel shields the neutron howitzer using for research and gamma-rays caused by the neutron capture education purposes in Training Center at Dalat reaction of boron. The simulation has been done Nuclear Research Institute is presented. A using the MCNP5 program. The result shows that mixture of paraffin and boron is used as both the design met requirements of usage and moderator and absorber in order to shield radiation safety rules in Vietnam. neutron from the 252Cf source. The howitzer Keywords: Neutron howitzer, paraffin howitzer, howitzer design INTRODUCTION Neutron howitzer is an efficient instrument inconvenient to setup shielding experiments, for research and education purposes, which have neutron cross-section determination, neutron to use isotope neutron sources such as 252Cf [1]. activation analysis, neutron dose calibration and Neutron howitzer can be classified according to some others. usage purposes or neutron moderators. Two Therefore, in order to solve the problem, we materials, which are mainly used as moderator, decided to design a new howitzer, which uses are paraffin and water. paraffin as a moderator. The design of the In 2011, a water neutron howitzer was paraffin howitzer must not only be suitable for established in the Training Center (TC) at Dalat setting up recommended experiments and ensure Nuclear Research Institute (DNRI) [2]. -
Arxiv:1712.05863V1 [Astro-Ph.SR]
Draft version September 17, 2018 A Preprint typeset using L TEX style AASTeX6 v. 1.0 HR 8844: A NEW TRANSITION OBJECT BETWEEN THE AM STARS AND THE HGMN STARS ? R. Monier1 LESIA, UMR 8109, Observatoire de Paris et Universit´ePierre et Marie Curie Sorbonne Universit´es, place J. Janssen, Meudon. M. Gebran2 Department of Physics and Astronomy, Notre Dame University-Louaize, PO Box 72, Zouk Mikael, Lebanon. F. Royer3 GEPI, Observatoire de Paris, place J. Janssen, Meudon, France. T. Kilicoglu4 Department of Astronomy and Space Sciences, Faculty of Science, Ankara University, 06100, Turkey. Y. Fremat´ 5 Royal observatory of Belgium, Dept. Astronomy and Astrophysics, Brussels, 8510, Belgium. ABSTRACT While monitoring a sample of apparently slowly rotating superficially normal early A stars, we have discovered that HR 8844 (A0 V), is actually a new Chemically Peculiar star. We have first compared the high resolution spectrum of HR 8844 to that of four slow rotators near A0V (ν Cap, ν Cnc , Sirius A and HD 72660) to highlight similarities and differences. The lines of Ti II, Cr II, Sr II and Ba II are conspicuous features in the high resolution high signal-to-noise SOPHIE spectra of HR 8844 and much stronger than in the spectra of the normal star ν Cap. The Hg II line at 3983.93 A˚ is also present in a 3.5 % blend. Selected unblended lines of 31 chemical elements from He up to Hg have been synthesized using model atmospheres computed with ATLAS9 and the spectrum synthesis code SYNSPEC48 including hyperfine structure of various isotopes when relevant.