DOCSLIB.ORG

Heat Transfer Salts for Nuclear Reactor Systems – Chemistry Control, Corrosion Mitigation, and Modeling

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Heat Transfer Salts for Nuclear Reactor Systems – Chemistry Control, Corrosion Mitigation, and Modeling Project No. 10-905 Heat Transfer Salts for Nuclear Reactor Systems – Chemistry Control, Corrosion Mitigation, and Modeling Reactor Concepts RD&D Dr. Mark Anderson University of Wisconsin, Madison In collaboration with: Pacific Northwest National Laboratory University of California, Berkeley Brian Robinson, Federal POC Michael McKellar, Technical POC Heat Transfer Salts for Nuclear Reactor Systems - chemistry control, corrosion mitigation and modeling CFP-10-100 Dr. Mark Anderson, Dr. Kumar Sridharan, Dr. Dane Morgan , Dr. Per Peterson, Dr. Pattrick Calderoni, Mr. Randall Scheele , Dr. Andrew Casella, Dr. Bruce McNamara, Brian Kelleher , Robert Sellers, Tony (Guiqiu) Zheng, Tommy Cisneros, Oday Albakri, Nick Kuwahara, Jun Yang, Maxwell Strassman, Arjun Kalra, William Ryan, David Pfotenhauer, Brad Motl, Paul Brooks UNIVERSITY OF WISCONSIN-MADISON, UNIVERSITY OF CALIFORNIA - BERKELEY, PACIFIC NORTHWEST NATIONAL LABORATORY i Executive Summary The concept of a molten salt reactor has existed for nearly sixty years. Previously all work was done during a large collaborative effort at Oak Ridge National Laboratory, culminating in a research reactor which operated for 15,000 hours without major error. This technical success has garnished interest in modern, high temperature, reactor schemes. Research using molten fluoride salts for nuclear applications requires a steady supply of high grade molten salts. There is no bulk supplier of research grade fluoride salts in the world, so a facility which could provide all the salt needed for testing at the University of Wisconsin had to be produced. Two salt purification devices were made for this purpose, a large scale purifier, and a small scale purifier, each designed to clean the salts from impurities and reduce their corrosion potential. As of now, the small scale has performed with flibe salt, hydrogen, and hydrogen flu- oride, yielding clean salt. This salt is currently being used in corrosion testing facilities at the Massachusetts Institute of Technology and the University of Wisconsin. Working with the beryllium based salts requires extensive safety measures and health moni- toring to prevent the development of acute or chronic beryllium disease, two pulmonary diseases created by an allergic reaction to beryllium in the lungs. Extensive health monitoring, engineering controls, and environment monitoring had to be set up with the University of Wisconsin depart- ment of Environment, Health and Safety. The hydrogen fluoride required for purification was also an extreme health hazard requiring thoughtful planning and execution. These dangers have made research a slow and tedious process. Simple processes, such as chemical handling and clean-up can take large amounts of ingenuity and time. Other work has complemented the experimental research at Wisconsin to advance high tem- perature reactor goals. Modeling work has been performed in house to re-evaluate thermophysical properties of flibe and flinak. Pacific Northwest National Laboratories has focused on evaluating the fluorinating gas nitrogen trifluoride as a potential salt purification agent. Work there was per- formed on removing hydroxides and oxides from flinak salt under controlled conditions. Lastly, the University of California