Nuclear Graphite for High Temperature Reactors
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Graphite Materials for the U.S
ANRIC your success is our goal SUBSECTION HH, Subpart A Timothy Burchell CNSC Contract No: 87055-17-0380 R688.1 Technical Seminar on Application of ASME Section III to New Materials for High Temperature Reactors Delivered March 27-28, 2018, Ottawa, Canada TIM BURCHELL BIOGRAPHICAL INFORMATION Dr. Tim Burchell is Distinguished R&D staff member and Team Lead for Nuclear Graphite in the Nuclear Material Science and Technology Group within the Materials Science and Technology Division of the Oak Ridge National Laboratory (ORNL). He is engaged in the development and characterization of carbon and graphite materials for the U.S. Department of Energy. He was the Carbon Materials Technology (CMT) Group Leader and was manager of the Modular High Temperature Gas-Cooled Reactor Graphite Program responsible for the research project to acquire reactor graphite property design data. Currently, Dr. Burchell is the leader of the Next Generation Nuclear Plant graphite development tasks at ORNL. His current research interests include: fracture behavior and modeling of nuclear-grade graphite; the effects of neutron damage on the structure and properties of fission and fusion reactor relevant carbon materials, including isotropic and near isotropic graphite and carbon-carbon composites; radiation creep of graphites, the thermal physical properties of carbon materials. As a Research Officer at Berkeley Nuclear Laboratories in the U.K. he monitored the condition of graphite moderators in gas-cooled power reactors. He is a Battelle Distinguished Inventor; received the Hsun Lee Lecture Award from the Chinese Academy of Science’s Institute of Metals Research in 2006 and the ASTM D02 Committee Eagle your success is our goal Award in 2015. -
The Era of Carbon Allotropes Andreas Hirsch
commentary The era of carbon allotropes Andreas Hirsch Twenty-five years on from the discovery of 60C , the outstanding properties and potential applications of the synthetic carbon allotropes — fullerenes, nanotubes and graphene — overwhelmingly illustrate their unique scientific and technological importance. arbon is the element in the periodic consist of extended networks of sp3- and 1985, with the advent of fullerenes (Fig. 1), table that provides the basis for life sp2 -hybridized carbon atoms, respectively. which were observed for the first time by Con Earth. It is also important for Both forms show unique physical properties Kroto et al.3. This serendipitous discovery many technological applications, ranging such as hardness, thermal conductivity, marked the beginning of an era of synthetic from drugs to synthetic materials. This lubrication behaviour or electrical carbon allotropes. Now, as we celebrate role is a consequence of carbon’s ability conductivity. Conceptually, many other buckminsterfullerene’s 25th birthday, it is to bind to itself and to nearly all elements ways to construct carbon allotropes are also the time to reflect on a growing family in almost limitless variety. The resulting possible by altering the periodic binding of synthetic carbon allotropes, which structural diversity of organic compounds motif in networks consisting of sp3-, sp2- includes the synthesis of carbon nanotubes and molecules is accompanied by a broad and sp-hybridized carbon atoms1,2. As a in 19914 and the rediscovery of graphene range of -
Chemistry with Graphene and Graphene Oxide - Challenges for Synthetic Chemists Siegfried Eigler* and Andreas Hirsch*
Chemistry with Graphene and Graphene Oxide - Challenges for Synthetic Chemists Siegfried Eigler* and Andreas Hirsch* Dr. Siegfried Eigler*, Prof. Dr. Andreas Hirsch* Department of Chemistry and Pharmacy and Institute of Advanced Materials and Processes (ZMP) Henkestrasse 42, 91054 Erlangen and Dr.-Mack Strasse 81, 90762 Fürth (Germany) Fax: (+49) 911-6507865015 E-mail: [email protected]; [email protected] The chemical production of graphene as well as its controlled wet- chemical modification is a challenge for synthetic chemists and the characterization of reaction products requires sophisticated analytic methods. In this review we first describe the structure of graphene and graphene oxide. We then outline the most important synthetic methods which are used for the production of these carbon based nanomaterials. We summarize the state-of-the-art for their chemical functionalization by non-covalent and covalent approaches. We put special emphasis on the differentiation of the terms graphite, graphene, graphite oxide and graphene oxide. An improved fundamental knowledge about the structure and the chemical properties of graphene and graphene oxide is an important prerequisite for the development of practical applications. 1. Introduction: Graphene and Graphene Oxide – Opportunities and Challenges for Synthetic Chemists Research into graphene and graphene oxide (GO) represents an emerging field of interdisciplinary science spanning a variety of disciplines including chemistry, physics, materials science, device fabrication and -
Coal Characteristics
