Creating a Star: the Global ITER Partnership
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Introduction to Cryostat Design
Introduction to Cryostat Design J. G. Weisend II July 2014 Course Goals Provide an introduction to cryostat design Examine cryostats as integrated systems rather then a group of subsystems Provide background information and useful data Provide pointers to resources for more detail Show examples Introduction to Cryostat Design 7/7/14 2 J. G. Weisend II ICEC 2014 Syllabus Introduction Cryostat Requirements Materials Selection Thermal Isolation and Heat Leak Structures Safety Instrumentation Seals, Feed throughs and Bayonets Transfer Lines Examples References and Resources Introduction to Cryostat Design 7/7/14 3 J. G. Weisend II ICEC 2014 Introduction What is a cryostat? A device or system for maintaining objects at cryogenic temperatures. Cryostats whose principal function is to store cryogenic fluids are frequently called Dewars. Named after the inventor of the vacuum flask and the first person to liquefy hydrogen Introduction to Cryostat Design 7/7/14 4 J. G. Weisend II ICEC 2014 Introduction Cryostats are one of the technical building blocks of cryogenics There are many different types of cryostats with differing requirements The basic principles of cryostat design remain the same Before we can do anything else we have to define our requirements Introduction to Cryostat Design 7/7/14 5 J. G. Weisend II ICEC 2014 E158 LH2 Target Cryostat Introduction to Cryostat Design 7/7/14 6 J. G. Weisend II ICEC 2014 Cryostat Requirements Maximum allowable heat leak at various temperature levels This may be driven by the number of cryostats to be built as well as by the impact of large dynamic heat loads (SCRF or target cryostats) Alignment and vibration requirements Impact of thermal cycles Need to adjust alignment when cold or under vacuum? Alignment tolerances can be quite tight (TESLA : +/‐ 0.5 mm for cavities and +/‐ 0.3 mm for SC magnets) Introduction to Cryostat Design 7/7/14 7 J. -
Versatile Cryogen-Free Cryostat for the Electromagnetic Characterization Of
Saniour et al. EPJ Techniques and Instrumentation (2020) 7:3 EPJ Techniques and https://doi.org/10.1140/epjti/s40485-020-00055-2 Instrumentation RESEARCH ARTICLE Open Access Versatile cryogen-free cryostat for the electromagnetic characterization of superconducting radiofrequency coils Isabelle Saniour1*† , Michel Geahel1,2,3†, Javier Briatico2, Cornelis J. van der Beek3,4, Georges Willoquet1, Laurène Jourdain1, Bertrand Baudouy5, Gilles Authelet5, Jean-Christophe Ginefri1, Luc Darrasse1 and Marie Poirier-Quinot1 * Correspondence: isabelle.saniour@ universite-paris-saclay.fr Abstract Isabelle Saniour and Michel Geahel are Co-first authors. The use of high temperature superconducting (HTS) radio frequency (RF) coils in †Isabelle Saniour and Michel Geahel Magnetic Resonance Imaging (MRI) greatly improves the signal-to-noise ratio (SNR) contributed equally to this work. in many biomedical applications and particularly in micro-MRI. However, a detailed 1Université Paris-Saclay, CEA, CNRS, Inserm, BioMaps, Orsay, France understanding of the electrical behavior of HTS coils is important in order to Full list of author information is optimize their performance through MR experiments. This paper presents a simple available at the end of the article and versatile cryogen-free cryostat designed to characterize the RF properties of HTS coils prior to their use in MRI. The cryostat can be used at temperatures from 50 K to 300 K, with a control precision of approximately 3 mK at 70 K, and can measure the RF electrical power transmitted to an HTS coil over a range from 1 μW to 10 W. The quality factor and resonance frequency of the tested HTS coil are determined as a function of the temperature and the power it dissipates. -
Rulemaking for Enhanced Security of Special Nuclear Material
Rulemaking for Enhanced Security of Special Nuclear Material RIN number: 3150-AJ41 NRC Docket ID: NRC-2014-0118 Regulatory Basis Document January 2015 Table of Contents 1. Introduction and Background .............................................................................................. 1 2. Existing Regulatory Framework .......................................................................................... 3 2.1 Regulatory History ............................................................................................................. 3 2.2 Existing Regulatory Requirements .................................................................................... 8 3. Regulatory Problem .......................................................................................................... 13 3.1 Generic Applicability of Security Orders .......................................................................... 13 3.2 Risk Insights .................................................................................................................... 16 3.3 Consistency and Clarity .................................................................................................. 27 3.4 Use of a Risk-Informed and Performance-Based Structure. ........................................... 29 4. Basis for Requested Changes ........................................................................................... 30 4.1 Material Categorization and Attractiveness ..................................................................... 30 4.2 -
Conceptual Design Report on JT-60SA ___1. JT-60SA