Berkeley has spent considerable time designing and simulating reactor components with fluoride salts at high temperatures. Despite the hurdles presented by the innate chemical hazards, considerable progress has been made. The stage has been set to perform new research on salt chemical control which could advance the fluoride salt cooled reactor concept towards commercialization. What were previously thought of as chemical undesirable, but nuclear certified, alloys have been shown to be theoretically compatible with fluoride salts at high temperatures. This preliminary report has been prepared to communicate the construction of the basic infrastructure required for flibe, as well as suggest original research to performed at the University of Wisconsin. Simultaneously, the contents of this report can serve as a detailed, but introductory guide to allow anyone to learn the fundamentals of chemistry, engineering, and safety required to work with flibe salt. ii Table of Contents Executive Summary i Table of Contents ii List of Tables vi List of Figures viii 1 Molten Fluoride Salts for Nuclear Power 1 1.1 History and Applications of Molten Salts . 1 1.2 The Molten Salt Reactor Experiment . 2 1.3 Generation IV Systems: The Fluoride Salt Cooled High Temperature Reactor . 5 2 Fluoride Salt Properties and Chemistry 7 2.1 Selection of Salt for Reactor Use . 7 2.2 Assorted Thermophysical Properties of Flibe . 7 2.3 Thermodynamics and Corrosion Mechanisms of Fluoride Salts . 10 2.3.1 Lewis Acid and Base Chemistry, Salt Stability, and Pure Salt Chemistry . 10 2.3.2 Redox Potential . 12 2.3.3 Chemical Equilibrium and Fluorine Potential . 14 2.3.4 Measured Solubilities of Cr, Fe, and Ni in Flibe . 19 2.3.5 Relationship of Fluorine Potential, Redox Potential, and Chemical Equi- librium . 21 2.3.6 Summary of Equilibrium . 21 2.4 Impurity Driven Corrosion . 22 2.4.1 Water Hydrolysis Reactions . 22 2.4.2 Sulfur Corrosion Reactions . 24 2.4.3 Galvanic Corrosion . 26 2.5 Corrosion Control . 26 2.5.1 Controlling Fluorine Potential . 27 2.5.2 The Hydrofluorination Process . 30 2.5.3 Oxide Removal . 32 2.5.4 Removal of Sulfur . 32 2.5.5 Metal and Metal Fluoride Removal . 33 2.6 Past Determination of Salt Composition and Impurities . 35 2.6.1 Measurements of Beryllium . 36 2.6.2 Structural Metal Analysis . 37 2.6.3 Oxide Analysis . 37 iii 2.7 Previous Corrosion Testing . 37 2.8 Hazards . 43 2.8.1 Beryllium . 44 2.8.2 Anhydrous and Aqueous Hydrogen Fluoride . 49 3 Purification Design and Operation 51 3.1 Purpose and Ultimate Use . 51 3.2 Oak Ridge Fluoride Salt Production Facility . 51 3.3 Wisconsin Purifier Materials Selection . 52 3.4 Wisconsin Fluoride Salt Production Facility . 54 3.4.1 Walk-in Fume Hood and Safety Systems . 55 3.4.2 Purification Vessel . 59 3.4.3 Small Purification Vessel . 61 3.4.4 Support Vessel . 62 3.4.5 Storage Vessel . 63 3.4.6 Salt Filtration . 64 3.4.7 Effluent Stream and Caustic Scrubbers . 66 3.4.8 Electronics . 69 3.4.9 Gas Delivery System . 72 3.4.10 Heating and Insulation . 74 3.5 Data Acquisition and Control . 78 3.5.1 Temperature . 79 3.5.2 Pressure . 81 3.5.3 Mass Flow . 81 3.5.4 Power . 82 3.5.5 Salt Weight . 82 3.5.6 Effluent Stream Composition . 83 3.5.7 Ambient Gas Composition . 84 3.6 Calibration and Uncertainties . 84 3.7 Purification Operation . 85 3.7.1 Personal Protection Equipment . 88 3.7.2 Safeguards . 90 3.7.3 Beryllium Monitoring . 90 3.7.4 Clean Up and Disposal . 93 4 Purification Results 94 4.1 Test Run with KF-ZrF4 ................................ 