Instrumental Neutron Activation Analysis (INAA)
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Volatility of Radiopharmacy-Prepared Sodium Iodide-131 Capsules
RADIATION SAFETY Volatility of Radiopharmacy-Prepared Sodium Iodide-131 Capsules James M. Bright, Trenton T. Rees, Louis E. Baca and Richard L. Green Pharmacy Services, Syncor International Corporation, Albuquerque, New Mexico; and Quality and Regulatory Department, Syncor International Corporation, Woodland Hills, California studied thyroid physiology using 128I in 1937 (1,2). In January Objective: The aims of this study were to quantify the extent 1941, Hertz and Roberts were the first to administer radioiodine of volatilization from 131I-NaI therapeutic capsules prepared in 131I for the treatment of hyperthyroid patients (3). Today, almost a centralized radiopharmacy and to quantify the amount of 60 y later, radioiodine therapy with 131I remains the primary volatile 131I released from a dispensing vial containing a compounded 131I-NaI therapy capsule. therapeutic agent used in nuclear medicine, and its use is firmly Methods: Therapy capsules were prepared by injecting 131I established in the 2 diseases first treated: hyperthyroidism and oral solution into capsules containing anhydrous dibasic thyroid carcinoma. sodium phosphate. Volatilized activity was obtained by filter- Initially the use of 131I was restricted to the only pharmaceu- ing air drawn across samples that were placed open on the tical dosage form then available—liquid oral solution. While 131 bottom of a sample holder cup. Volatile I was captured by liquid radioiodine proved to be beneficial to the patients to filtering it through 3 triethylenediamine-impregnated carbon whom it was administered, the frequency of contamination and cartridge filters, arranged in series. To quantify the amount of thyroid uptake activity in nuclear medicine personnel who volatile 131I released from a dispensing vial during a simulated patient administration, a vial containing a compounded 131I handled the material was noted with increasing alarm (4–7). -
Neutron Scattering Facilities in Europe Present Status and Future Perspectives
2 ESFRI Physical Sciences and Engineering Strategy Working Group Neutron Landscape Group Neutron scattering facilities in Europe Present status and future perspectives ESFRI scrIPTa Vol. 1 ESFRI Scripta Volume I Neutron scattering facilities in Europe Present status and future perspectives ESFRI Physical Sciences and Engineering Strategy Working Group Neutron Landscape Group i ESFRI Scripta Volume I Neutron scattering facilities in Europe - Present status and future perspectives Author: ESFRI Physical Sciences and Engineering Strategy Working Group - Neutron Landscape Group Scientific editors: Colin Carlile and Caterina Petrillo Foreword Technical editors: Marina Carpineti and Maddalena Donzelli ESFRI Scripta series will publish documents born out of special studies Cover image: Diffraction pattern from the sugar-binding protein Gal3c with mandated by ESFRI to high level expert groups, when of general interest. lactose bound collected using LADI-III at ILL. Picture credits should be given This first volume reproduces the concluding report of an ad-hoc group to D. Logan (Lund University) and M. Blakeley (ILL) mandated in 2014 by the Physical Science and Engineering Strategy Design: Promoscience srl Work Group (PSE SWG) of ESFRI, to develop a thorough analysis of the European Landscape of Research Infrastructures devoted to Neutron Developed on behalf of the ESFRI - Physical Sciences and Engineering Strategy Scattering, and its evolution in the next decades. ESFRI felt the urgency Working Group by the StR-ESFRI project and with the support of the ESFRI of such analysis, since many reactor-based neutron sources will be closed Secretariat down in the next years due to national decisions, while the European The StR-ESFRI project has received funding from the European Union’s Spallation Source (ESS) in Lund will be fully operative only in the mid Horizon 2020 research and innovation programme under grant agreement or late 2020s. -
PGNAA Neutron Source Moderation Setup Optimization