CCTR Indiana Center for Coal Technology Research COAL CHARACTERISTICS CCTR Basic Facts File # 8 Brian H. Bowen, Marty W. Irwin The Energy Center at Discovery Park Purdue University CCTR, Potter Center, 500 Central Drive West Lafayette, IN 47907-2022 http://www.purdue.edu/dp/energy/CCTR/ Email: [email protected] October 2008 1 Indiana Center for Coal Technology Research CCTR COAL FORMATION As geological processes apply pressure to peat over time, it is transformed successively into different types of coal Source: Kentucky Geological Survey http://images.google.com/imgres?imgurl=http://www.uky.edu/KGS/coal/images/peatcoal.gif&imgrefurl=http://www.uky.edu/KGS/coal/coalform.htm&h=354&w=579&sz= 20&hl=en&start=5&um=1&tbnid=NavOy9_5HD07pM:&tbnh=82&tbnw=134&prev=/images%3Fq%3Dcoal%2Bphotos%26svnum%3D10%26um%3D1%26hl%3Den%26sa%3DX 2 Indiana Center for Coal Technology Research CCTR COAL ANALYSIS Elemental analysis of coal gives empirical formulas such as: C137H97O9NS for Bituminous Coal C240H90O4NS for high-grade Anthracite Coal is divided into 4 ranks: (1) Anthracite (2) Bituminous (3) Sub-bituminous (4) Lignite Source: http://cc.msnscache.com/cache.aspx?q=4929705428518&lang=en-US&mkt=en-US&FORM=CVRE8 3 Indiana Center for Coal Technology Research CCTR BITUMINOUS COAL Bituminous Coal: Great pressure results in the creation of bituminous, or “soft” coal. This is the type most commonly used for electric power generation in the U.S. It has a higher heating value than either lignite or sub-bituminous, but less than that of anthracite. Bituminous coal -
A Comparison of Advanced Nuclear Technologies
A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department. -
Molten Salt Chemistry Workshop
The cover depicts the chemical and physical complexity of the various species and interfaces within a molten salt reactor. To advance new approaches to molten salt technology development, it is necessary to understand and predict the chemical and physical properties of molten salts under extreme environments; understand their ability to coordinate fissile materials, fertile materials, and fission products; and understand their interfacial reactions with the reactor materials. Modern x-ray and neutron scattering tools and spectroscopy and electrochemical methods can be coupled with advanced computational modeling tools using high performance computing to provide new insights and predictive understanding of the structure, dynamics, and properties of molten salts over a broad range of length and time scales needed for phenomenological understanding. The actual image is a snapshot from an ab initio molecular dynamics simulation of graphene- organic electrolyte interactions. Image courtesy of Bobby G. Sumpter of ORNL. Molten Salt Chemistry Workshop Report for the US Department of Energy, Office of Nuclear Energy Workshop Molten Salt Chemistry Workshop Technology and Applied R&D Needs for Molten Salt Chemistry April 10–12, 2017 Oak Ridge National Laboratory Co-chairs: David F. Williams, Oak Ridge National Laboratory Phillip F. Britt, Oak Ridge National Laboratory Working Group Co-chairs Working Group 1: Physical Chemistry and Salt Properties Alexa Navrotsky, University of California–Davis Mark Williamson, Argonne National Laboratory Working -
Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options
Order Code RL34579 Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options July 11, 2008 Mark Holt Specialist in Energy Policy Resources, Science, and Industry Division Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options Summary Current U.S. nuclear energy policy focuses on the near-term construction of improved versions of existing nuclear power plants. All of today’s U.S. nuclear plants are light water reactors (LWRs), which are cooled by ordinary water. Under current policy, the highly radioactive spent nuclear fuel from LWRs is to be permanently disposed of in a deep underground repository. The Bush Administration is also promoting an aggressive U.S. effort to move beyond LWR technology into advanced reactors and fuel cycles. Specifically, the Global Nuclear Energy Partnership (GNEP), under the Department of Energy (DOE) is developing advanced reprocessing (or recycling) technologies to extract plutonium and uranium from spent nuclear fuel, as well as an advanced reactor that could fully destroy long-lived radioactive isotopes. DOE’s Generation IV Nuclear Energy Systems Initiative is developing other advanced reactor technologies that could be safer than LWRs and produce high-temperature heat to make hydrogen. DOE’s advanced nuclear technology programs date back to the early years of the Atomic Energy Commission in the 1940s and 1950s. In particular, it was widely believed that breeder reactors — designed to produce maximum amounts of plutonium from natural uranium — would be necessary for providing sufficient fuel for a large commercial nuclear power industry. Early research was also conducted on a wide variety of other power reactor concepts, some of which are still under active consideration. -
Properties and Characteristics of Graphite
SPECIALTY MATERIALS PROPERTIES AND CHARACTERISTICS OF GRAPHITE For the semiconductor industry May 2013 INTRODUCTION Introduction Table of Contents As Entegris has continued to grow its market share of Introduction .............................................................1 manufactured graphite material and to expand their usage into increasingly complex areas, the need to Structure ..................................................................2 be more technically versed in both Entegris’ POCO® graphite and other manufactured graphite properties Apparent Density .....................................................6 and how they are tested has also grown. It is with this Porosity ....................................................................8 thought in mind that this primer on properties and characteristics of graphite was developed. Hardness ................................................................11 POCO, now owned by Entegris, has been a supplier Compressive Strength .............................................12 to the semiconductor industry for more than 35 years. Products include APCVD wafer carriers, E-Beam cruci- Flexural Strength ...................................................14 bles, heaters (small and large), ion implanter parts, Tensile Strength .....................................................16 LTO injector tubes, MOCVD susceptors, PECVD wafer trays and disk boats, plasma etch electrodes, quartz Modulus of Elasticity .............................................18 replacement parts, sealing -
Graphene: a Peculiar Allotrope of Carbon