94 4.1.1 Sparge Gases and Salt Composition . 96 4.1.2 Valve Failure . 96 4.1.3 Heater Leads Oxidation . 97 4.1.4 Effluent Stream Contents . 99 4.1.5 Performance of Filtration Unit . 100 iv 4.1.6 Cleaning . 101 7 4.2 Purification of MSRE LiF-BeF2 (66-34 mol%) . 103 4.2.1 MSRE Flibe Canister and Initial Sampling . 105 4.2.2 Tritium Content . 105 4.2.3 Transfer of MSRE Salts . 107 4.2.4 Purification Process . 109 4.2.5 Purified Salt Contents and Appearance . 110 4.3 ICP-OES and ICP-MS Purity Measurements . 112 4.4 Neutron Activation Analysis . 113 5 Nitrogen Trifluoride Analysis 116 5.1 Selection of Salt for Reactor Use . 116 5.2 Heating the Pure Hydroxides and Reaction with NF3 . 116 5.3 Corrosion of the Experimental Setups . 117 5.4 Flow-Through Experiments . 119 5.5 Static Experiments in Stainless Steel . 119 5.6 Static Experiments in Monel . 122 5.7 XRD Data . 123 5.8 Analysis of Impurity Hydroxide or Oxide in Water . 126 5.9 Flinak Evaluations . 130 6 Modeling of Fluoride Salts 133 6.1 Introduction to Modeling . 133 6.2 Details of First-Principles Molecular Dynamics Simulation . 134 6.3 Evaluation of Thermo-Kinetic Properties from FPMD . 136 6.3.1 Effect of XC-Functional and Dispersion . 137 6.3.2 Thermodynamic Properties of Pure Fluoride Salts . 140 Equilibrium Volume, Density and Bulk Modulus . 140 Coefficient of Thermal Expansion . 143 6.3.3 Kinetic Properties of Pure Fluoride Salts . 144 6.4 FPMD Modeling of Solutes in Fluoride Salts . 148 6.4.1 Diffusion of Solute Ions in Fluoride Salts . 149 6.4.2 Structure Surrounding Solutes in Fluoride Salts . 151 Structure Surrounding Dissolved Cr . ..
Load more

Recommended publications
  • Extensive Interest in Nuclear Fuel Cycle Technologies
    Institute for Science and International Security ISIS REPORT March 19, 2012 Department 70 and the Physics Research Center: Extensive Interest in Nuclear Fuel Cycle Technologies By David Albright, Paul Brannan, Mark Gorwitz, and Andrew Ortendahl On February 23, 2012, ISIS released the report, The Physics Research Center and Iran’s Parallel Military Nuclear Program, in which ISIS evaluated a set of 1,600 telexes outlining a set of departments or buying centers of the former Physics Research Center (PHRC). These departments appeared to be purchasing a variety of goods for specific nuclear technologies, including gas centrifuges, uranium conversion, uranium exploration and perhaps mining, and heavy water production. Figure 1 is a list of the purposes of these departments. The telexes are evaluated in more depth in the February 23, 2012 ISIS report and support that, contrary to Iran’s statements to the International Atomic Energy Agency (IAEA), the PHRC ran a parallel military nuclear program in the 1990s. In the telexes, ISIS identified a department called Department 70 that is linked to the PHRC. This department tried to procure or obtained technical publications and reports from a document center, relevant know-how from suppliers, catalogues from suppliers about particular goods, and a mini- computer from the Digital Equipment Corporation. Department 70 appears to have had personnel highly knowledgeable about the existing literature on a variety of fuel cycle technologies, particularly gas centrifuges. Orders to a British document center reveal many technical publications about gas centrifuges, atomic laser isotope enrichment, the production of uranium compounds including uranium tetrafluoride and uranium hexafluoride (and precursors such as hydrofluoric acid), nuclear grade graphite, and the production of heavy water.
