Nuclear Science and Technology for Ceramics
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Anion Vacancies As a Source of Persistent Photoconductivity in II-VI and Chalcopyrite Semiconductors
PHYSICAL REVIEW B 72, 035215 ͑2005͒ Anion vacancies as a source of persistent photoconductivity in II-VI and chalcopyrite semiconductors Stephan Lany and Alex Zunger National Renewable Energy Laboratory, Golden, Colorado 80401, USA ͑Received 13 January 2005; revised manuscript received 12 April 2005; published 18 July 2005͒ Using first-principles electronic structure calculations we identify the anion vacancies in II-VI and chalcopy- rite Cu-III-VI2 semiconductors as a class of intrinsic defects that can exhibit metastable behavior. Specifically, ͑ ͒ we predict persistent electron photoconductivity n-type PPC caused by the oxygen vacancy VO in n-ZnO, originating from a metastable shallow donor state of VO. In contrast, we predict persistent hole photoconduc- ͑ ͒ tivity p-type PPC caused by the Se vacancy VSe in p-CuInSe2 and p-CuGaSe2. We find that VSe in the chalcopyrite materials is amphoteric having two “negative-U”-like transitions, i.e., a double-donor transition ͑2+/0͒ close to the valence band and a double-acceptor transition ͑0/2−͒ closer to the conduction band. We introduce a classification scheme that distinguishes two types of defects: type ␣, which have a defect-localized- state ͑DLS͒ in the band gap, and type , which have a resonant DLS within the host bands ͑e.g., the conduction band for donors͒. In the latter case, the introduced carriers ͑e.g., electrons͒ relax to the band edge where they can occupy a perturbed-host state. Type ␣ is nonconducting, whereas type  is conducting. We identify the neutral anion vacancy as type ␣ and the doubly positively charged vacancy as type . -
State-Of-The-Art Report on Structural Materials Modelling
Nuclear Science NEA/NSC/R(2016)5 May 2017 www.oecd-nea.org State-of-the-art Report on Structural Materials Modelling State-of-the-art Report on Structural Materials Modelling ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 35 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, Chile, the Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Israel, Italy, Japan, Korea, Latvia, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The European Commission takes part in the work of the OECD. OECD Publishing disseminates widely the results of the Organisation’s statistics gathering and research on economic, social and environmental issues, as well as the conventions, guidelines and standards agreed by its members. NUCLEAR ENERGY AGENCY The OECD Nuclear Energy Agency (NEA) was established on 1 February 1958. Current NEA membership consists of 31 countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, Norway, Poland, Portugal, Russia, the Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. -
WASH-1097.Pdf
WASH 1097 UC-80 THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969 PREPARED BY Brookhaven National Laboratory AND THE Division of Reactor Development and Technology WITH THE ASSISTANCE OF ARGONNE NATIONAL LABORATORY BABCOCK & WILCOX GULF GENERAL ATOMIC OAK RIDGE NATIONAL LABORATORY PACIFIC NORTHWEST LABORATORY For sale by the Superintendent of Documents, U.S. Government Printing Office Washington, D.C. 20402 - Price $1.25 FOREWORD This report on "The Use of Thorium in Nuclear Power Reactors" was prepared under the direction of the Division of Reactor Development and Technology, U.S.A.E.C., as part of an overall assessment of the Civilian Nuclear Power Program initiated in response to a request in 1966 by the Joint Committee on Atomic Energy. It represents the results of the inquiry by the Thorium Systems Task Force whose membership included representatives of Babcock & Wilcox Company, Gulf General Atomic Company, the Argonne National Laboratory, the Brookhaven National Laboratory, the Oak Ridge National Laboratory, the Pacific Northwest Laboratory, and the U.S. Atomic Energy Commission. Publication of this report, which provides information basic to the AEC reactor development program, completes one phase of the evaluation effort outlined in the 1967 Supplement to the 1962 Report to the President on Civilian Nuclear Power, issued in February 1967. The 1967 Supplement outlined changes since 1962 in the technical, economic and resource picture and provided background for further study. Specifically, this report represents the consensus of the task force on the potential use of the thorium cycle and the specific thorium fueled reactor designs which have been proposed. -
Eighth World Conference on Nondestructive Testing Huitieme Conference Moiudiale Sur Les Essais Non Destructifs
