Plasma-Facing Components in Tokamaks: Material Modification And
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OAK RIDGE NATIONAL LABORATORY Engineering Physics
oml ORNL-6868 OAK RIDGE NATIONAL LABORATORY Engineering Physics LOCK H * M D NJA Jt rim Or" and Mathematics Division ^ Progress Report for Period Ending December 31,1994 R. F. Sincovec, Director MANAGED BY LOCKHEED MARTIN ENERGY SYSTEMS, INC. FOR THE UNITED STATES DEPARTMENT OF ENERGY UCI*13673 {36 W5) This report has been reproduced directly from the ilabie copy. Available to DOE and DOE contractors from the Scientific and Techni- cal Information, P.O. Box 62, Oak Ridge, TN 37> s available from (615) 576-8401, FTS 626-8401. Available to the public from the National Teci rmation Service, U.S. Department of Commerce, 5285 Port Royal Rd.,; d, VA 22161. 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 any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com• pleteness, or usefulness of any information, apparatus, product, or process dis• closed, 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 consti• tute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. ORNL-6868 Engineering Physics and Mathematics Division ENGINEERING PHYSICS AND MATHEMATICS DIVISION PROGRESS REPORT FOR PERIOD ENDING DECEMBER 31, 1994 R. -
Recent Tritium Breeding Experiments with Lithium Titanate Mock-Ups Irradiated with DT Neutrons
JAP]Rf-Conf 2004-012 III11111 1111111111 11111 11111 11111 11IN JP0450771 7.2 Recent tritium breeding experiments with lithium titanate mock-ups irradiated with DT neutrons Axel Klix", Yury Verz iloVb , Kentaro Ochiai6, Takeo Nishitan b, Akito Takahashi' ' Department of Nuclear Engineering, Osaka nVuersity, Sulta, Japan bFusion Neutronics Source, Japan Atomic Energy Research Institute, Tokaimura, Japan Experiments with breeding blanket mock-ups composed of layers of beryllium, ferritic steel F82H and 6Li enriched lithium titanate, Li2TiO3 are currently under investigation at Fusion Neutronics Source (FNS) of JAERI. Pellets of Li2TiO3 were used as detectors for the tritium production rate inside the tritium breeding layer. A method for direct measurement of low concentrations of tritium in Li2TiO3 was developed. After irradiation, the pellets were dissolved in concentrated hydrochloric acid and the tritium activity in the sample solution was measured by liquid scintillation counting. This method was applied to several mock-up experiments and the experiments analyzed with three-dimensional Monte Carloc calculations. In some cases the tritium production rate was found to be overestimated by the calculations. KEYWORDS: FNS, D-T neutrons, breeding blanket, lithium titanate, tritium I Introduction 100 r -So rce: FENIS_ Tritium is a fuel for fusion reactors based on the E T Deuterium-Tritium (DT) fusion reaction. It must be pro- 1: 10 duced artificially in a lithium compound in the breeding .0 Q) T :7 -7 7-7, blanket which surrounds the fusion zone. A sufficiently U) _ i high tritium production performance is an important de- U3 f sign parameter for the breeding blanket. -
Article Thermonuclear Bomb 5 7 12
1 Inexpensive Mini Thermonuclear Reactor By Alexander Bolonkin [email protected] New York, April 2012 2 Article Thermonuclear Reactor 1 26 13 Inexpensive Mini Thermonuclear Reactor By Alexander Bolonkin C&R Co., [email protected] Abstract This proposed design for a mini thermonuclear reactor uses a method based upon a series of important innovations. A cumulative explosion presses a capsule with nuclear fuel up to 100 thousands of atmospheres, the explosive electric generator heats the capsule/pellet up to 100 million degrees and a special capsule and a special cover which keeps these pressure and temperature in capsule up to 0.001 sec. which is sufficient for Lawson criteria for ignition of thermonuclear fuel. Major advantages of these reactors/bombs is its very low cost, dimension, weight and easy production, which does not require a complex industry. The mini thermonuclear bomb can be delivered as a shell by conventional gun (from 155 mm), small civil aircraft, boat or even by an individual. The same method may be used for thermonuclear engine for electric energy plants, ships, aircrafts, tracks and rockets. ----------------------------------------------------------------------- Key words: Thermonuclear mini bomb, thermonuclear reactor, nuclear energy, nuclear engine, nuclear space propulsion. Introduction It is common knowledge that thermonuclear bombs are extremely powerful but very expensive and difficult to produce as it requires a conventional nuclear bomb for ignition. In stark contrast, the Mini Thermonuclear Bomb is very inexpensive. Moreover, in contrast to conventional dangerous radioactive or neutron bombs which generates enormous power, the Mini Thermonuclear Bomb does not have gamma or neutron radiation which, in effect, makes it a ―clean‖ bomb having only the flash and shock wave of a conventional explosive but much more powerful (from 1 ton of TNT and more, for example 100 tons). -
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. -
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. -
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. -
Fusion Rockets for Planetary Defense