    [Show full text]
  • The Heat of Combustion of Beryllium in Fluorine*
    JOURNAL OF RESEARCH of the National Bureau of Standards -A. Physics and Chemistry Vol. 73A, No.3, May- June 1969 The Heat of Combustion of Beryllium in Fluorine* K. L. Churney and G. T. Armstrong Institute for Materials Research, National Bureau of Standards, Washington, D.C. 20234 (February 11, 1969) An expe rimental dete rmination of the e ne rgies of combustion in Auorine of polyte traAuoroethylene film and Q.o wder and of mixtures of beryllium with polytetraAuoroethyle ne gi ves for reacti on ( 1)f).H ~.or= - 1022.22 kJ 111 0 1- 1 (- 244.32 kcal mol - I) wit h a n ove ra ll precision of 0.96 kJ 111 0 1- 1 (0. 23 kcal 111 0 1- 1 ) at the 95 pe rce nt confid ence limit s. The tota l un cert a int y is estimated not to exceed ±3.2 kJ mol- I (±0.8 kcal mol - I). The measureme nts on polytetraflu oroeth yle ne giv e for reaction (2a) and reacti on (2 b) f).H ~. o c =- 10 369. 7 and - 10392.4 Jg- I, respective ly. Overall precisions e xpressed at the 95 pe rcent confide nce Ijmits are 3.3 and 6.0 Jg- I, respective ly. Be(c)+ F,(g) = BeF2(a morphous) (1) C,F.(polym e r powd er) + 2F2(g) = 2CF.(g) (2a) C2F.(polyme r film ) + 2F2 (g) = 2CF.(g) (2b) Be2C and Be metal were observed in a small carbonaceous residue from the co mbustion of the beryll iul11 -polytetraAuoroethylene mixtures.
    [Show full text]
  • Exposure Data
    BERYLLIUM AND BERYLLIUM eOMPOUNDS Beryllium and beryllium compounds were considered by previous Working Groups, In 1971,1979 and 1987 (lARe, 1972, 1980, 1987a). New data have since become available, and these are included in the present monograph and have been taken into consideration In the evaluation. The agents considered herein Include (a) metallic beryllium, (b) beryllium- aluminium and -copper alloys and (c) some beryllum compounds. 1. Exposure Data 1.1 Chemical and physical data and analysis 1.1.1 Synonyms, trade names and molecular formulae Synonyms, trade names and molecular formulae for beryllium, beryllum-aluminium and -copper alloys and certain beryllium compounds are presented in Thble 1. The list is not exhaustive, nor does it comprise necessarily the most commercially important beryllum- containing substances; rather, it indicates the range of beryllum compounds available. 1. 1.2 Chemical and physical properties of the pure substances Selected chemical and physical properties of beryllium, beryllum-aluminium and -copper alloys and the beryllium compounds covered in this monograph are presented in Thble 2. The French chemist Vauquelin discovered beryllium in 1798 as the oxide, while analysing emerald to prove an analogous composition (Newland, 1984). The metallc element was first isolated in independent experiments by Wöhler (1828) and Bussy (1828), who called it 'glucinium' owing to the sweet taste of its salts; that name is stil used in the French chemical literature. Wöhler's name 'beryllum' was offcially recognized by IUPAe in 1957 (WHO, 1990). The atomic weight and corn mon valence of beryllum were originally the subject of much controversy but were correctly predicted by Mendeleev to be 9 and + 2, respectively (Everest, 1973).
