Abstract for 43Rd Loss Prevention Symposium, Aiche, Spring 2009
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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. -
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. -
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. -
Hebron Project Comprehensive Study Report Table of Contents
Hebron Project Comprehensive Study Report Table of Contents TABLE OF CONTENTS 1 INTRODUCTION ................................................................................................................................. 1-1 1.1 Hebron Project Area ............................................................................................................. 1-1 1.1.1 Nearshore Project Area ...................................................................................... 1-1 1.1.2 Offshore Project Area ......................................................................................... 1-2 1.2 Project Proponents .............................................................................................................. 1-3 1.3 Regulatory Context .............................................................................................................. 1-4 1.4 Purpose of the Comprehensive Study Report................................................................... 1-7 1.5 Scope of the Project ............................................................................................................. 1-7 1.5.1 Project Components - Nearshore Project Area .................................................. 1-7 1.5.2 Project Components - Offshore Project Area ..................................................... 1-8 1.5.3 Potential Expansion Opportunities ...................................................................... 1-8 1.6 Document Organization ...................................................................................................... -
Radiation Safety Plan
RADIATION SAFETY PLAN ENVIRONMENTAL NOVA SOUTHEASTERN HEALTH AND SAFETY UNIVERSITY POLICY/PROCEDURE POLICY/PROCEDURE TITLE: Radiation Safety Plan NUMBER: 9 DOCUMENT HISTORY OWNER: Facilities Management/AHIS Date: 1 Sept 2011 APPROVED: NSU Radiation Safety Committee Date: 1 Sept 2011 IMPLEMENTED: Date: 1 Oct 2010 RETIRED: Date: Date: Revision No. Review / Changes Reviewer 1/2017 1 Remove Gamma Irradiator reference RSO-5 form RSC 1/2017 2 Change EHS Committee to Radiation Safety RSC Committee (RSC) 1/2017 3 Change references from EHS to RSO RSC 4/2019 4 Edit section 5.4 to remove shipping building RSO RADIATION SAFETY PLAN RADIATION SAFETY PLAN Table of Contents Section 1: Introduction ........................................................................................................ 4 Section 2: Biological Effects and Exposure Protection ......................................................... 9 Section 3: Responsibilities ................................................................................................. 12 Section 4: License Requirements ....................................................................................... 15 Section 5: Authorization and Procurement of Radioactive Materials ................................ 16 Section 6: Training ............................................................................................................. 19 Section 7: Personnel Monitoring and Occupational Dose Limits ....................................... 22 Section 8: Signs and Labels ............................................................................................... -
Signature Redacted %
EXAMINATION OF THE UNITED STATES DOMESTIC FUSION PROGRAM ARCHW.$ By MASS ACHUSETTS INSTITUTE Lauren A. Merriman I OF IECHNOLOLGY MAY U6 2015 SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING I LIBR ARIES IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF BACHELOR OF SCIENCE IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY FEBRUARY 2015 Lauren A. Merriman. All Rights Reserved. - The author hereby grants to MIT permission to reproduce and to distribute publicly Paper and electronic copies of this thesis document in whole or in part. Signature of Author:_ Signature redacted %. Lauren A. Merriman Department of Nuclear Science and Engineering May 22, 2014 Signature redacted Certified by:. Dennis Whyte Professor of Nuclear Science and Engineering I'l f 'A Thesis Supervisor Signature redacted Accepted by: Richard K. Lester Professor and Head of the Department of Nuclear Science and Engineering 1 EXAMINATION OF THE UNITED STATES DOMESTIC FUSION PROGRAM By Lauren A. Merriman Submitted to the Department of Nuclear Science and Engineering on May 22, 2014 In Partial Fulfillment of the Requirements for the Degree of Bachelor of Science in Nuclear Science and Engineering ABSTRACT Fusion has been "forty years away", that is, forty years to implementation, ever since the idea of harnessing energy from a fusion reactor was conceived in the 1950s. In reality, however, it has yet to become a viable energy source. Fusion's promise and failure are both investigated by reviewing the history of the United States domestic fusion program and comparing technological forecasting by fusion scientists, fusion program budget plans, and fusion program budget history. -
Public Annual Report 2019
W-'nova TERRA NOVA DEVELOPMENT Terra Nova Development Canada-Newfoundland and Labrador Benefits Public Annual Report 2019 2019 ANNUAL CANADA-NEWFOUNDLAND AND LABRADOR D'nova BENEFITS REPORT Table of Contents INTRODUCTION ............................................................................................................................ 3 PROJECT ACTIVITY AND BENEFITS ACCOMPLISHMENTS ............................................................ 4 EMPLOYMENT ............................................................................................................................. 5 CANADIAN-NL CONTENT ESTIMATES ........................................................................................ 8 CONTRACTING AND PROCUREMENT ........................................................................................... 8 RESEARCH AND DEVELOPMENT AND EDUCATION AND TRAINING ........................................... 11 DIVERSITY ................................................................................................................................. 13 CONCLUSION ............................................................................................................................. 20 FIGURES AND TABLES FIGURE 1 – 2019 TERRA NOVA PURCHASE ORDERS ....................................................................................... 8 FIGURE 2 – WOMEN IN ENGINEERING SCHOLARSHIP PRESENTATION ........................................................ 16 FIGURE 3 – VOLUNTEERING AT THE SINGLE PARENT ASSOCIATION OF NEWFOUNDLAND -
