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Thermal Transport in Thorium Dioxide Nuclear Engineering and Technology
Nuclear Engineering and Technology 50 (2018) 731e737 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: www.elsevier.com/locate/net Original Article Thermal transport in thorium dioxide Jungkyu Park*, Eduardo B. Farfan, Christian Enriquez Kennesaw State University, Department of Mechanical Engineering, Kennesaw, GA 30144, USA article info abstract Article history: In this research paper, the thermal transport in thorium dioxide is investigated by using nonequilibrium Received 28 September 2017 molecular dynamics. The thermal conductivity of bulk thorium dioxide was measured to be 20.8 W/m-K, Received in revised form confirming reported values, and the phonon mean free path was estimated to be between 7 and 8.5 nm 20 December 2017 at 300 K. It was observed that the thermal conductivity of thorium dioxide shows a strong dependency Accepted 12 February 2018 on temperature; the highest thermal conductivity was estimated to be 77.3 W/m-K at 100 K, and the Available online 1 March 2018 lowest thermal conductivity was estimated to be 4.3 W/m-K at 1200 K. In addition, by simulating thorium dioxide structures with different lengths at different temperatures, it was identified that short Keywords: Molecular Dynamics Simulation wavelength phonons dominate thermal transport in thorium dioxide at high temperatures, resulting in Nuclear Fuel decreased intrinsic phonon mean free paths and minimal effect of boundary scattering while long Thermal Transport wavelength phonons dominate the thermal transport in thorium dioxide at low temperatures. Thorium Dioxide © 2018 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/). -
INFORMATION O a a .Aoi Chemistry-Traniuranie Elements
INFORMATION o a a .aoi Chemistry-Traniuranie Elements UNIVERSITY O r CALIFORNIA Radiation Laboratory Contract No. W-7405-eng~48 CUBSITIClTIOH CAKCBLUD IV. TT Ftv«Jbs Itti'.s fJ«cR'otsdLisV^ CRYSTAL STRUCTURES OF AMERICIUM COMPOUNDS D. H. Templeton and Carol H. Dauben February 3, 1953 RESTRICTEO^JCTA This document cqpm pLrw ricted data as defined in ttagSrarfic Energy Act of 1944. Its tsn fip rtfa l or disclosure of Its contents ^p*ny manner to an unautor- ised person is prohibited. Berkeley, California UNIVERSITY Of CALIFORNIA Rodiotiofl Loborotory 42RC8 Cover Shoot INDE X NO. Ill K£ ■ -10/ Do not rsrtovt Tbit document eo nto in t__ IL- pages Tbit is copy ^ of tor lot tL Glassification Eoch perton who rtcoivot thltdocument must tipn the cover thstt I Route to Notsd by Date Route to Noted by D aft OHO A im *[|S 5(M) CRYSTAL STRUCTURES OF AMERICIUM COMPOUNDS1 D. H. Templeton and Carol H. Dauben Department of Chemistry and Radiation Laboratory University of California, Berkeley, California February 3, 1953 ABSTRACT The crystal structures of several compounds of americium, element 95, have been determined by the X-ray powder diffraction method. AisF^ is hexagonal (LaF^ type) with a = 4. 067 t 0.001 X and c « 7. 225 t 0.002 Si for the pseudoceil which explains the powder data. AmO^ is cubic (CaF^ type) with 1 a = 5. 38) t 0.001 X AmOCl is tetragonal (PbFCl type) with a = 4.00+O.OlX, c = 6.78 t 0.01 X. The metal parameter la 0.18 t 0.01. -
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. -
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. -
Subject Index
SUBJECT INDEX Vol. 1: 1–698, Vol. 2: 699–1395, Vol. 3: 1397–2111, Vol. 4: 2113–2798, Vol. 5: 2799–3440. Page numbers suffixed by t and f refer to Tables and Figures respectively. Absorption spectra in aqueous solution, 752–770 of americium, 1364–1368 compounds of, 721–752 americium (III), 1364–1365, 1365f coordination complexes in solution, americium (IV), 1365 771–782 americium (V), 1366, 1367f history of, 699–700 americium (VI), 1366, 1367f isotope production, 702–703 americium (VII), 1367–1368, 1368f metallic state of, 717–721 of liquid plutonium, 963 in nature, 703–704 of neptunium, 763–766, 763f, 786–787 nuclear properties of, 700–702 neptunium (VII) ternary oxides, 729 separation and purification, 704–717 of plutonium plutonium hexafluoride, 1088, 1089f atomic properties of, 857–862 ions, 1113–1117, 