    [Show full text]
  • Detailed Teacher Instructions: Inheritance, X-Linkage, Evolution Over Multiple Generations, Genetic Hitchhiking
    Revised Laboratory on Molecular Evolution Gredler et al. (2015) Detailed Teacher Instructions: Inheritance, X-linkage, Evolution over Multiple Generations, Genetic Hitchhiking Objectives: Between the laboratory exercise and the associated lectures, students will be able to: Explain the process of evolution by natural selection in terms of fitness-related traits and allele frequencies Describe the concept of X-linked inheritance Perform DNA extractions, PCR, and gel electrophoresis Analyze molecular data as a means of understanding an evolutionary process Explain the concepts of selective sweeps, hitchhiking, and linkage Materials: Drosophila melanogaster heat shock white-eyed strain 60739 Drosophila melanogaster heat shock white-eyed strain 60740 Drosophila melanogaster Zimbabwe (wild type) strain 60741 Culture vials, plugs, and food (media) for Drosophila rearing Carolina Biological FlyNap® Anesthetic Kit: 173010 (Optional but strongly preferred) CO2 anesthetization facilities for Drosophila DNA extraction buffer and proteinase-K for DNA isolation Sorting brushes "Squishing buffer" and proteinase-K for DNA isolation Equipment and reagents for polymerase chain reaction including oligonucleotides for "NEAR" and "FAR" markers Equipment and reagents for agarose gel electrophoresis Magnifying glasses Sharpie markers Custom PowerPoints and projector, if desired 1 Revised Laboratory on Molecular Evolution Gredler et al. (2015) This exercise allows students to view evolution over multiple generations, experiment with molecular techniques, and learn concepts of molecular evolution. This exercise requires considerable advance preparation (must be started approximately 6 weeks before planned class start date, with initial white- eyed fly crosses starting approximately 4 weeks before the planned class start date). The supplies and directions are listed out so that you may purchase or use supplies you already have.
    [Show full text]
  • Depleted Uranium Technical Brief
    Disclaimer - For assistance accessing this document or additional information,please contact [email protected]. Depleted Uranium Technical Brief United States Office of Air and Radiation EPA-402-R-06-011 Environmental Protection Agency Washington, DC 20460 December 2006 Depleted Uranium Technical Brief EPA 402-R-06-011 December 2006 Project Officer Brian Littleton U.S. Environmental Protection Agency Office of Radiation and Indoor Air Radiation Protection Division ii iii FOREWARD The Depleted Uranium Technical Brief is designed to convey available information and knowledge about depleted uranium to EPA Remedial Project Managers, On-Scene Coordinators, contractors, and other Agency managers involved with the remediation of sites contaminated with this material. It addresses relative questions regarding the chemical and radiological health concerns involved with depleted uranium in the environment. This technical brief was developed to address the common misconception that depleted uranium represents only a radiological health hazard. It provides accepted data and references to additional sources for both the radiological and chemical characteristics, health risk as well as references for both the monitoring and measurement and applicable treatment techniques for depleted uranium. Please Note: This document has been changed from the original publication dated December 2006. This version corrects references in Appendix 1 that improperly identified the content of Appendix 3 and Appendix 4. The document also clarifies the content of Appendix 4. iv Acknowledgments This technical bulletin is based, in part, on an engineering bulletin that was prepared by the U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (ORIA), with the assistance of Trinity Engineering Associates, Inc.
    [Show full text]
  • Material Safety Data Sheet
    LTS Research Laboratories, Inc. Safety Data Sheet Zirconium fluoride ––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––– 1. Product and Company Identification ––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––– Trade Name: Zirconium fluoride, Zirconium tetrafluoride Chemical Formula: ZrF4 Recommended Use: Scientific research and development Manufacturer/Supplier: LTS Research Laboratories, Inc. Street: 37 Ramland Road City: Orangeburg State: New York Zip Code: 10962 Country: USA Tel #: 855-587-2436 / 855-lts-chem 24-Hour Emergency Contact: 800-424-9300 (US & Canada) +1-703-527-3887 (International) ––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––– 2. Hazards Identification ––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––– Signal Word: Danger Hazard Statements: H314: Causes severe skin burns and eye damage H318: Causes serious eye damage Precautionary Statements: P303+P361+P353: IF ON SKIN (or hair): Remove/Take off immediately all contaminated clothing. Rinse skin with water/shower P305+P351+P338: IF IN EYES: Rinse cautiously with water for several minutes. Remove contact lenses if present and easy to do – continue rinsing P405: Store locked up P501: Dispose of contents/container in accordance with local/regional/national/international regulations HMIS Health Ratings (0-4): Health: 3 Flammability: 0 Physical: 1 –––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––
