14. the Design of Plants for Handling Hydrofluoric Acid K. M. Hill
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Aero-Flex Corporation 3147 Jupiter Park Circle Suite 2 Jupiter, Florida 33458 (561) 745-2534
Aero-Flex Corporation 3147 Jupiter Park Circle Suite 2 Jupiter, Florida 33458 (561) 745-2534 QUALITY WITHOUT QUESTION Flexible Metal Hose Assemblies Corrugated Metal Hoses that we offer: Hose Master Hoses OmegaFlex Hoses Penflex Hoses ANNUFLEX 700 Series Abrasion Resistant Tubular Braid for 1SBX Braid for 700 Series Hose Annuflex 700 Series Series 300 Hose- Stainless Steel Bronze Braid T304 Bronzeflex 1100 Series Monel Braid Bronze Tubular Braid for Series 400 ChemKing™ Hose Series 400 Stainless Steel Hose Monel Tubular Braid for Series 500 Series 600 Stainless Steel Braid ChlorSafe™ Hose Series 600 Stainless Steel Hose Series 100 - Helical, Stainless Steel, Series 700 Stainless Steel and Extraflex 9000 Series Standard Pitch Hose Compressed Hose Formaflex 900 Series Series 300 - Annular, Stainless Steel, Series 740 Monel Hose Standard Pitch Hose Series 794 Bronze Hose Hydraflex 9400 Series Series 400 - Annular, Bronze, Standard Pitch Hose Series 800 High Pressure Braid Interflex Series 800 Stainless Steel Hose Series 500 - Annular, Monel, Standard Pitch Hose Series 900 High Pressure Braid Masterflex 500 Series Series 900 Stainless Steel Hose Series 800 - Annular, Stainless Steel, Pressureflex HP High Pressure Hose and Braid Series P3 Stainless Steel Braid PressureMax HP Series P3 Stainless Steel Hose Tubular Braid for Series 100 Hose - Stainless Steel T304, T321 and T316 Stainless Steel Braid for Series Tar and Asphalt 400 Helical Hose Tubular Braid for Series 300 Stainless Steel Standard Braid for Ultraflex Braided Braid for Series 300 Series 700 Hose 1/4 - 12 inch 304, 316, & 321 Stainless Steel Single or Double Braid Why Flex Hose? It is comparatively light weight, temperature resistance, has great pressure retention, and allows for variance in fit up and alignment. -
Elemental Fluorine Product Information (Pdf)
Elemental Fluorine Contents 1 Introduction ............................................................................................................... 4 2.1 Technical Application of Fluorine ............................................................................. 5 2.2 Electronic Application of Fluorine ........................................................................... 7 2.3 Fluorine On-Site Plant ............................................................................................ 8 3 Specifications ............................................................................................................ 9 4 Safety ...................................................................................................................... 10 4.1 Maintenance of the F2 system .............................................................................. 12 4.2 First Aid ................................................................................................................ 13 5.1 Chemical Properties ............................................................................................. 14 5.2 Physical Data ....................................................................................................... 15 6 Toxicity .................................................................................................................... 18 7 Shipping and Transport ........................................................................................... 20 8 Environment ........................................................................................................... -
International Conference on Nuclear Criticality Safety
