Materials for Nuclear Industry: Some Historical Perspectives
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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. -
Cosmic Search Issue 06
North American AstroPhysical Observatory (NAAPO) Cosmic Search: Issue 6 (Volume 2 Number 2; Spring (Apr., May, June) 1980) [All Articles & Miscellaneous Items] Webpage Table of Contents (Bookmarks) (Internal links to items in this webpage) [Note. Use Back button (or <Alt>+<Left Arrow>) to get back to this Table of Contents after you have clicked on a link and viewed the article.] Codes Used Below: P: Starting page of article in magazine; A: Author(s); T: Title of article P: 2; A: Bruce E. Fleury; T: The Aliens In Our Oceans: Dolphins As Analogs P: 6; A: George H. Brown; T: Marconi P: 9; A: Editors; T: Letters P: 10; A: John Kraus; T: Editorial: Technology and the Future of Our Civilization P: 11; A: Editors; T: Space Happenings P: 12; A: Mirjana Gearhart; T: Off the Shelf P: 13; A: I. J. (Irving John "Jack") Good; T: The Chief Entities P: 17; A: Mirjana Gearhart; T: In Review: P: 18; A: Jill Tarter; T: Communication with Extraterrestrial Intelligence P: 19; A: Jill Tarter; T: Life in the Universe P: 20; A: Virginia Trimble; T: Where Are They? P: 26; A: G. Harry Stine; T: Space Industrialization: Opportunity for Space Science P: 30; A: Don Lago; T: In the Time Machine P: 32; A: John Kraus; T: ABCs of Space P: 38; A: Editors; T: College Courses on "Life in the Universe" P: 40; A: Vernon Pankonin; T: Allocating the Radio Spectrum P: 44; A: Robert S. Dixon; T: The SEnTInel (SETI News) P: various; A: Editors; T: Miscellaneous: Information from the Editors, Quotes & Graphics The Aliens In Our Oceans: Dolphins As Analogs By: Bruce E. -
Atomic Health News Is Now Available Through Email
VOLUME 4, EDITION 2 Claim Denied, But Former Atomic Worker Does Not Give Up “I saw the ash,” recalled Ross, a and said, ‘move everything o the former Electronic Technician at shelves and onto the oor.’ ey Nevada Test Site. “en came the didn’t want anything to fall o and ground waves. It felt like I was break because of the blast.” standing in the middle of the ocean with waves all around.” Ross experienced many once-in-a-lifetime events while Ross recalled one of his experiences working at both Nevada Test Site and aer a nuclear weapon was detonated Idaho National Lab. Unfortunately, underground at the Nevada Test Site, while working at these sites, Ross also where he worked from 1965-1968. experienced exposure to toxic Ross holds his DOL benets card he received chemicals and radiation. Several years from self-ling. Nuclear Care Partners is “ey came in to the equipment trailer ago, Ross was diagnosed with thyroid now providing Ross with guidance on how to add his other conditions to his card. CONTINUED ON PAGE 2... NCP ATOMIC SITE FOCUS AMES LABORATORY A Historical Highlight of One of the Many Nuclear Weapons Facilities Across the Nation e discovery of nuclear ssion in program to accompany the Manhattan 1939 led to advanced research of Project’s existing physics program. e uranium and other rare radioactive Ames Project, as it came to be known, was elements and isotopes. In 1942, Frank responsible for producing high purity Spedding of Iowa State College, an uranium from uranium ores. e Ames expert in the chemistry of rare earth Project group, led by chemist Harley A. -
The Rare Earths II
Redis co very of the Elements The Ra re Earth s–The Con fusing Years I A gallery of rare earth scientists and a timeline of their research I I James L. Marshall, Beta Eta 1971 , and Virginia R. Marshall, Beta Eta 2003 , Department of Chemistry, University of North Texas, Denton, TX 76203-5070, [email protected] The rare earths after Mosander. In the pre - vi ou s HEXAGON “Rediscovery” article, 1p we were introduced to the 17 rare earths, found in the f-block and the Group III chemical family of Figure 1. Important scientists dealing with rare earths through the nineteenth century. Johan Gadolin the Periodic Table. Because of a common (1760 –1852) 1g —discovered yttrium (1794). Jöns Jacob Berzelius (1779 –1848) and Martin Heinrich valence electron configuration, the rare earths Klaproth (1743 –1817) 1d —discovered cerium (1803). Carl Gustaf Mosander (1787 –1858) 1p —discovered have similar chemical properties, and their lanthanum (1839), didymium (1840), terbium, and erbium (1843). Jean-Charles deGalissard Marignac chemical separation from one another can be (1817 –1894) 1o —discovered ytterbium (1878) and gadolinium (1880). Per Teodor Cleve (1840 –1905) 1n — difficult. From preparations of the first two rare discovered holmium and thulium (1879). Lars Fredrik Nilson (1840 –1899) 1n —discovered scandium earth element s—yttrium and ceriu m—the (1879). Paul-Émile Lecoq de Boisbaudran (1838 –1912) —discovered samarium (1879) and dysprosium Swedish chemist Carl Gustaf Mosander (Figure (1886). 1b Carl Auer von Welsbach (1858 –1929) 1c —discovered praseodymium and neodymium (1885); 1, 2) was able to separate four additional ele - co-discovered lutetium (1907). -
ORAU TEAM Dose Reconstruction Project for NIOSH
ORAU TEAM Dose Reconstruction Project for NIOSH Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation Page 1 of 84 Document Title: Document Number: ORAUT-TKBS-0055 Revision: 00 Site Profile for Ames Laboratory Effective Date: 06/22/2007 Type of Document TBD Supersedes: None Subject Expert(s): Jerome B. Martin, Dillard B. Shipler, Donald E. Bihl, Eva E. Hickey, and Bruce A. Napier Site Expert(s): N/A Approval: Signature on File Approval Date: 06/11/2007 Jerome B. Martin, Document Owner Concurrence: Signature on File Concurrence Date: 06/08/2007 John M. Byrne, Task 3 Manager Concurrence: Signature on File Concurrence Date: 06/08/2007 Edward F. Maher, Task 5 Manager Concurrence: Signature on File Concurrence Date: 06/12/2007 Kate Kimpan, Project Director Approval: Brant A. Ulsh Signature on File for Approval Date: 06/22/2007 James W. Neton, Associate Director for Science New Total Rewrite Revision Page Change FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION. Document No. ORAUT-TKBS-0055 Revision No. 00 Effective Date: 06/22/2007 Page 2 of 84 PUBLICATION RECORD EFFECTIVE REVISION DATE NUMBER DESCRIPTION 06/22/2007 00 Approved new Site Profile for Ames Laboratory. Incorporates formal internal and NIOSH review comments. Adds Glossary and Attributions and Annotations section. There is no change to the assigned dose and no PER is required. Training required: As determined by the Task Manager. Initiated by Jerome B. Martin Document No. ORAUT-TKBS-0055 Revision No. -
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 -
Charles Lathrop Parsons Mr
Revised 01/2011 Author’s Note: This is a work in progress and any further information that readers may have would be appreciated. [email protected] Charles Lathrop Parsons Mr. ACS Clarence J. Murphy Department of Chemistry East Stroudsburg University of Pennsylvania East Stroudsburg, PA 18301-2999 More than one hundred years ago in September 1907 Charles Lathrop Parsons took office as the Secretary of the American Chemical Society which had 3000 members. When he retired thirty-eight years later in 1945 the Society was the largest single professional society in the world with 43,000 members and he was better known than any of the presidents who he served and was known as Mr. ACS. As early as 1932 ACS President Marston T. Bogert said, “Having closely followed the progress of our Society for the past forty years I say unhesitatingly and without fear of contradiction that what the American Chemical Society is today it owes more to Charles Lathrop Parsons than any other American chemist.” (1) Parsons’ life and professional career can be divided into four overlapping periods: Early Years, New Hampshire Years, Bureau of Mines, and ACS Secretary. Early Years Charles Lathrop Parsons was born in New Marlboro, Berkshire County, MA on March 23, 1867, the oldest son of Benjamin Franklin and Leonora Bartlett Parsons. A second son, William Naramore Parsons was born October 11, 1869. Benjamin Franklin Parsons was a graduate of Williams College, class of 1857, which had been founded by one of his ancestors. He was ordained a minister shortly after graduation and moved to Charles Lathrop Parsons Mr ACS 012011.docx 1 Revised 01/2011 Author’s Note: This is a work in progress and any further information that readers may have would be appreciated. -
