Activated Fusion Radwaste Disposition/Recycling/Clearance
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小型飛翔体／海外 ［Format 2］ Technical Catalog Category
小型飛翔体／海外 ［Format 2］ Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC １．DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体／海外 Figure 2: DEEP prototype software ２．Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
Laboratory Astrophysics with Lasers Chantal Stehlé
Laboratory Astrophysics with lasers Chantal Stehlé LERMA (Laboratoire d’Etudes de la Ma4ère et du Rayonnement en Astrophysique et Atmosphères) This work is partly supported by French state funds managed by the ANR within the InvesBssements d'Avenir programme under reference ANR-11-IDEX-0004-02. Plasma astrophysics see for instance Savin et al. « Lab astro white paper », 2010 Perimeter Methods • Microscopic physical • Experiments processes (opacity, EOS) • Theory, databases • • MulBscale, mulphysics Numerical simulaons • Links to observaons processes (e.g. magne4c reconnecon, shock waves, instabili4es …) Tools • Study of large scale scaled • Medium size lab. processes, (e.g. stellar jets) experiments • Large scale faciliBes (lasers and pinches ) • Super-compung ressources OUTLINE • IntroducBon • Stellar Opacity • EOS for gazeous planets • Scaling • Accreon & Ejecon processes in Young Stars • Conclusion Opacity for stellar interiors From Turck Chièze et al. ApSS 2010 4 Opacity An example of opacity : For a optically thick medium, Hydrogen( Stehlé et al 1993) • LTE is ~ valid -> near blackbody radiaon κν/ρ • The monochromac radiave flux Fν ! is proporBonal to the gradient of rad. Energy and to 1/κν (The radia4on tends to escape from regions where κν is low, ie between lines) hν • The frequency averaged flux <F> is linked to the Rosseland opacity κR. 1 3 dν dB (T) / dT 16 σ T dT 1 ∫ κ ν < F > = and = ν d dB (T) / dT 3 κ R dz κ R ∫ ν ν 5 CEPHEIDS: the enigma Strong periodic (P~ 1 – 50 days) Rela4on P-L : variaons of luminosity L, Teff, and distance calibrator radius. Enveloppe 2 The pulsaon (κ mechanism) log(κR in g/cm ) 2 • in the external part of the stellar envelope 1.5 • linked to an increase of the opacity 1 4 6 -7 -2 3 0.5 10 < T < 10 K (10 < ρ < 10 g/cm ) 0 Hence radiaon is blocked in the internal layers, -> heang -> expansion and beang Core 34 32 30 28 log(External Mass in g ) 2 In the 90’, no code was able Temperature in K, κ in cm /g for M* = 5 M8, Y=0.25, Z=0.08, to reproduce the pulsa6on. -
Inertial Fusion Power Development:Path for Global Warming Suppression
Inertial Fusion Power Development:Path for Global Warming Suppression EU:France, UK,etc. US: LLNL, SNL, U. Rochester East Asia: Japan, China,etc. Kunioki Mima Institute of Laser Engineering, Osaka University IAEA- FC 2008, 50 years’ Ann. of Fusion Res. , Oct.15, 2008, Geneva, SW Outline • Brief introduction and history of IFE research • Frontier of IFE researches Indirect driven ignition by NIF/LMJ Ignition equivalent experiments for fast ignition • IF reactor concept and road map toward power plant IFE concepts Several concepts have been explored in IFE. Driver Irradiation Ignition Laser Direct Central hot spark Ignition HIB Indirect Fast ignition Impact ignition Pulse power Shock ignition The key issue of IFE is implosion physics which has progressed for more than 30 years Producing 1000times solid density and 108 degree temperature plasmas Plasma instabilities R Irradiation non-uniformities Thermal transport and ablation surface of fuel pellet ΔR R-M Instability ΔR0 R-T instability R0 R Feed through R-M and R-T Instabilities in deceleration phase Turbulent Mixing Canter of fuel pellet t Major Laser Fusion Facilities in the World NIF, LLNL, US. LMJ, CESTA, Bordeaux, France SG-III, Menyang,CAEP, China GXII-FIREX, ILE, Osaka, Japan OMEGA-EP, LLE, Rochester, US HiPER, RAL, UK Heavy Ion Beam Fusion: The advanced T-lean fusion fuel reactor Test Stand at LBNL NDCX-I US HIF Science Virtual National Lab.(LBNL, LLNL,PPPL) has been established in 1990. (Directed by G Logan) • Implosion physics by HIB • HIB accelerator technology for 1kA, 1GeV, 1mm2 beam: Beam brightness, Neutralization, NDCX II Collective effects of high current beam, Stripping.(R.Davidson etal) • Reactor concept with Flibe liquid jet wall (R.Moir: HYLIF for HIF Reactor) History of IFE Research 1960: Laser innovation (Maiman) 1972: Implosion concept (J. -