OFFICIAL PROGRAMPREVIEW International Conference on Nuclear Criticality Safety International Cooperation Hosted by the Nuclear Criticality Safety Division of the American Nuclear Society Co-Sponsored by NEA Photo by Randy Montoya/SandiaPhoto Randy by Laboratories National September 13-17, 2015 Omni Charlotte Hotel Charlotte, NC 2015 International Conference on Nuclear Criticality Safety Our most sincere thanks to the following contributors for their support Gold Level Silver Level Bronze Level Other Table of Contents General Meeting Information Conference Officials 4 Schedule at a Glance 5 Daily Schedule 6-7 General Information 8 Plenary and Special Sessions Welcome Reception 9 Opening Plenary 9 Reception at the Mint Museum 9 ICNC Poster Session and Reception 10 Banquet Dinner at Founders Hall 10 ICNC Workshop 10 V.C. Summer Nuclear AP1000® Nuclear Plant 10 International Cooperation Construction Tour Columbia Fuel Fabrication Facility Plant Tour 10 Technical Sessions Technical Sessions by Day: Monday 11-12 Technical Sessions by Day: Tuesday 13-16 Technical Sessions by Day: Wednesday 17-20 Technical Sessions by Day: Thursday 21-22 Additional Hotel Map 23 www.ans.org 2015 International Conference on Nuclear Criticality Safety: Official Program 3 Meeting Officials International Cooperation International Conference on Nuclear Criticality Safety Every 4 years the international nuclear criticality safety community gathers to discuss technical, operational, computational, and regulatory issues in the practice of nuclear criticality safety. ICNC 2015 (International Conference on Nuclear Criticality) allows specialists from around the globe to come together to discuss, analyze and study the latest developments in the area of nuclear criticality safety. This is a unique opportunity to exchange ideas with industry experts, leaders, colleagues and peers. -
Stainless Steel Selection Guide
TAContentsBLE OF Discovery of Stainless Steel . .page 2 What is Stainless Steel . .page 3 Stainless Steel Classifications . .page 4 • Austenitic . .page 4 • Ferritic . .page 5 • Duplex . .page 5 • Martensitic . .page 6 • Precipitation Hardening . .page 6 Nickel Based Alloys . .page 7 Strength & Heat Treatment . .page 7 The Basics of Corrosion . .page 8 • General or Uniform Corrosion . .page 9 • Galvanic Corrosion . .page 11 • Pitting Corrosion . .page 11 • Crevice Corrosion . .page 13 • Intergranular Corrosion . .page 14 • Stress Corrosion Cracking . .page 15 • Microbiologically Influence Corrosion . .page 17 Welding Stainless Steel . .page 18 Alloy Selection . .page 22 Wrought Stainless Steel Composition . .page 24 Wrought Nickel Alloy Composition . .page 25 Stainless Steel and Nickel Alloy Filler Metal . .page 26 PR“It’sEF stainlessAC steel,E it shouldn’t rust” This is often the kind of statements heard from individuals when discussing a failure of process piping or equipment. This is also an indication of how little is actually understood about stainless steel and the applications where it is used. For years the food, beverage and pharmaceutical industries have used stainless steels in their process piping systems. Most of the time stainless steel components provide satisfactory results. Occasionally a catastrophic failure will occur. The purpose of the information contained within this document is to bring an understanding to stainless steel, it’s uses, and why it will fail under certain conditions. In the following pages we will discuss the different classes of stainless steel, heat treatment, corrosion, welding, and finally material selection. As with any failure, it is imperative the cause of the failure be identified before a proper fix can be recognized. -
Onr Corporate Plan 2017/18 En Route to 2020
ONR CORPORATE PLAN 2017/18 EN ROUTE TO 2020 Office for Nuclear Regulation Corporate Plan 2017/18 Financial year 1 April 2017 to 31 March 2018 Presented to Parliament pursuant to Paragraphs 23 and 25(3) of Schedule 7 to the Energy Act 2013 July 2017 © ONR copyright 2017 The text of this document (this excludes, where present, the Royal Arms and all departmental or agency logos) may be reproduced free of charge in any format or medium provided that it is reproduced accurately and not in a misleading context. The material must be acknowledged as ONR copyright and the document title specified. Where third party material has been identified, permission from the respective copyright holder must be sought. Any enquiries related to this publication should be sent to us at [email protected] This publication is available at https://www.gov.uk/government/publications Print ISBN 9781474145695 Web ISBN 9781474145701 ID P002881793 06/17 Printed on paper containing 75% recycled fibre content minimum Printed in the UK for Williams Lea Group on behalf of the Controller of Her Majesty’s Stationery Office CONTENTS 1. Foreword .........................................................................................................1 2. About this plan ..............................................................................................3 3. Our Operating Environment .........................................................................9 4. Our Strategic Themes and Key Activities ....................................................15 Influencing improvements -