Nuclear Graphite for High Temperature Reactors
Nuclear Graphite for High temperature Reactors B J Marsden AEA Technology Risley, Warrington Cheshire, WA3 6AT, UK Abstract The cores and reflectors in modem High Temperature Gas Cooled Reactors (HTRs) are constructed from graphite components. There are two main designs; the Pebble Bed design and the Prism design, see Table 1. In both of these designs the graphite not only acts as a moderator, but is also a major structural component that may provide channels for the fuel and coolant gas, channels for control and safety shut off devices and provide thermal and neutron shielding. In addition, graphite components may act as a heat sink or conduction path during reactor trips and transients. During reactor operation, many of the graphite component physical properties are significantly changed by irradiation. These changes lead to the generation of significant internal shrinkage stresses and thermal shut down stresses that could lead to component failure. In addition, if the graphite is irradiated to a very high irradiation dose, irradiation swelling can lead to a rapid reduction in modulus and strength, making the component friable. The irradiation behaviour of graphite is strongly dependent on its virgin microstructure, which is determined by the manufacturing route. Nevertheless, there are available, irradiation data on many obsolete graphites of known microstructures. There is also a well-developed physical understanding of the process of irradiation damage in graphite. This paper proposes a specification for graphite suitable for modem HTRs. HTR Graphite Component Design and Irradiation Environment The details of the HTRs, which have, or are being, been built and operated, are listed in Table 1. -
Mon. Oct 29, 2018 Room1 Plenary Talk 1
Mon. Oct 29, 2018 Plenary Talk The 9th International Conference on Multiscale Materials Modeling Mon. Oct 29, 2018 Room1 Plenary Talk | Plenary Talk [PL1] Plenary Talk 1 Chair: Ju Li(MIT, USA) 10:10 AM - 11:00 AM Room1 [PL1] Plenary Talk 1 ○Christopher A. Schuh (Department of Materials Science and Engineering, MIT, USA) Plenary Talk | Plenary Talk [PL2] Plenary Talk 2 Chair: Alexey Lyulin(Technische Universiteit Eindhoven, The Netherlands) 11:00 AM - 11:50 AM Room1 [PL2] Plenary Talk 2 ○Maenghyo Cho (School of Mechanical and Aerospace Engineering, Seoul National University, Korea) ©The 9th International Conference on Multiscale Materials Modeling Mon. Oct 29, 2018 Symposium The 9th International Conference on Multiscale Materials Modeling Mon. Oct 29, 2018 Sauzay2, Mihai Cosmin Marinica1, Normand Mousseau3 Room1 (1.SRMP-CEA Saclay, France, 2.SRMA-CEA Saclay, France, 3.Département de Physique, Université de Symposium | C. Crystal Plasticity: From Electrons to Dislocation Montréal , Canada) Microstructure [SY-C1] Symposium C-1 Symposium | C. Crystal Plasticity: From Electrons to Dislocation Chair: Emmanuel Clouet(CEA Saclay, SRMP, France) Microstructure 1:30 PM - 3:15 PM Room1 [SY-C2] Symposium C-2 Chair: Stefan Sandfeld(Chair of Micromechanical Materials [SY-C1] Kinetic Monte Carlo model of screw dislocation- Modelling, TU Bergakademie Freiberg, Germany) solute coevolution in W-Re alloys 3:45 PM - 5:30 PM Room1 Yue Zhao1, Lucile Dezerald3, ○Jaime Marian1,2 (1.Dept. [SY-C2] Finite deformation Mesoscale Field Dislocation of Materials Science -
Inhibition of Oxidation in Nuclear Graphite
NEA/NSC/WPFC/DOC(2015)9 Inhibition of oxidation in nuclear graphite Philip L. Winston, James W. Sterbentz and William E. Windes Idaho National Laboratory, United States Abstract Graphite is a fundamental material of high-temperature gas-cooled nuclear reactors, providing both structure and neutron moderation. Its high thermal conductivity, chemical inertness, thermal heat capacity, and high thermal structural stability under normal and off-normal conditions contribute to the inherent safety of these reactor designs. One of the primary safety issues for a high-temperature graphite reactor core is the possibility of rapid oxidation of the carbon structure during an off-normal design basis event where an oxidising atmosphere (air ingress) can be introduced to the hot core. Although the current Generation IV high-temperature