Radiological Basics
Transportation Emergency Preparedness Program MERRTT Radiological Basics INTRODUCTION The reliance upon, and use of, radioactive material in agriculture, notesnotes industry, and medicine continues to increase. As the manufacture, notesnotes use, and disposal of radioactive material has increased, so has the need to transport it. Consequently, the potential for you as a responder to encounter an incident involving some type of radioactive material has increased. Having knowledge of radiological hazards, and the terminology used to describe them, will increase your ability to quickly recognize, safely respond, and accurately relay information during an incident involving radioactive material. PURPOSE Upon completion of this module, you will have a better understanding of the basic structure of an atom and the fundamentals of radiation. MODULE OBJECTIVES Upon completion of this module, you will be able to: 1. Identify the basic components of an atom. 2. Define ionizing radiation, radioactivity, radioactive material, and radioactive contamination. 3. Distinguish between radiation and contamination. 4. Identify some commonly transported sources of radioactive material. 01/05 rev. 3 2-1 Transportation Emergency Preparedness Program MERRTT Radiological Basics BACKGROUND notesnotes Radiation is all around us and has been present since the birth of notesnotes this planet. Today, both man-made and natural radioactive material are part of our daily lives. We use radioactive material for beneficial purposes, such as generating electricity and diagnosing and treating medical conditions. Radiation is used in many ways to improve our health and the quality of our lives. In 1895, while working in his laboratory, Wilhelm Roentgen discovered a previously unknown phenomenon: rays that could penetrate solid objects. -
Nuclear Energy & the Environmental Debate
FEATURES Nuclear energy & the environmental debate: The context of choices Through international bodies on climate change, the roles of nuclear power and other energy options are being assessed by Evelyne ^Environmental issues are high on international mental Panel on Climate Change (IPCC), which Bertel and Joop agendas. Governments, interest groups, and citi- has been active since 1988. Since the energy Van de Vate zens are increasingly aware of the need to limit sector is responsible for the major share of an- environmental impacts from human activities. In thropogenic greenhouse gas emissions, interna- the energy sector, one focus has been on green- tional organisations having expertise and man- house gas emissions which could lead to global date in the field of energy, such as the IAEA, are climate change. The issue is likely to be a driving actively involved in the activities of these bodies. factor in choices about energy options for elec- In this connection, the IAEA participated in the tricity generation during the coming decades. preparation of the second Scientific Assessment Nuclear power's future will undoubtedly be in- Report (SAR) of the Intergovernmental Panel on fluenced by this debate, and its potential role in Climate Change (IPCC). reducing environmental impacts from the elec- The IAEA has provided the IPCC with docu- tricity sector will be of central importance. mented information and results from its ongoing Scientifically there is little doubt that increas- programmes on the potential role of nuclear ing atmospheric levels of greenhouse gases, such power in alleviating the risk of global climate as carbon dioxide (CO2) and methane, will cause change. -
Radioactive Waste