Submitted to ‘Chinese Physics C PGNAA neutron source moderation setup optimization Zhang Jinzhao1(张金钊)Tuo Xianguo1(庹先国) (1.Chengdu University of Technology Applied Nuclear Techniques in Geoscience Key Laboratory of Sichuan Province,Chengdu 610059,China) Abstract: Monte Carlo simulations were carried out to design a prompt γ-ray neutron activation analysis (PGNAA) thermal neutron output setup using MCNP5 computer code. In these simulations the moderator materials, reflective materials and structure of the PGNAA 252Cf neutrons of thermal neutron output setup were optimized. Results of the calcuations revealed that the thin layer paraffin and the thick layer of heavy water moderated effect is best for 252Cf neutrons spectrum. The new design compared with the conventional neutron source design, the thermal neutron flux and rate were increased by 3.02 times and 3.27 times. Results indicate that the use of this design should increase the neutron flux of prompt gamma-ray neutron activation analysis significantly. Key word: PGNAA; neutron source; thermal neutron; moderation; reflection 1. Introduction study, Monte Carlo calculation was carried out for the Prompt gamma ray neutron activation analysis design of a 252Cf neutron source moderation setup for the (PGNAA) is a rapid, nondestructive, powerful analysis cement samples[7]. The model of Monte Carlo multielemental analysis technique, large samples of some simulation was verified by experiment[8, 9].We improve minor, trace light elements and is used in industrial the thermal neutron source yield rate of 252Cf neutron by control[1-5]. In a PGNAA analysis, the sample nuclear the PGNAA neutron source structure to the design. The composition is determined from prompt gamma rays calculation results for the new design were compared which produced through neutron inelastic scattering and with the previous, example: themal neutron flux rate, fast thermal neutron capture. -
Activation Analysis
26 August 1967 Leading Articles MEDIBALJOURNAL 509 her patients or the hospital midwife to undertake the home lation has been found between arsenic level in the blood and visiting of them after discharge. degree of renal insufficiency as indicated by blood creatinine Br Med J: first published as 10.1136/bmj.3.5564.509 on 26 August 1967. Downloaded from From the Bradford reports it can be seen that the final measurements. But speculative inquiries of this kind are decision to permit a mother and baby home after 48 hours worth while because they may sometimes provide the first must be made by someone at least of registrar status. It clue to the solution of an intractable problem. Information would also be of considerable value if the general practitioner of a more immediately useful kind can be expected from and district midwife in charge of such a case could freely using activation analysis in problems where the underlying obtain an opinion by domiciliary consultation from either the biochemical and physiological considerations are better hospital obstetric or paediatric department on any puerperal understood. or neonatal complication before readmission of the woman Thyroid metabolism, much studied by radioactive isotopes, after she has returned home. offers interesting problems for attack by activation analysis. When early discharge was discussed in these columns three Semi-automatic methods for the routine determination of years ago' the conclusion was drawn that, though it might protein-bound stable iodine have been elaborated, notably be suitable in emergency conditions, it had little part in in France,2 where the establishment of a laboratory to carry long-term planning. -
Arxiv:1708.07449V1 [Nucl-Ex] 24 Aug 2017
August 25, 2017 0:18 WSPC/INSTRUCTION FILE cosmogenics-ijmpa International Journal of Modern Physics A c World Scientific Publishing Company Cosmogenic activation of materials Susana Cebri´an Grupo de F´ısica Nuclear y Astropart´ıculas, Universidad de Zaragoza, Calle Pedro Cerbuna 12, 50009 Zaragoza, Spain Laboratorio Subterr´aneo de Canfranc, Paseo de los Ayerbe s/n 22880 Canfranc Estaci´on, Huesca, Spain [email protected] Received Day Month Year Revised Day Month Year Experiments looking for rare events like the direct detection of dark matter particles, neutrino interactions or the nuclear double beta decay are operated deep underground to suppress the effect of cosmic rays. But the production of radioactive isotopes in ma- terials due to previous exposure to cosmic rays is an hazard when ultra-low background conditions are required. In this context, the generation of long-lived products by cosmic nucleons has been studied for many detector media and for other materials commonly used. Here, the main results obtained on the quantification of activation yields