reactor designs attempt to mitigate any damage caused by a postualed air ingress event, the use of graphite components that inhibit oxidation is a logical step to increase the safety of these reactors. Recent experimental studies of graphite containing between 5.5 and 7 wt% boron carbide (B4C) indicate that oxidation is dramatically reduced even at prolonged exposures at temperatures up to 900°C. The proposed addition of B4C to graphite components in the nuclear core would necessarily be enriched in B-11 isotope in order to minimise B-10 neutron absorption and graphite swelling. The enriched boron can be added to the graphite during billet fabrication. Experimental oxidation rate results and potential applications for borated graphite in nuclear reactor components will be discussed. Introduction Current Generation IV high-temperature gas-cooled reactors (HTR) are predominately constructed of graphite structural components and graphite fuel elements. -
Surface Analysis of Nuclear Graphite
Keywords Surface analysis Graphite, XPS, 2 of nuclear graphite Auger d-parameter, sp Application Note MO426(1) Further application/technical notes are available online at: www.kratos.com Overview Introduction In this short study we will explore the differences in Graphite is one of the key materials used in the current generation of nuclear reactors in the UK. Since the early days of nuclear fission surface chemistry between two different graphites used graphite has been recognised as an excellent neutron moderator in the nuclear industry. In recent times a wide variety and reflector allowing sustainable controlled fission. of nanostructured carbon forms have been observed in Contaminants in moderator rods are a major problem as they nuclear graphite which vary the graphitic nature of the can act as neutron absorbers. This causes decreased fission and material. The nature of these forms can greatly affect production of unwanted isotopes – a common cause of radioactive waste. The goal of this application is to understand the surface the material’s ability to act as an effective moderator. chemistry of two different graphites: Pile Grade A (PGA) and Here we will discuss the elemental composition of the Gilsocarbon (Gilso). PGA is an early form of nuclear graphite used graphite surface and the extent of graphitic sp2 bonding. in many reactors world-wide, particularly in the UK in the Magnox series. It is derived from a petroleum coke (which is a by-product of the oil refining industry). Gilsocarbon was developed later and is used in the Generation II Advanced Gas-Cooled Reactors. The Gilsonite coke is produced from refining the asphalt. -
The Life and Work of Charles James by Marion James
9/26/2016 UNH Magazine: UNH Magazine The Life and Work of Charles James Easy to print version Return to UNH Magazine Fall '10 web extras The Life and Work of Charles James A professor emeritus of history writes about her father, a UNH professor and prominent chemist. By Marion James '40 One hundred years ago, Charles James arrived at New Hampshire College to teach chemistry and begin a distinguished career. Early Years Charles James was born in England on April 27, 1880. His father died when he was 6, and he was brought up by his mother, Mary Diana ShatfordJames, in Holly House in the small village of Broughton, Northamptonshire. He was educated first by a governess and later at a school in the neighboring town of Wellinborough, where he took the program run by Cambridge University. He said he was introduced to chemistry through reading his father's books on the subject. He also may have taken a chemistry course at school. Becoming fascinated with the field, he set up a laboratory at home at age 15 for his own experiments. A friend of his later remembered seeing him making bombs to blow up decaying tree stumps in the area. ¹ Around the same time, his studies encouraged him to establish connections to the scientific world. He collected the names and addresses of great English chemists, and wrote to Sir William Crookes and Sir William Ramsey, the latter about to win the Noble Prize and who "was considered the greatest chemist of his time." ² Both men replied, and he and Ramsey continued to correspond.