Radioactive Waste 07/05/2011 1 Regulations 2 Regulations 1. Nuclear Regulatory Commission (NRC) 10 CFR 20 Subpart K. Various approved options for radioactive waste disposal. (See also Appendix F) 10 CFR 35.92. Decay in storage of medically used byproduct material. 10 CFR 60. Disposal of high-level wastes in geologic repositories. 10 CFR 61. Shallow land disposal of low level waste. 10 CFR 62. Criteria and procedures for emergency access to non-Federal and regional low-level waste disposal facilities. 10 CFR 63. Disposal of high-level rad waste at Yucca Mountain, NV 10 CFR 71 Subpart H. Quality assurance for waste packaging and transportation. 10 CFR 72. High level waste storage at an MRS 3 Regulations 2. Department of Energy (DOE) DOE Order 435.1 Radioactive Waste Management. General Requirements regarding radioactive waste. 10 CFR 960. General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. Site selection guidelines for a waste repository. The following are not regulations but they provide guidance regarding the implementation of DOE Order 435.1: DOE Manual 435.1-1. Radioactive Waste Management Manual. Describes the requirements and establishes specific responsibilities for implementing DOE O 435.1. DOE Guide 435.1-1. Suggestions and acceptable ways of implementing DOE M 435.1-1 4 Regulations 3. Environmental Protection Agency 40 CFR 191. Environmental Standards for the Disposal of Spent Nuclear Fuel, High-level and Transuranic Radioactive Wastes. Protection for the public over the next 10,000 years from the disposal of high-level and transuranic wastes. 4. Department of Transportation 49 CFR Parts 171 to 177. -
Nova Laser Technology
Nova Laser Technology In building the Nova laser, we have significantly advanced many technologies, including the generation and propagation of laser beams. We have also developed innovations in the fields of alignment, diagnostics, computer control, and image processIng.• For further information contact Nova is the world's most powerful at least 10 to 30 times more energetic John F. Holzrichter (415) 423-7454. laser system. It is designed to heat and than Shiva would be needed to compress small targets, typically 0.1 cm investigate ignition conditions and in size, to conditions otherwise produced possibly to reach gains near unity. only in nuclear weapons or in the Because of the importance of such a interior of stars. Its beams can facility to the progress of inertial fusion concentrate 80 to 120 kJ of energy (in research and because of the construction 3 ns) or 80 to 120 TW of power (in time entailed (at least five to seven 100 ps) on such targets. To couple energy years), the Nova project was proposed to more favorably with the target, Nova's the Energy Research and Development laser light will be harmonically converted Administration and to Congress. It was with greater than 50% efficiency from its decided to base this system on the near-infrared fundamental wavelength proven master-oscillator, linear-amplifier (1.05-,um wavelength) to green (0.525- chain laser system used on the Argus ,um) or blue (0.35-,um) wavelengths. The and Shiva systems. We had great goals of our experiments with Nova are confidence in extending this to make accurate measurements of high neodymium-glass laser technology to the temperature and high-pressure states of 200- to 300-kJ level. -
1 Looking Back at Half a Century of Fusion Research Association Euratom-CEA, Centre De