Conceptual Design Report on JT-60SA ________ 1. JT-60SA Mission and Program 1.1 Introduction Realization of fusion energy requires long-term research and development. A schematic of fusion energy development is shown in Fig. 1.1-1. Fusion energy development is divided into 3 phases before commercialization. The large Tokamak phase achieved equivalent break-even plasmas in JET and JT-60 and significant DT Power productions in TFTR and JET. A programmatic objective of the ITER phase is demonstration of scientific and technical feasibility of fusion energy. A primary objective of the DEMO phase is to demonstrate power (electricity) production in a manner leading to commercialization of fusion energy. The fast track approach to fusion energy is to shorten its development period for fusion energy utilization by adding appropriate programs (BA program) in parallel with ITER. Program elements are advanced tokamak/simulation studies and fusion technology/material development. Fig. 1.1-1 Schematic of fusion energy development To specify program elements needed in parallel with ITER, we have to identify the concept of DEMO. Typical DEMO concepts of Japan and EU are shown in Fig.1.1-2. Although size spans widely, operation mode is unanimously “steady-state”. Ranges of the normalized beta are pretty close each other, βN=3.5 to 4.3 for JA DEMO and 3.4 to 4.5 for EU DEMO. Fig. 1.1-2 Cross section and parameters of JA-EU DEMO studies ave 2 The neutron wall load of DEMO exceeds that of ITER (Pn =0.57MW/m ) by a factor of 3-6. -
Tokamak Foundation in USSR/Russia 1950--1990
IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014003 (8pp) doi:10.1088/0029-5515/50/1/014003 Tokamak foundation in USSR/Russia 1950–1990 V.P. Smirnov Nuclear Fusion Institute, RRC ’Kurchatov Institute’, Moscow, Russia Received 8 June 2009, accepted for publication 26 November 2009 Published 30 December 2009 Online at stacks.iop.org/NF/50/014003 In the USSR, nuclear fusion research began in 1950 with the work of I.E. Tamm, A.D. Sakharov and colleagues. They formulated the principles of magnetic confinement of high temperature plasmas, that would allow the development of a thermonuclear reactor. Following this, experimental research on plasma initiation and heating in toroidal systems began in 1951 at the Kurchatov Institute. From the very first devices with vessels made of glass, porcelain or metal with insulating inserts, work progressed to the operation of the first tokamak, T-1, in 1958. More machines followed and the first international collaboration in nuclear fusion, on the T-3 tokamak, established the tokamak as a promising option for magnetic confinement. Experiments continued and specialized machines were developed to test separately improvements to the tokamak concept needed for the production of energy. At the same time, research into plasma physics and tokamak theory was being undertaken which provides the basis for modern theoretical work. Since then, the tokamak concept has been refined by a world-wide effort and today we look forward to the successful operation of ITER. (Some figures in this article are in colour only in the electronic version) At the opening ceremony of the United Nations First In the USSR, NF research began in 1950. -
Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation. -
Nuclear Regulatory Commission § 70.5
Nuclear Regulatory Commission § 70.5 section 51 of the act, determines to be intermediates, which are unsuitable for special nuclear material, but does not use in their present form, but all or include source material; or (2) any ma- part of which will be used after further terial artificially enriched by any of processing. the foregoing but does not include Strategic special nuclear material source material; means uranium-235 (contained in ura- Special nuclear material of low strategic nium enriched to 20 percent or more in significance means: the U235 isotope), uranium-233, or pluto- (1) Less than an amount of special nium. nuclear material of moderate strategic Transient shipment means a shipment significance as defined in paragraph (1) of nuclear material, originating and of the definition of strategic nuclear terminating in foreign countries, on a material of moderate strategic signifi- vessel or aircraft which stops at a cance in this section, but more than 15 United States port. grams of uranium-235 (contained in Unacceptable performance deficiencies uranium enriched to 20 percent or more mean deficiencies in the items relied in U-235 isotope) or 15 grams of ura- on for safety or the management meas- nium-233 or 15 grams of plutonium or ures that need to be corrected to en- the combination of 15 grams when com- sure an adequate level of protection as puted by the equation, grams = (grams defined in 10 CFR 70.61(b), (c), or (d). contained U-235) + (grams plutonium) + United States, when used in a geo- (grams U-233); or graphical sense, includes Puerto Rico (2) Less than 10,000 grams but more and all territories and possessions of than 1,000 grams of uranium-235 (con- the United States. -
A European Success Story the Joint European Torus