    [Show full text]
  • Program and Abstracts
    The Atlantic Geoscience Society (AGS) La Société Géoscientifique de l’Atlantique 44th Colloquium and Annual Meeting Special Sessions: • Basin-forming processes during supercontinent assembly: New insights from the Devono-Permian record of Atlantic Canada • Paleontology and Sedimentology in the Maritimes and Beyond • Advances in Assessing Arctic Geohazards • Methane Emissions from Legacy Fossil Fuel Sites in the Maritimes • Rocks, maps, and tectonic models • Records of Environmental Change from the Atlantic Provinces and Beyond • The Meguma Terrane: Its place in the Appalachian Orogen and beyond • AGS Outreach innovations: Past, Present and Future General Sessions: Current Research in the Atlantic Provinces 2-3 February, 2018 Holiday Inn, Truro, Nova Scotia PROGRAM WITH ABSTRACTS We gratefully acknowledge sponsorship from the following companies and organizations: Department of Energy Department of Natural Resources Welcome to the 44th Colloquium and Annual Meeting of the Atlantic Geoscience Society in Truro. We have returned to Truro this year, following many positive comments about the facility and the convenience of meeting in the “Hub of Nova Scotia”. You provided a plethora of special sessions, making for a very full program this year! We hope we have managed to arrange schedules so that you will be informed and stimulated by the posters and presentations. AGS members are clearly pushing the boundaries of geoscience in all its branches! Be sure to take in the science on the posters downstairs in the Elm Room and the displays from sponsors in the lower level foyer. And don’t miss the after-banquet jam and open mike on Saturday night. For social media types, please consider sharing updates on Facebook.
    [Show full text]
  • Molten Salts As Blanket Fluids in Controlled Fusion Reactors [Disc 6]
    r1 0 R N L-TM-4047 MOLTEN SALTS AS BLANKET FLUIDS IN CONTROLLED FUSION REACTORS W. R. Grimes Stanley Cantor .:, .:, .- t. This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or their employees, 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. om-TM- 4047 Contract No. W-7405-eng-26 REACTOR CHENISTRY DIVISION MOLTEN SALTS AS BLANKET FLUIDS IN CONTROLLED FUSION REACTORS W. R. Grimes and Stanley Cantor DECEMBER 1972 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the 1J.S. ATOMIC ENERGY COMMISSION This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or 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 disclosed, or represents that its use would not infringe privately owned rights. i iii CONTENTS Page Abstract ............................. 1 Introduction ........................... 2 Behavior of Li2BeFq in a Eypothetical CTR ............3 Effects of Strong Magnetic Fields .............5 Effects on Chemical Stability .............5 Effects on Fluid Dynamics ...............7 Production of Tritium ..................
    [Show full text]
  • Monitoring and Diagnosis Systems to Improve Nuclear Power Plant Reliability and Safety. Proceedings of the Specialists` Meeting
    J — v ft INIS-mf—15B1 7 INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR ELECTRIC Ltd. Monitoring and Diagnosis Systems to Improve Nuclear Power Plant Reliability and Safety PROCEEDINGS OF THE SPECIALISTS’ MEETING JOINTLY ORGANISED BY THE IAEA AND NUCLEAR ELECTRIC Ltd. AND HELD IN GLOUCESTER, UK 14-17 MAY 1996 NUCLEAR ELECTRIC Ltd. 1996 VOL INTRODUCTION The Specialists ’ Meeting on Monitoring and Diagnosis Systems to Improve Nuclear Power Plant Reliability and Safety, held in Gloucester, UK, 14 - 17 May 1996, was organised by the International Atomic Energy Agency in the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) and the International Task Force on NPP Diagnostics in co-operation with Nuclear Electric Ltd. The 50 participants, representing 21 Member States (Argentina, Austria, Belgium, Canada, Czech Republic, France, Germany, Hungary, Japan, Netherlands, Norway, Russian Federation, Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, Ukraine, UK and USA), reviewed the current approaches in Member States in the area of monitoring and diagnosis systems. The Meeting attempted to identify advanced techniques in the field of diagnostics of electrical and mechanical components for safety and operation improvements, reviewed actual practices and experiences related to the application of those systems with special emphasis on real occurrences, exchanged current experiences with diagnostics as a means for predictive maintenance. Monitoring of the electrical and mechanical components of systems is directly associated with the performance and safety of nuclear power plants. On-line monitoring and diagnostic systems have been applied to reactor vessel internals, pumps, safety and relief valves and turbine generators. The monitoring techniques include nose analysis, vibration analysis, and loose parts detection.