Looking Back at Half a Century of Fusion Research P. STOTT Association Euratom-CEA, Centre de Cadarache, 13108 Saint Paul lez Durance, France. This article gives a short overview of the origins of nuclear fusion and of its development as a potential source of terrestrial energy. 1 Introduction A hundred years ago, at the dawn of the twentieth century, physicists did not understand the source of the Sun‘s energy. Although classical physics had made major advances during the nineteenth century and many people thought that there was little of the physical sciences left to be discovered, they could not explain how the Sun could continue to radiate energy, apparently indefinitely. The law of energy conservation required that there must be an internal energy source equal to that radiated from the Sun‘s surface but the only substantial sources of energy known at that time were wood or coal. The mass of the Sun and the rate at which it radiated energy were known and it was easy to show that if the Sun had started off as a solid lump of coal it would have burnt out in a few thousand years. It was clear that this was much too shortœœthe Sun had to be older than the Earth and, although there was much controversy about the age of the Earth, it was clear that it had to be older than a few thousand years. The realization that the source of energy in the Sun and stars is due to nuclear fusion followed three main steps in the development of science. -
ENGINEERING DESIGN of the NOVA LASER FACILITY for By
ENGINEERING DESIGN OF THE NOVA LASER FACILITY FOR INERTIAL-CONFINEMENT FUSION* by W. W. Simmons, R. 0. Godwin, C. A. Hurley, E. P. Wallerstein, K. Whitham, J. E. Murray, E. S. Bliss, R. G. Ozarski. M. A. Summers, F. Rienecker, D. G. Gritton, F. W. Holloway, G. J. Suski, J. R. Severyn, and the Nova Engineering Team. Abstract The design of the Nova Laser Facility for inertia! confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to- performance requirements as they impact the various subsystems that comprise this complex experimental facility. - DISCLAIMER - CO;.T-CI104n--17D DEf;2 013.375 *Research performed under the auspices of the U.S. Department of Energy by the Lawrence Livermore National Laboratory under contract number W-7405-ENG-48. Foreword The Nova Laser System for Inertial Confinement Fusion studies at Lawrence Livermore National Laboratories represents a sophisticated engineering challenge to the national scientific and industrial community, embodying many disciplines - optical, mechanical, power and controls engineering for examples - employing state-of-the-art components and techniques. The papers collected here form a systematic, comprehensive presentation of the system engineering involved in the design, construction and operation of the Nova Facility, presently under construction at LLNL and scheduled for first operations in 1985. The 1st and 2nd Chapters present laser design and performance, as well as an introductory overview of the entire system; Chapters 3, 4 and 5 describe the major engineering subsystems; Chapters 6, 7, 8 and 9 document laser and target systems technology, including optical harmonic frequency conversion, its ramifications, and its impact upon other subsystems; and Chapters 10, 11, and 12 present an extensive discussion of our integrated approach to command, control and communications for the entire system. -
RTM Perspectives June 27, 2016
Fusion Finally Coming of Age? Manny Frishberg, Contributing Editor RTM Perspectives June 27, 2016 Harnessing nuclear fusion, the force that powers the sun, has been a pipe dream since the first hydrogen bombs were exploded. Fusion promises unlimited clean energy, but the reality has hovered just out of reach, 20 years away, scientists have said for more than six decades—until now. Researchers at Lawrence Livermore Labs, the University of Washington, and private companies like Lockheed Martin and Canada’s General Fusion now foresee the advent of viable, economical fusion energy in as little as 10 years. Powered by new developments in materials, control systems, and other technologies, new reactor designs are testing old theories and finding new ways to create stable, sustainable reactions. Nuclear power plants create energy by breaking apart uranium and plutonium atoms; by contrast, fusion plants squeeze together atoms (typically hydrogen) at temperatures of 1 to 2 million degrees C to form new, heavier elements, essentially creating a miniature star in a bottle. Achieving fusion requires confining plasma to create astronomical