on the Earth’s surface will be summarized, considering both measurements and calculations following different approaches. The isotope production cross sections and the cosmic ray spectrum are the two main ingredients when calculating this cosmogenic activation; the different alternatives for implementing them will be discussed. Activation that can take place deep underground mainly due to cosmic muons will be briefly commented too. Presently, the experimental results for the cosmogenic production of radioisotopes are scarce and discrepancies between different calculations are important in many cases, but the increasing interest on this background source which is becoming more and more relevant can help to change this situation. -
Sonie Applications of Fast Neutron Activation Analysis of Oxygen
S E03000182 CTH-RF- 16-5 Sonie Applications of Fast Neutron Activation Analysis of Oxygen Farshid Owrang )52 Akadenmisk uppsats roir avliiggande~ av ilosofie ficentiatexamen i Reaktorf'ysik vid Chalmer's tekniska hiigskola Examinator: Prof. Imre PiAst Handledare: Dr. Anders Nordlund Granskare: Bitr. prof. G~iran Nyrnan Department of Reactor Physics Chalmers University of Technology G6teborg 2003 ISSN 0281-9775 SOME APPLICATIONS OF FAST NEUTRON ACTIVATION OF OXYGE~'N F~arshid Owrang Chalmers University of Technology Departmlent of Reactor Physics SEP-1-412 96 G~iteborg ABSTRACT In this thesis we focus on applications of neutron activation of oxygen for several purposes: A) measuring the water level in a laboratory tank, B) measuring the water flow in a pipe system set-up, C) analysing the oxygen in combustion products formed in a modern gasoline S engine, and D) measuring on-line the amount of oxygen in bulk liquids. A) Water level measurements. The purpose of this work was to perform radiation based water level measurements, aimed at nuclear reactor vessels, on a laboratory scale. A laboratory water tank was irradiated by fast neutrons from a neutron enerator. The water was activated at different water levels and the water level was decreased. The produced gamma radiation was measured using two detectors at different heights. The results showed that the method is suitable for measurement of water level and that a relatively small experimental set-up can be used for developing methods for water level measurements in real boiling water reactors based on activated oxygen in the water. B) Water flows in pipe. -
Neutron Capture Cross Sections of Cadmium Isotopes
Neutron Capture Cross Sections of Cadmium Isotopes By Allison Gicking A thesis submitted to Oregon State University In partial fulfillment of the requirements for the degree of Bachelor of Science Presented June 8, 2011 Commencement June 17, 2012 Abstract The neutron capture cross sections of 106Cd, 108Cd, 110Cd, 112Cd, 114Cd and 116Cd were determined in the present project. Four different OSU TRIGA reactor facilities were used to produce redundancy in the results and to measure the thermal cross section and resonance integral separately. When the present values were compared with previously measured values, the differences were mostly due to the kind of detector used or whether or not the samples were natural cadmium. Some of the isotopes did not have any previously measured values, and in that case, new information about the cross sections of those cadmium isotopes has been provided. Table of Contents I. Introduction………………………………………………………………….…….…1 II. Theory………………………………………………………………………...…...…3 1. Neutron Capture…………………………………………………….….……3 2. Resonance Integral vs. Effective Thermal Cross Section…………...………5 3. Derivation of the Activity Equations…………………………………....…..8 III. Methods………………………………………………………….................…...…...12 1. Irradiation of the Samples………………………………………….….....…12 2. Sample Preparation and Parameters………………..………...………..……16 3. Efficiency Calibration of Detectors…………………………..………....…..18 4. Data Analysis…………………………………...…….………………...…..19 5. Absorption by 113Cd……………………………………...……...….………20 IV. Results………………………………………………….……………..……….…….22 -
Determination of Uranium and Thorium by Neutron Activation Analysis Applied to Fossil Samples Dating