    [Show full text]
  • Patent Office
    Patented Mar. 12, 1940 2,193,364 UNITED STATES PATENT OFFICE 2,193,364 PROCESS FOR OBTANING BEEY UMAND BERYLUMAL LOYS Carlo Adamoli, Milan, Italy, assignor to Perosa Corporation, Wilmington, Oel, a corporation of Delaware No Drawing. Application April 17, 1939, Serial No. 268,385. a tally June 6, 1936 16 Claims. (C. 5-84) The present application relates to a process ical method for the production of beryllium and for directly obtaining in a single operation start its alloys by treatment with a decomposing bi ing from halogenated compounds containing be valent metal such as magnesium, of a fluorine ryllium, beryllium as such or in the state of alloys containing compound of beryllium, that is a 5 with one or more alloyed elements capable of double fluoride of beryllium and an alkali metal 5 alloying with beryllium, and is a continuation-in (sodium) less rich in sodium fluoride than the part of my prior application Ser. No. 144,411 filed normal double fluoride BeFa2NaF. on May 24, 1937. The practical impossibility in fact has been In my said prior application, I have disclosed established which is met with in operating with 0 a process for directly obtaining in a single oper the normal double fluoride according to the re o ation beryllium or beryllium alloys starting from action: simple beryllium fluoride anhydrous and free or Substantially free from oxide. The present in which is rendered explosive by reason of the lib vention relates more particularly to a process eration of sodium and this is the reason in par s 5 of manufacture of beryllium or beryllium alloys ticular why instead of the normal double fluo starting from normal double fluoride of beryllium ride BeF2.2NaF the complex fluoride BeFa.NaF and an alkali-metal, the term “normal' being in is treated according to the reaction: tended to designate double fluorides containing ! 2BeFaNaF.--Mg-Be--MgF2--BeF2,2NaF two molecules of alkali fluoride for one molecule 20 of beryllium fluoride.
    [Show full text]
  • Molten-Salt Technology and Fission Product Handling
    Molten-Salt Technology and Fission Product Handling Kirk Sorensen Flibe Energy, Inc. ORNL MSR Workshop October 4, 2018 2018-10-16 Hello, my name is Kirk Sorensen and I’d like to talk with you today about fission products and their handling in molten-salt reactors. One of the things that initially attracted me to molten-salt reactor technology was the array of options that it gave for the intelligent handling of fission products. It represented such a contrast to solid-fueled systems, which mixed fission products in with unburned nuclear fuel in a form that was difficult to separate, one from another. While my focus will be on our work on molten-salt reactor fission product handling, many of the principles are general to molten-salt reactors as a whole. Fundamental Nuclear Reactor Concept In its simplest form, a nuclear reactor generates thermal energy that is carried away by a coolant. That coolant heats the working fluid of a power conversion system, which generates electricity from part of the thermal energy and rejects the remainder to the environment. coolant working fluid fresh fuel electricity Power Nuclear Heat Conversion Reactor Exchanger System spent fuel heated water or air coolant working fluid The primary coolant chosen for a nuclear reactor determines, in large part, its size and manufacturability. The temperature of the coolant determines the efficiency of electrical generation. Fundamental Nuclear Reactor Concept In its simplest form, a nuclear reactor generates thermal energy that is carried away by a coolant. That coolant heats the working fluid of a power conversion system, which generates electricity from part of the thermal energy and rejects the remainder to the environment.
    [Show full text]
  • 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.
    [Show full text]