./ 1ÍOIS_ UJ._ EIGHTH WORLD CONFERENCE ON NONDESTRUCTIVE TESTING HUITIEME CONFERENCE MOIUDIALE SUR LES ESSAIS NON DESTRUCTIFS A NONDESTRUCTIVE EXAMINATION PROGRAM FOR UNCLAD CARBON-COMPOSITE REACTOR FUEL ELEMENTS UN PROGRAMME D'KSSAIS NON DESTRUCTIFS POUR LES ELEMENTS COMBUSTIBLES DE REACTEUR NON GAINÊS EN COMPOSITE DU CARBONE FULLBRIGHT H. J. LOS ALAMOS, NEW MEXICO LOS ALAMOS SCIENTIFIC LABORATORY U. S. A. SUMMARY- ^ non<lestructive testing program for the examination of (U,Zr)C—C reactor fuel elements is described. RESUME :O n décrit un programme d'essais non destructifs pour examiner les elements combustibles de réacteur en (U.Zr)C-C. I. INTRODUCTION The Los Alamos Scientific Laboratory has been active for the past twenty years in the development and testing of graphitic-based high temperature reactor fuel elements. The initial involvement was in the field of nuclear propulsion systems. Project Rover began as a program to develop a nuclear-powered, hydrogen-propelled rocket engine. The target exhaust temperature of the propellant was about 2775 K. The fuel element for such an engine would have to maintain its integrity and strength at higher temperatures and would have to resist currosion by the hot hydrogen gas, which is very reactive. These constraints limited the choice of materials to a very few. Carbon melts above about 3800 K, has excellent high-tenperature strength, and is not a strong neutron absorber. It is very reactive to high temperature hydrogen. The basic fuel element foi the Rover Program became uranium-loaded graphite. The enriched uranium fuel was incorporated into the graphite matrix as uranium oxide, later as py- rolytic-carbon coated uranium dicarbide inicrospheres, and, aosf recently, as a solid solution of uranium carbide and zirconium carbide. -
Study on Vacancy Defect Concentration and Hybrid Potential of Metal-Based Epitaxial Graphene with Temperature
Study on Vacancy Defect Concentration and Hybrid Potential of Metal-based Epitaxial Graphene with Temperature J H Gao, W Liu*, X X Ren and R L Zheng Engineering Research Center of New Energy Storage Devices and Applications, Chongqing Chongqing University of Arts and Sciences, Chongqing 402160, P. R.China Corresponding author and e-mail: W Liu, [email protected] Abstract. This paper investigates the variation of the vacancy defect concentration and hybrid potential of copper and nickel - based epitaxial graphene with temperature by considering the existence of vacancy defects. Moreover, we discuss the impact of atomic non - harmonic vibration on the metal - based epitaxial graphene. First, the concentration of vacancy defects increases nonlinearly with increasing temperature, and the changing rate of the vacancy defect concentration of the metal-based epitaxial graphene with temperature is smaller than that of graphene; Second, the hybrid potential increases with increasing temperature, but not much; Third, the hybrid potential is independent of temperature without considering the atomic non-harmonic vibration which has an important influence on the vacancy defect concentration and the hybrid potential. The higher the temperature is, the more significant the non-harmonic effects are. 1. Introduction Epitaxial graphene has attracted the attention of researchers worldwide for its application prospect [1-4]. Conductivity is one of the most widely used and most important properties. Beside the experimental research, many literatures have studied the conductivity of epitaxial graphene. In 2013, Z Z Alisultanov studied the electrical conductivity of electron gas on metal-based and semiconductor-based epitaxial graphene in Ref. [5]. In 2015, the variation of electrical conductivity with temperature and thickness of little layer graphene and graphene nanosheets were studied, indicating that the electrical conductivity gradually decreased with increasing temperature in Ref. -
Point Defects in Aln and Al-Rich Algan from First Principles
ABSTRACT HARRIS, JOSHUA SIMON. Point Defects in AlN and Al-rich AlGaN from First Principles. (Under the direction of Douglas L. Irving.) Point defects and defect complexes in AlN and Al-rich AlGaN have been investigated using ab initio density functional theory (DFT) in three separate but related projects. First, oxygen and silicon defects in Al0.65Ga0.35N were examined using explicit random alloy sim- 1 ulations. The O−N acceptor was found to relax into one of many DX configurations, with formation energies strongly dependent on local chemistry. Trends in the formation ener- gies were identified and explained with simple arguments involving cation-oxygen bonds. +1 +1 ON and SiIII were found to relax into on-site configurations with little