EFDA JET JETJETJET LEAD ING DEVICE FOR FUSION STUDIES HOLDER OF THE WORLD RECORD OF FUSION POWER PRODUCTION EXPERIMENTS STRONGLY FOCUSSED ON THE PREPARATION FOR ITER EXPERIMENTAL DEVICE USED UNDER THE EUROPEAN FUSION DEVELOPEMENT AGREEMENT THE JOINT EUROPEAN TORUS A EUROPEAN SUCCESS STORY EFDA Fusion: the Energy of the Sun If the temperature of a gas is raised above 10,000 °C virtually all of the atoms become ionised and electrons separate from their nuclei. The result is a complete mix of electrons and ions with the sum of all charges being very close to zero as only small charge imbalance is allowed. Thus, the ionised gas remains almost neutral throughout. This constitutes a fourth state of matter called plasma, with a wide range of unique features. D Deuterium 3He Helium 3 The sun, and similar stars, are sphe- Fusion D T Tritium res of plasma composed mainly of Li Lithium hydrogen. The high temperature, 4He Helium 4 3He Energy U Uranium around 15 million °C, is necessary released for the pressure of the plasma to in Fusion T balance the inward gravitational for- ces. Under these conditions it is pos- Li Fission sible for hydrogen nuclei to fuse together and release energy. Nuclear binding energy In a terrestrial system the aim is to 4He U produce the ‘easiest’ fusion reaction Energy released using deuterium and tritium. Even in fission then the rate of fusion reactions becomes large enough only at high JG97.362/4c Atomic mass particle energy. Therefore, when the Dn required nuclear reactions result from the thermal motions of the nuclei, so-called thermonuclear fusion, it is necessary to achieve u • extremely high temperatures, of at least 100 million °C. -
611130 Outgoing Amendment No. 52 to Curium US LLC to License No
NRCFORM374 PAGE 1 OF 5 PAGES U.S. NUCLEAR REGULATORY COMMISSION Amendment No. 52 MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30, 31, 32, 33, 34, 35, 36, 37, 39, 40, 70 and 71, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. Licensee In accordance with letter dated 4. Expiration Date: July 31, 2022 Janua~22...2.0J», 1. Curium US LLC ~~t\ Kt:G t----------..iii-,..iii-,--1 5. Docket No.: 030-10801 2. 2703 Wagner Place 3. license No.: 24-04206-05f\A[() Reference No.: Maryland Heights, MO 63043 is amended in Its entirety to re~ as follows: i!" 1 ~i\il'W, 6. Byproduct, source, 7. Chemical ahttor physical form 8. Maximum amount that lice~e·~ 9. Authorized use and/or special nuclear may possess at any one tfmel material this license A. -
Energy Analysis for the Connection of the Nuclear Reactor DEMO to the European Electrical Grid
energies Article Energy Analysis for the Connection of the Nuclear Reactor DEMO to the European Electrical Grid Sergio Ciattaglia 1, Maria Carmen Falvo 2,* , Alessandro Lampasi 3 and Matteo Proietti Cosimi 2 1 EUROfusion Consortium, 85748 Garching, Germany; [email protected] 2 DIAEE—Department of Astronautics, Energy and Electrical Engineering, University of Rome Sapienza, 00184 Rome, Italy; [email protected] 3 ENEA Frascati, 00044 Frascati, Rome, Italy; [email protected] * Correspondence: [email protected] Received: 31 March 2020; Accepted: 22 April 2020; Published: 1 May 2020 Abstract: Towards the middle of the current century, the DEMOnstration power plant, DEMO, will start operating as the first nuclear fusion reactor capable of supplying its own loads and of providing electrical power to the European electrical grid. The presence of such a unique and peculiar facility in the European transmission system involves many issues that have to be faced in the project phase. This work represents the first study linking the operation of the nuclear fusion power plant DEMO to the actual requirements for its correct functioning as a facility connected to the power systems. In order to build this link, the present work reports the analysis of the requirements that this unconventional power-generating facility should fulfill for the proper connection and operation in the European electrical grid. Through this analysis, the study reaches its main objectives, which are the definition of the limitations of the current design choices in terms of power-generating capability and the preliminary evaluation of advantages and disadvantages that the possible configurations for the connection of the facility to the European electrical grid can have. -
NIAC 2011 Phase I Tarditti Aneutronic Fusion Spacecraft Architecture Final Report
NASA-NIAC 2001 PHASE I RESEARCH GRANT on “Aneutronic Fusion Spacecraft Architecture” Final Research Activity Report (SEPTEMBER 2012) P.I.: Alfonso G. Tarditi1 Collaborators: John H. Scott2, George H. Miley3 1Dept. of Physics, University of Houston – Clear Lake, Houston, TX 2NASA Johnson Space Center, Houston, TX 3University of Illinois-Urbana-Champaign, Urbana, IL Executive Summary - Motivation This study was developed because the recognized need of defining of a new spacecraft architecture suitable for aneutronic fusion and featuring game-changing space travel capabilities. The core of this architecture is the definition of a new kind of fusion-based space propulsion system. This research is not about exploring a new fusion energy concept, it actually assumes the availability of an aneutronic fusion energy reactor. The focus is on providing the best (most efficient) utilization of fusion energy for propulsion purposes. The rationale is that without a proper architecture design even the utilization of a fusion reactor as a prime energy source for spacecraft propulsion is not going to provide the required performances for achieving a substantial change of current space travel capabilities. - Highlights of Research Results This NIAC Phase I study provided led to several findings that provide the foundation for further research leading to a higher TRL: first a quantitative analysis of the intrinsic limitations of a propulsion system that utilizes aneutronic fusion products directly as the exhaust jet for achieving propulsion was carried on. Then, as a natural continuation, a new beam conditioning process for the fusion products was devised to produce an exhaust jet with the required characteristics (both thrust and specific impulse) for the optimal propulsion performances (in essence, an energy-to-thrust direct conversion). -
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.