Terra Nova Industrial Benefits – Quarterly Report Q1 2016
Terra Nova Development Canada-Newfoundland and Labrador Industrial Benefits Public Quarterly Report January 01, 2016 – March 31, 2016 Terra Nova Development Canada-Newfoundland and Labrador Industrial Benefits Public Report – 1st Quarter 2016 Table of Contents Section 1.0 – Introduction............................................................................................................................. 3 Section 2.0 – Terra Nova Development ........................................................................................................ 4 Section 3.0 – Project Activity and Benefits Accomplishments ..................................................................... 5 Section 4.0 – Employment ............................................................................................................................ 6 Section 5.0 – Canadian-Newfoundland and Labrador Content .................................................................... 8 Section 6.0 – Contracting and Procurement ................................................................................................. 9 Section 7.0 – Conclusion ............................................................................................................................. 10 Terra Nova Development Canada-Newfoundland and Labrador Industrial Benefits Public Report – 1st Quarter 2016 Section 1.0 – Introduction Suncor is one of the world’s largest integrated energy companies. As stewards of valuable natural resources, Suncor has the opportunity – and the responsibility -
Doctoral Capstone Experience in Academia- Nova Southeastern University
Nova Southeastern University NSUWorks Department of Occupational Therapy Entry- Level Capstone Projects Department of Occupational Therapy 4-25-2021 Doctoral Capstone Experience in Academia- Nova Southeastern University Milady Velazquez De Jesus Nova Southeastern University, [email protected] Follow this and additional works at: https://nsuworks.nova.edu/hpd_ot_capstone Part of the Education Commons Share Feedback About This Item NSUWorks Citation Milady Velazquez De Jesus. 2021. Doctoral Capstone Experience in Academia- Nova Southeastern University. Capstone. Nova Southeastern University. Retrieved from NSUWorks, . (22) https://nsuworks.nova.edu/hpd_ot_capstone/22. This Entry Level Capstone is brought to you by the Department of Occupational Therapy at NSUWorks. It has been accepted for inclusion in Department of Occupational Therapy Entry-Level Capstone Projects by an authorized administrator of NSUWorks. For more information, please contact [email protected]. Running head: FINAL CULMINATING PROJECT Doctoral Capstone Experience in Academia- Nova Southeastern University Milady Velázquez De Jesús Department of Occupational Therapy, Nova Southeastern University OTD 8494: Doctoral Residency Dr. Kane April 25, 2021 2 FINAL CULMINATING PROJECT Table of Content Abstract ........................................................................................................................................................ 3 Introduction ................................................................................................................................................ -
Terra Nova Industrial Benefits – Quarterly Report Q1 2019
Terra Nova Development Canada-Newfoundland and Labrador Industrial Benefits Public Quarterly Report January 01, 2019 – March 31, 2019 Terra Nova Development Canada-Newfoundland and Labrador Industrial Benefits Public Report – 1st Quarter 2019 Table of Contents Section 1.0 – Introduction............................................................................................................................. 3 Section 2.0 – Terra Nova Development ........................................................................................................ 4 Section 3.0 – Project Activity and Benefits Accomplishments...................................................................... 5 Section 4.0 – Employment ............................................................................................................................ 6 Section 5.0 – Canadian-Newfoundland and Labrador Content .................................................................... 8 Section 6.0 – Contracting and Procurement ................................................................................................. 9 Section 7.0 – Conclusion ............................................................................................................................. 10 Terra Nova Development Canada-Newfoundland and Labrador Industrial Benefits Public Report – 1st Quarter 2019 Section 1.0 – Introduction Suncor is one of the world’s largest integrated energy companies. As stewards of valuable natural resources, Suncor has the opportunity – and the responsibility -
Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends
Energies 2010, 3, 1067-1086; doi:10.3390/en30601067 OPEN ACCESS energies ISSN 1996-1073 www.mdpi.com/journal/energies Review Fifty Years of Magnetic Fusion Research (1958–2008): Brief Historical Overview and Discussion of Future Trends Laila A. El-Guebaly University of Wisconsin-Madison, 1500 Engineering Dr. Madison, WI 53706, USA; E-Mail: [email protected]; Tel.: +01-608-263-1623; Fax: +01-608-263-4499 Received: 3 March 2010; in revised form: 29 April 2010 / Accepted: 10 May 2010 / Published: 1 June 2010 Abstract: Fifty years ago, the secrecy surrounding magnetically controlled thermonuclear fusion had been lifted allowing researchers to freely share technical results and discuss the challenges of harnessing fusion power. There were only four magnetic confinement fusion concepts pursued internationally: tokamak, stellarator, pinch, and mirror. Since the early 1970s, numerous fusion designs have been developed for the four original and three new approaches: spherical torus, field-reversed configuration, and spheromak. At present, the tokamak is regarded worldwide as the most viable candidate to demonstrate fusion energy generation. Numerous power plant studies (>50), extensive R&D programs, more than 100 operating experiments, and an impressive international collaboration led to the current wealth of fusion information and understanding. As a result, fusion promises to be a major part of the energy mix in the 21st century. The fusion roadmaps developed to date take different approaches, depending on the anticipated power plant concept and the degree of extrapolation beyond ITER. Several Demos with differing approaches will be built in the US, EU, Japan, China, Russia, Korea, India, and other countries to cover the wide range of near-term and advanced fusion systems.