levels of pressure and heat. Two approaches to confining the plasma have dominated: magnetic and inertial confinement. Magnetic confinement uses the electrical conductivity of the plasma to contain it with magnetic fields. Inertial confinement fires an array of powerful lasers or particle beams at the hydrogen atoms to pressurize and superheat them. Both approaches require huge amounts of energy, and they struggle to get more energy back out of the system. Most efforts to date have relied on some form of magnetic confinement. For instance, the International Thermonuclear Experimental Reactor, or ITER, being built in southern France by a coalition that includes the European Union, China, India, Japan, South Korea, Russia, and the United States, is a tokamak reactor. -
Subject Categories and Scope Descriptions Co Q
International Nuclear Information System (INIS) • LU Q CD XA0202260 D) c CO IAEA-ETDE/TNIS-2 o X LU CO -I—• SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS CO Q ETDE/INIS Joint Reference Series No. 2 CT O c > LU O O E "- =3 CO I? O cB CD C , LU • CD 3 CO -Q T3 CD >- c •a « C c CD o o CD «2 i- CO .3-3/33 CO ,_ CD a) O % 3 O •z. a. Renewable energy technologies • Radiation protection • Energy storage, conversion, and consumption Radioactive waste management • Energy policy • Radiation effects on living organisms • Fossil fuels INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, JULY 2002 ETDE/INIS Joint Reference Series No. 2 SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, JULY 2002 SUBJECT CATEGORIES AND SCOPE DESCRIPTIONS IAEA, VIENNA, 2002 IAEA-ETDE/INIS-2 ISBN 92-0-112902-5 ISSN 1684-095X © IAEA, 2002 Printed by the IAEA in Austria July 2002 PREFACE This document is one in a series of publications known as the ETDE/INIS Joint Reference Series. It defines the subject categories and provides the scope descriptions to be used for categorization of the nuclear literature for the preparation of INIS input by national and regional centers. Together with volumes of the INIS Reference Series and ETDE/INIS Joint Reference Series it defines the rules, standards and practices and provides the authorities to be used in the International Nuclear Information System. A list of the volumes published in the IMS Reference Series and ETDE/ENIS Joint Reference Series can be found at the end of this publication. -
LA-7973-MS the Reversed-Field Pinch Reactor (RFPR) Concept O
LA-7973-MS Informal Report The Reversed-Field Pinch Reactor (RFPR) Concept 01 O LOS ALAMOS SCIENTIFIC LABORATORY Post Office Box 1663 Los Alamos. New Mexico 87545 LA-7973-MS Informal Report UC-20d MOT Issued: August 1979 The Reversed-Field Pinch Reactor (RFPR) Concept R. L. Hagenson R. A. Krakowski G. E. Cort MAJOR CONTRIBUTORS Engineering: W. E. Fox, R. W. Teasdale Neutronics: P. D. Soran Tritium: C. G. Bathke, H. Cullingford Materials: F. W. Clinard, Jr. Plasma Engineering: R. L. Miller Physics: D. A. Baker, J. N. DiMarco Electrotechnology: R. W. Moses l-neip. :«. makes s any legal inW,i» „. ,«p..nS*.lil> >"' <'« 11|lll.CSi Ulit l'ISCl • '' ! 1. Equilibrium and Stability 15b 2. Transport 155 3-. Startup . 158 4. Rundown (Quench) 159 B. T'jchnolofey Assessment 160 1. First wall 160 2. Blanket 160 3» Energy Transfer, Storage and Switching 161 4. Magnets 162 5« Vacuum and Tritium Recovery 162 C. Summary Assessment 163 APPENDIX A. RFPR BURN MODEL AND REACTOR'CODE 166 1. Plasma and Magnetic Field Models 166 2. Plasma Energy balance 169 3. Anomalous Radial Transport 17A APPENDIX B. COSTING MODEL 176 APPENDIX C. STANDARD FUSIOt: REACTOR DESIGN TABLE 185 APPENDIX D. BLANKET TRITIUM TRANSPORT MODEL 197 1. Development of Model 197 2. Evaluation of Model 200 3. Tritium Inventory Question - 202 APPENDIX E. SUMMARY REVIEW OF DESIGN POINT EVOLUTION 206 vn TABLE OF CONTENTS THL REVERSED-FIELI) PINCH REACTOR (KFPR) CONCEPT 1 ABSTRACT 1 I. INTRODUCTION 2 II. EXECUTIVE SUMMARY 4 A. Fundamental Physics Issues 4 B. Reactor Description ••* 9 1. Reactor Operation 10 2.