2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 DETERMINATION OF URANIUM AND THORIUM BY NEUTRON ACTIVATION ANALYSIS APPLIED TO FOSSIL SAMPLES DATING Regina B. Ticianelli 1, Ana Maria Graciano Figueiredo 1, Guilherme S. Zahn 1, 2,3 2 Angela Kinoshita , Oswaldo Baffa 1 Instituto de Pesquisas Energéticas e Nucleares –IPEN-CNEN/SP, C.P. 11049, 05422-970, São Paulo, SP. [email protected] 2 Departamento de Física, FFCRLP- USP, Ribeirão Preto, SP 3 Universidade Sagrado Coração, Bauru, SP ABSTRACT Electron Spin Resonance (ESR) dating is based on the fact that ionizing radiation can create stable free radicals in insulating materials, like tooth enamel and bones. The concentration of these radicals - determined by ESR - is a function of the dose deposed in the sample along the years. The accumulated dose of radiation, called Archeological Dose, is produced by the exposition to environmental radiation provided by U, Th, K and cosmic rays. If the environmental dose rate in the site where the fossil sample is found is known, it is possible to convert this dose into the age of the sample. The annual dose rate coming from the radioactive elements present in the soil and in the sample itself can be calculated by determining the U, Th and K concentration. Therefore, the determination of the dose rate depends on the concentration of these main radioactive elements. Neutron Activation Analysis has the sensitivity and the accuracy necessary to determine U, Th and K with this objective. -
LENS Report Low Energy Accelerator-Driven Neutron Sources
LENS Report Low Energy Accelerator-driven Neutron Sources LENS Ad-hoc Working Group CANS Nov. 2020 2 www.lens-initiative.org Table of Content 1 Foreword ................................................................................................................................6 2 Executive summary .................................................................................................................8 3 Neutrons for science and industry ......................................................................................... 12 4 Neutron production and landscape of neutron Infrastructures in Europe .............................. 16 4.1 Neutron production ........................................................................................................... 16 4.2 Situation in Europe ............................................................................................................ 16 4.3 Situation outside Europe ................................................................................................... 18 5 Capabilities of CANS .............................................................................................................. 22 5.1 What is a CANS ? ............................................................................................................... 22 5.2 What are the different types of facilities that can be considered? ...................................... 22 5.3 What performances can be achieved on a CANS for neutron scattering ............................. 23 6 Advantages / limitations -
PGNAA (Prompt Gamma Neutron Activation Analysis) Everything You Need to Know About PGNAA (Prompt Gamma Neutron Activation Analysis)
Everything You Need to Know About PGNAA (Prompt Gamma Neutron Activation Analysis) Everything You Need to Know About PGNAA (Prompt Gamma Neutron Activation Analysis) Everything You Need to Know About PGNAA (Prompt Gamma Neutron Activation Analysis) Prompt gamma neutron activation analysis (PGNAA) utilizes neutron sources—such as californium-252 (Cf-252)—to determine the elemental composition of material samples. It is an efficient and effective method of analyzing materials to guide critical decisions regarding extraction operations. The following eBook provides a comprehensive overview of the PGNAA process, including what it is, how it works, what advantages it offers, how and where it is used, and the importance of Cf-252. Phone: 937.376.5691 Email: [email protected] Web: www.frontier-cf252.com 2 Everything You Need to Know About PGNAA (Prompt Gamma Neutron Activation Analysis) What Is PGNAA? PGNAA is a non-contact and non-destructive analytical technique that irradiates a given material sample with a beam of neutrons to determine its elemental makeup. In the coal and cement industries, it is used to obtain information about the composition of material in real time as the coal or cement material moves along the conveyor belt. How Does PGNAA Work? PGNAA uses a strong neutron source (such as Cf-252) to generate a stream of neutrons to bombard the sample material with. This interaction between the neutrons and the sample produces unique prompt gamma rays that are then detected and measured using a high-resolution gamma ray spectrometer. The detector picks up both the energy signatures and intensities emitted by the sample as it stabilizes, allowing it to identify the exact elements and concentrations within the sample. -