variation in forma- tion energies. Second, DFT simulations were used to explain the experimentally observed “compensation knee” in Si-doped AlN (whereby the Si donor becomes an acceptor at high doping levels). VAl + nSiAl complexes were demonstrated to be the key to a mechanistic understanding of the compensation knee. Using a Grand Canonical charge balance solver, the compensation knee was qualitatively reproduced from the results of DFT simulations. Additionally, a shift in optical emissions was predicted for the high and low doping limits, which was confirmed by photoluminescence measurements. Finally, phonon and thermal strain simulations were used to investigate the temperature-dependent properties of bulk AlN and common point defects in AlN (Si, O, C, and vacancies). A number of general trends were identified in finite-temperature properties which are common to all or many of the defects under study. -
Quantities of Fissile Materials in US and Soviet
Quantities of Fissile Materials in --US and Soviet ~uclearWeapons Arsenals * Frank von Hippel David H. ~lbri~ht+ Barbara G. Levi PU/CEES Report No. 168 July 1986 * Also Woodrow Wilson School of Public and International Affairs, Princeton University . + Also Federation of American Scientists, 307 Massachusetts Ave. N.E., Washington, DC 20002. Center for Energy and Environmental Studies The Engineering Quadrangle Princeton University Princeton, NJ 08544 TABLE OF CONTENTS a I. INTRODUCTION 11. US STOCKPILE OF WEAPON-GRADE URANIUM 111. US STOCKPILE OF WEAPON-GRADE PLUTONIUM a IV. DISPOSITION OF THE US GOVERNMENT'S STOCKPILE OF NATURAL URANIUM V. SOVIET STOCKPILE OF PLUTONIUM I. INTRODUCTION --TABLE OF CONTENTS History of the Proposal to Cut Off the Production of Fissile Material for Nuclear Weapons a The Verifiability of a Fissile Cutoff The Importance of Knowing the Amounts of Fissile Materials Already in the Nuclear Arsenals 2 REFERENCES Table 1-1. The Amounts of Fissile Material in the US Weapons Stockpile and An Upper-Bound Estimate of the Amount of Separated Plutonium in the USSR I. INTRODUCTION History of the Proposal to Cut Off the Production -of Fissile Material for Nuclear Weapons Although the original nuclear weapons control proposals such as the 1946 Baruch Plan - focused on the control of nuclear weapons materials, recent arms control negotiations have focused principally on the control of long-range nuclear weapons delivery systems. This has been in part due to the shift in the focus of the nuclear arms race from the quantitative to the qualitative. In part also it resulted from the Soviet Union's reluctance to allow intrusive verification arrangements. -
Ultra High Temperature Reactor Critical Experiment (Ucx) Safety Analysis Report
r-- Cs ‘iA-:279 CL-I 4 FIE~ORT COLLECTION IREYRODUCTIQN COPY LOS ALAMOS SCIENTIFIC LABORATORY LOS ALAMOS of the ~ NEW MEXICO University of California ULTRA HIGH TEMPERATURE REACTOR CRITICAL EXPERIMENT (UCX) SAFETY ANALYSIS REPORT J— UNITED STATES ATOMIC ENERGY COMMISSION CONTRACT W-7405 -ENG. 36 ,— LEGAL NO TIC E-I This report was prepared as an account of Government sponsored work. Neither the United States, nor the Commission, nor any person acting on behalf of the Commission: A. Makea any warranty or representation, expressed or implied, with respect to the accu- racy, completeness, or usefulness of tbe information contatned in this report, or that the use of any information, apparatus, method, or process disclosed In this report may not Infringe privately owned rights; or B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of any information, apparatus, method, or process disclosed in this report. As used in the above, “person acttng on behalf of the Commission” includes any em- ployee or contractor of the Commission, or employee of such contractor, to the extent that such employee or contractor of the Commission, or employee of such contractor prepares, disseminates, or provides access to, any information pursuant to his employment or contract with the Commteeion, or MS employment with such contractor. Printed in USA. Price $4.00. Availablefrom the Clearinghousefor Federal Scientific and Technical Information, NationalBureau of Standards, U. S. Department of Commerce, Springfield,Virginia LA-3279 UC-80, REACTOR TECHNOLOGY TID-4500 (38thEd.) LOS ALAMOS SCIENTIFIC LABORATORY LOS ALAMOS of the> NEW MEXICO University of California Report written: March 1965 Report distributed:March 31, 1965 ULTRA HIGH TEMPERATURE REACTOR CRITICAL EXPERIMENT (UCX) SAFETY ANALYSIS REPORT Prepared By K-Division o 9 I AESTRACT The UHTREX Critical Experiment uses the core, reflector, fuel elements, and control rod materials of UHTREX to produce data for the verification of nuclear design calculations. -