1116t compounds of, 987–1108 plutonium (IV), 849 metal and intermetallic compounds of, polymerization, 1151, 1151f 862–987 tetrachloride, 1093–1094, 1094f natural occurrence of, 822–824 tribromide, 1099t, 1100 nuclear properties of, 815–822 trichloride, 1099, 1099t separation and purification of, 826–857 Accelerator mass spectrometry (AMS), of solution chemistry of, 1108–1203 neptunium, 790 Actinide elements Acetates atomic volumes of, 922–923, 923f of americium, 1322, 1323t extraction of of plutonium, 1177, 1180 DIDPA, 1276 Acetone, derived compounds, of americium, HDEHP, 1275 1322, 1323t, 1324 organophosphorus and Acids carbamoylphosphonate reagents, for Purex process, 711 1276–1278 for solvent extraction, 839 stripping of, 1280–1281 Actinide -
Electrical Characterization of Crystalline UO 2 , Tho 2 and U
Air Force Institute of Technology AFIT Scholar Theses and Dissertations Student Graduate Works 12-17-2018 Electrical Characterization of Crystalline UO2, ThO2 AND U0.71Th0.29O2 Christina L. Dugan Follow this and additional works at: https://scholar.afit.edu/etd Part of the Engineering Physics Commons Recommended Citation Dugan, Christina L., "Electrical Characterization of Crystalline UO2, ThO2 AND U0.71Th0.29O2" (2018). Theses and Dissertations. 1944. https://scholar.afit.edu/etd/1944 This Dissertation is brought to you for free and open access by the Student Graduate Works at AFIT Scholar. It has been accepted for inclusion in Theses and Dissertations by an authorized administrator of AFIT Scholar. For more information, please contact [email protected]. ELECTRICAL CHARACTERIZATION OF CRYSTALLINE UO2, THO2 AND U0.71TH0.29O2 DISSERTATION Christina L. Dugan, Lieutenant Colonel, USA AFIT-ENP-DS-18-D-007 DEPARTMENT OF THE AIR FORCE AIR UNIVERSITY AIR FORCE INSTITUTE OF TECHNOLOGY Wright-Patterson Air Force Base, Ohio DISTRIBUTION STATEMENT A Approved For Public Release; Distribution Unlimited The views expressed in this thesis are those of the author and do not reflect the official policy or position of the United States Air Force, the Department of Defense, or the United States Government. AFIT-ENP-DS-18-D-007 ELECTRICAL CHARACTERIZATION OF CRYSTALLINE UO2, THO2 AND U0.71TH0.29O2 DISSERTATION Presented to the Faculty Department of Engineering Physics Graduate School of Engineering and Management Air Force Institute of Technology Air University Air Education and Training Command In Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy Christina L. -
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 -
Instrumental Neutron Activation Analysis (INAA)
Instrumental Neutron Activation Analysis (INAA) Overview: Unlike most analytical techniques INAA requires no chemical processing of the samples, therefore it is described as Instrumental NAA rather than radiochemical NAA. This characteristic has several advantages: (1) Rapid, i.e., less labor required to prepare samples. (2) Precludes the possibility of contaminating the samples. As shown in Fig. 1 (Periodic Table), in terrestrial sediments INAA typically obtains precise abundance data (i.e. duplicate analyses agree within 5%) for many elements, typically occurring as trace elements in the parts per million (by weight) range. The concept of INAA is to produce radioactive isotopes by exposing the samples to a high flux of neutrons in a nuclear reactor. These isotopes typically decay by beta decay and in the process gamma rays (electromagnetic radiation) with discrete energies are emitted). These discrete energies are the fingerprint for an isotope. Note that this technique determines abundance of isotopes, but because isotopic abundances of most, at least high atomic number, elements are constant in natural materials, isotopic abundance is readily translated to elemental abundances. Gamma rays arise from transitions between nuclear energy levels whereas X-rays arise from transitions between electron energy levels. An advantage of gamma rays is that many are much more energetic than X-rays; therefore gamma rays are less readily absorbed and matrix corrections (see lecture on electron microprobe) are not usually important. 1 Periodic Table -
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.