Neutron Activation Analysis (DGNAA): Measurement of Gamma-Rays Emitted During the Decay of the Product Nucleus After the Capture Reaction Is Stopped
NEUTRONNEUTRON ACTIVATIONACTIVATION ANALYSISANALYSIS MonicaMonica SistiSisti Università and INFN Milano-Bicocca TheThe techniquetechnique NeutronNeutron activationactivation analysisanalysis (NAA)(NAA) isis aa veryvery sensitivesensitive methodmethod forfor qualitativequalitative andand quantitativequantitative determinationdetermination ofof elementselements basedbased onon thethe measurementmeasurement ofof characteristiccharacteristic radiationradiation fromfrom radionuclidesradionuclides formedformed directlydirectly oror indirectlyindirectly byby neutronneutron irradiationirradiation ofof thethe material.material. ● Multi-element capability ● Sensitivity for many elements The principle is very simple: to be measured Monica Sisti - LRT 2019 2 BriefBrief historyhistory ● After the discovery of the neutron by Chadwick in 1932, neutron activation was first suggested by G. Hevesy and H. Levi in 1936, using a neutron source (226Ra+Be) to measure activated Dy atoms. ● In the first decade of activation analysis, many worked on the measurement of fundamental data of radionuclides, using GM counters and ionization chambers as major instruments. ● In the 1940s, research reactors became an available source of neutrons increasing the fluxes at one's disposal of at least six orders of magnitude. ● The availability of scintillation detectors in the 1950s, the development of semiconductor detectors and multichannel analyzers in the 1960s, and the advent of computers and relevant software in the 1970s, made the nuclear technique an important analytical tool for the determination of many elements at trace level. Monica Sisti - LRT 2019 3 BasicBasic principlesprinciples ofof NAANAA ● A bombarding particle is absorbed by an atomic nucleus after a nuclear reaction. ● A compound nucleus is formed (highly excited, unstable nucleus). ● The compound nucleus de-excites, usually by ejecting a small particle and a product Most common type of nuclear reaction for NAA nucleus. Prompt radiation emitted ~10-14 s after neutron capture. -
28 Neutron Activation Analysis (NAA) Predicting the Sensitivity of Neutron Activation Analysis (NAA)
Neutron Activation and Activation Analysis 11/26/09 1 General 2 General Many nuclear reactions produce radioactive products. The most common of these reactions involve neutrons: Neutron + Target Nuclide → Activation Product 3 General Important Applications/Issues Associated with Neutron Activation 1. Neutron Activation Analysis (NAA) This is an extraordinarily powerful technique for identifying and quantifying various elements (and nuclides) in a sample. 2. Neutron Fluence Rate (Flux) Measurements Neutron fluence rates in reactors or other neutron sources can be measured by exposing targets (e.g., metal foils) to the neutrons and measuring the induced activity. 4 General Important Applications/Issues Associated with Neutron Activation 3. Dosimetry Following Criticality Accidents The induced activity in objects or individuals following a criticality accident can be used to estimate the doses to these individuals. 4. Hazards from Induced Activity Induced radioactivity in the vicinity of intense neutron sources can constitute an exposure hazard. Examples of such sources include reactors, accelerators and, of course, nuclear explosions. 5 General Neutron Capture The most important reaction is neutron capture: Thermal neutrons are most likely to be captured. The target nuclide is usually, but not necessarily stable. If the product is radioactive, it is likely a beta emitter. The gamma ray, referred to as a prompt gamma or capture gamma, is typically of high energy. 6 General Neutron Capture Example: This is an exception to the generalization that the activation product is a beta emitter. Cr-51 decayyys by electron cap ture! The major prompt gamma rays: 749 keV produced 11.0% of the time 8512.1 keV produced 6.16% of the time 8484.0 keV produced 4.54% of the time 7 General Neutron-Proton Reaction Another potentially important reaction is the n-p reaction: The n-p reaction is most likely for fast neutrons and target nuclides with low atomic numbers.