Graphene: A Peculiar Allotrope Of Carbon Laxmi Nath Bhattarai Department of Physics, Butwal Multiple Campus Correspondence: [email protected] Abstract Graphene is a two dimensional one atom thick allotrope of Carbon. Electrons in grapheme behave as massless relativistic particles. It is a 2 dimensional nanomaterial with many peculiar properties. In grapheme both integral and fractional quantum Hall effects are observed. Many practical application are seen from use of Graphene material. Keywords: Graphene, allotrope, Quantum Hall effect, nanomaterial. Introduction Graphene is a two dimensional allotropic form of Honey comb structure of Graphene carbon. This was discovered in 2004. Diamond and Graphene is considered as the mother of all graphitic Graphite are three dimensional allotropes of carbon materials because it is the building block of carbon which are known from ancient time. One dimensional materials of all other dimensions (Srinivasan, 2007). carbon nanotubes were discovered in 1991 and Griphite is obtained by the stacking of Graphene zero dimensional Fullerenes were discovered in layers, Diamond can be obtained from Graphene under 1985. Graphene was experimentally extracted from extreme pressure and temperatures. One-dimensional 3-dimensional Graphite by Physisists Andre Geim and carbon nanotubes can be obtained by rolling and Konstantin Novoselov of Manchester University UK Zero–dimensional Fullerenes is obtained by wrapping in 2004. For their remarkable work they were awarded Graphene layers. the Nobel Prize of Physics for the year 2010. Properties Structure The young material Graphene is found to have Graphene is a mono layer of Carbon atoms packed following unique properties: into a honeycomb crystal structure. Graphene sheets 2 are one atom thick 2-dimensional layers of sp – bonded a) It is the thinnest material in the universe and the carbon. -
Preliminary Core Design Studies for the Advanced Burner Reactor Over a Wide Range of Conversion Ratios
ANL-AFCI-177 Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios Nuclear Engineering Division About Argonne National Laboratory Argonne is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory’s main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne, see www.anl.gov. Availability of This Report This report is available, at no cost, at http://www.osti.gov/bridge. It is also available on paper to the U.S. Department of Energy and its contractors, for a processing fee, from: U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 phone (865) 576-8401 fax (865) 576-5728 [email protected] Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor UChicago Argonne, LLC, nor any of their employees or officers, makes any warranty, express 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. Reference 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 United States Government or any agency thereof. The views and opinions of document authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof, Argonne National Laboratory, or UChicago Argonne, LLC. -
Small Modular Reactors – Key to Future Nuclear Power Generation in the U.S.1,2
Small Modular Reactors – Key to Future Nuclear Power Generation in the U.S.1,2 Robert Rosner and Stephen Goldberg Energy Policy Institute at Chicago The Harris School of Public Policy Studies Contributor: Joseph S. Hezir, Principal, EOP Foundation, Inc. Technical Paper, Revision 1 November, 2011 1 The research described in this paper was funded by the U.S. DOE through Argonne National Laboratory, which is operated by UChicago Argonne, LLC under contract No. DE-AC02-06CH1357. This report was prepared as an account of work sponsored by the United States Department of Energy. Neither the United States Government nor any agency thereof, nor the University of Chicago, nor any of their employees or officers, makes any warranty, express 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. Reference 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 United States Government or any agency thereof. The views and opinions of document authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof, Argonne National Laboratory, or the institutional opinions of the University of Chicago. 2 This paper is a major update of an earlier paper, July 2011. This -
Fundamentals of Nuclear Power
Fundamentals of Nuclear Power Juan S. Giraldo Douglas J. Gotham David G. Nderitu Paul V. Preckel Darla J. Mize State Utility Forecasting Group December 2012 Table of Contents List of Figures .................................................................................................................................. iii List of Tables ................................................................................................................................... iv Acronyms and Abbreviations ........................................................................................................... v Glossary ........................................................................................................................................... vi Foreword ........................................................................................................................................ vii 1. Overview ............................................................................................................................. 1 1.1 Current state of nuclear power generation in the U.S. ......................................... 1 1.2 Nuclear power around the world ........................................................................... 4 2. Nuclear Energy .................................................................................................................... 9 2.1 How nuclear power plants generate electricity ..................................................... 9 2.2 Radioactive decay .................................................................................................