| Los Alamos National Laboratory | Fusion Rockets for Planetary Defense Glen Wurden Los Alamos National Laboratory Exploratory Plasma Research Workshop Feb 26, 2016 LA-UR-16-21396 LA-UR-15-xxxx UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA April 2014 | UNCLASSIFIED | 1 | Los Alamos National Laboratory | My collaborators on this topic: T. E. Weber1, P. J. Turchi2, P. B. Parks3, T. E. Evans3, S. A. Cohen4, J. T. Cassibry5, E. M. Campbell6 . 1Los Alamos National Laboratory . 2Santa Fe, NM . 3General Atomics . 4Princeton Plasma Physics Laboratory . 5University of Alabama, Huntsville . 6LLE, University of Rochester, Rochester Wurden et al., Journal of Fusion Energy, Vol. 35, 1, 123 (2016) UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA April 2014 | UNCLASSIFIED | 2 | Los Alamos National Laboratory | How many ways is electricity made today? Primary Energy Source Nominally CO2 Free Current capacity (%) Expected Lifetime (yrs) Natural Gas no 100 Coal no 80.6 400 Oil no < 50 Biomass neutral 11.4 > 400 Wind yes 0.5 > 1000 Solar photovoltaic yes 0.06 > 1000 Solar thermal yes 0.17 > 1000 Hydro yes 3.3 > 1000 Wave/Tidal yes 0.001 > 1000 Geothermal yes 0.12 > 1000 Nuclear fission yes 2.7 > 400 [i] REN21–Renewable Energy Policy Network for the 21st Century Renewables 2012–Global Status Report, 2012, http://www.map.ren21.net/GSR/GSR2012.pdf , http://en.wikipedia.org/wiki/Energy_development UNCLASSIFIED Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA April 2014 | UNCLASSIFIED | 3 | Los Alamos National Laboratory | What is the most important product that fusion could deliver? . -
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 -
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. -
Starpower: the US and the International Quest for Fusion Energy
Appendix B Other Approaches to Fusion The main body of this report has discussed magnetic The issues addressed by inertial confinement fusion confinement fusion, the approach to controlled fusion research in the United States concern the individual that the worldwide programs emphasize most heav- targets containing the fusion fuel; the input energy ily. However, two other approaches to fusion are also sources, called drivers, that heat and compress these being investigated. All three approaches are based on targets; and the mechanism by which energy from the the same fundamental physical process, in which the driver is delivered–or coupled–into the target. Due nuclei of light isotopes, typically deuterium and tri- to the close relationship between inertial confinement tium, release energy by fusing together to form heav- fusion target design and thermonuclear weapon de- ier isotopes. Some of the technical issues are similar sign, inertial confinement fusion research is funded among all the fusion approaches, such as mechanisms by the nuclear weapons activities portion of the De- for recovering energy and breeding tritium fuel. How- partment of Energy’s (DOE’s) budget. Inertial confine- ever, compared to magnetic confinement, the two ap- ment research is conducted largely at nuclear weap- proaches discussed below create the conditions nec- ons laboratories; its near-term goals are dedicated essary for fusion to occur in very different ways, and largely to military, rather than energy applications, and some substantially different science and technology a substantial portion of this research is classified. issues emerge in each case. There are two near-term military applications of in- ertial confinement fusion—one actual and one not yet Inertial Confinement Fusion1 realized. -
Physics and Technology Considerations for the Deuterium–Tritium Fuel Cycle and Conditions for Tritium Fuel Self Sufficiency
International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 61 (2021) 013001 (51pp) https://doi.org/10.1088/1741-4326/abbf35 Review Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency 1, 1 1 2 Mohamed Abdou ∗, Marco Riva , Alice Ying , Christian Day , Alberto Loarte3, L.R. Baylor4, Paul Humrickhouse5, Thomas F. Fuerst5 and Seungyon Cho6 1 University of California, Los Angeles (UCLA), United States of America 2 Karlsruhe Institute of Technology (KIT), Germany 3 ITER Organization, Route de Vinon-sur-Verdon, CS90046, 13067 St Paul-lez-Durance, France 4 Oak Ridge National Laboratory (ORNL), United States of America 5 Idaho National Laboratory (INL), United States of America 6 National Fusion Research Institute (NFRI), Korea, Republic Of E-mail: [email protected] Received 22 June 2020, revised 16 September 2020 Accepted for publication 7 October 2020 Published 23 November 2020 Abstract The tritium aspects of the DT fuel cycle embody some of the most challenging feasibility and attractiveness issues in the development of fusion systems. The review and analyses in this paper provide important information to understand and quantify these challenges and to dene the phase space of plasma physics and fusion technology parameters and features that must guide a serious R&D in the world fusion program. We focus in particular on components, issues and R&D necessary to satisfy three ‘principal requirements’: (1) achieving tritium self-sufciency within the fusion system, (2) providing a tritium inventory for the initial start-up of a fusion facility, and (3) managing the safety and biological hazards of tritium. -
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 .................................................................................................