Nuclear Fuels and Reprocessing Technologies: a US Perspective
INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective March 2021 Guy Fredrickson Tae-Sic Yoo DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective Guy Fredrickson Tae-Sic Yoo March 2021 Idaho National Laboratory Pyrochemistry & Molten Salt Systems Department Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 Page intentionally left blank ABSTRACT Reprocessing and/or waste management issues are of concern to the “back end” of the nuclear fuel cycle. Of course, there are a great many “nuclear fuel cycle” scenarios to consider; if not in practice, then at least in theory. The simplest conceptually is the “once through” fuel cycle in which the spent fuel is discarded. -
NRC Collection of Abbreviations
I Nuclear Regulatory Commission c ElLc LI El LIL El, EEELIILE El ClV. El El, El1 ....... I -4 PI AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service Include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. -
Crystal Imperfections-- Point, Line and Planar Defect
CRYSTAL IMPERFECTIONS: Introduction After studying the basics of crystallography, we arrived on one of the most important topics named Crystal Imperfection. Here we will be discussing the dimensional imperfection we encounter and its subtopics like the need to study, the cause behind the imperfection and the types of Imperfection we come across in a solid. We know about a crystal and its characteristics. And we also know that behind the ideality of theories in science, there is a reality of application in the true world. And in this topic, we will be encountering the reality. So, I will be defining an ideal crystal on the basis of facts provided to us till now. IDEAL CRYSTAL = Lattice + Motif An atom or group of 3 -D periodic atoms associated with each lattice arrangement of points Fig. 3-d representation of crystal of common salt The deviations we encounter in this set of ideal crystal, are termed as Defects or Imperfections. DEFINITION- Deviations in the regular geometrical arrangement of the atoms in a crystalline solid. Causes There can be a number of wanted and unwanted causes behind the defects that appear in a solid. Some are mentioned below: 1 .Deformation of solids (Alteration in size or shape of a body under the influence of mechanical forces) 2 3 4 .Rapid cooling from high temperature. .Crystallisation occurring at a differed rate. .High-energy radiation striking the solid. These reasons influence the mechanical, electrical, and optical behaviour of a crystal or a solid. Healthy Imperfections When we come across the word “Imperfection”, we assume that the thing for which this adjective is used is not perfect or worse than the perfect one. -
Vacancy Defect Positron Lifetimes in Strontium Titanate
1 Vacancy defect positron lifetimes in strontium titanate R.A. Mackie,1 S. Singh,1 J. Laverock, 2 S.B. Dugdale,2 and D.J. Keeble1,* 1Carnegie Laboratory of Physics, School of Engineering, Physics, and Mathematics, University of Dundee, Dundee DD1 4HN, UK 2 H.H. Wills Physics Laboratory, University of Bristol, Tyndall Avenue, Bristol BS8 1TL, UK *Corresponding author. Electronic address: [email protected] The results of positron annihilation lifetime spectroscopy measurements on undoped, electron irradiated, and Nb doped SrTiO3 single crystals are reported. Perfect lattice and vacancy defect positron lifetimes were calculated using two different first-principles schemes. The Sr vacancy defect related positron lifetime was obtained from measurements on Nb doped, electron irradiated, and vacuum annealed samples. Undoped crystals showed a defect lifetime component dominated by trapping to Ti vacancy related defects. 2 I. INTRODUCTION Vacancies are normally assumed to be the dominant point defects in perovskite oxide (ABO3) titanates, and often strongly influence the material properties such as electrical conductivity and domain stability and dynamics.1, 2 Strontium titanate is one of the most widely studied oxide materials, having a model cubic perovskite oxide structure at room temperature and exhibits an antiferrodistortive phase transition at 105 K. The material is a 0 3 wide band gap semiconductor (with Eg = 3.3 eV, ) but can be made a good conductor by 4 doping, for example, with Nb. Single crystal SrTiO3 substrates are readily available, and high quality epitaxial layers can be grown.5-7 The recent observation of two-dimensional 8 electron gas formation at the interface between SrTiO3 and LaAlO3, residing in the SrTiO3, has further demonstrated the importance of the material for future 9 multifunctional oxide electronic device structures.