Nuclear Decommissioning Authority
Nuclear Decommissioning Authority Infrastructure Development Working Group Meeting 8 May 2014 Natasha Hanson Head of People Relations Skills Challenges Growing Global Demand for Nuclear Skills An Ageing Workforce The NDA Estate Wide Resource Profile NDA Total Resource Gap - 2012 to 2026 18000 Shortage = -1395 17000 16000 15000 Excess = +930 14000 13000 Total Demand Attrition 2.5% pa 12000 11000 Full Time Equivalent Number 10000 9000 8000 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 2025 2026 Year 3 NDA Estate Wide & New Nuclear Build Requirements NDA Estate and New Build Requirements 28000 26000 24000 22000 20000 18000 16000 14000 NDA Estate 12000 New Build 10000 Total 8000 Full Time Equivalent Number 6000 4000 2000 0 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 2025 2026 Year 4 NDA Estate Resource Issues • Acceleration of de-commissioning leading to early release of nuclear resources • Low staff attrition (average of 2% for staff) • Higher attrition of ASW staff – dependent on economic climate, opportunities within the catchment and scarcity of skill • Over next 15 years at least 34% of the workforce will reach pensionable age • Implied recruitment of 18% of existing population over the next 15 years • Approach (overall) is to continue with apprentice, and graduate training schemes and development of the current workforce 5 Skills Priorities High Priorities Other Priorities • Project / Programme Managers • Design Engineers / Technicians • Construction Project Managers • Quality Assurance • Steel -
Research a He Edge of Sp Ce Contents I Mission and Accomplishmen Ts
https://ntrs.nasa.gov/search.jsp?R=19640004493 2020-03-11T17:07:03+00:00Z RESEARCH A HE EDGE OF SP CE CONTENTS I MISSION AND ACCOMPLISHMEN TS . .. 1 II EARLIER RESEARCH AIRCRAFT ................. 5 III CONCEPT, HISTORY, AND TECH NICAL CONSIDERATIONS ... 11 IV THE X-15 FLIGH T PROGRAM ................. _ 19 V FUTURE ......... ................... _ 31 ~O';).,IOOO Q. ~ !y f) S 1+) tJ~'(j 1;"v -' ~,I!.-. RESEARCH AT THE EDGE OF SPACE I (/1 5 E F_ '!) CPO ' ~ () I 3 D -1: 1 For sale by the Superintendpnt of Documents, U.S. Government Printing Office 1. ~ ~ : ashington, D.C ., 20402- PriceToCeiits -.-, NASA Ep·9 - - ------- -.--------~~- ~--- .- - -- MISSION AND ACCOMPLISHMENTS , l_ - .-- -- ------ ---- - - I In the fall of 1963, the X-IS completed a series of dental to the goals of the program. The real mis flights at speeds and altitudes never before attained sion of the X-IS is a quest for knowledge. In carry by any vehicle fully controlled by a pilot from launch ing out this mission, the X-IS has made a number to landing on the ground. In the process of making of substantial contributions to the advancement of almost 100 successful flights, it had essentially aerospace science. completed its original program of fli ght research Although primarily an aeronautical vehicle with and had begun to carry out additional aerospace wings and aerodynamic controls, the aircraft travels experiments. well beyond the effective atmosphere on most of its From conception through the phases of design, flights_ At extreme altitudes, the pilot controls the construction, test, and operation, it had rounded out X-IS by reaction jets, like a spacecraft; he is some 11 years of exploring a variety of technological weightless for brief periods, and the research plane and scientific problems. -
Magnox Electric Plc's Strategy for Decommissioning Its Nuclear
A review by HM Nuclear Installations Inspectorate Magnox Electric plc’s strategy for decommissioning its nuclear licensed sites A review by HM Nuclear Installations Inspectorate Magnox Electric plc’s strategy for decommissioning its nuclear licensed sites Published by the Health and Safety Executive February 2002 Further copies are available from: Health and Safety Executive Nuclear Safety Directorate Information Centre Room 004 St Peter’s House Balliol Road, Bootle Merseyside L20 3LZ Tel: 0151 951 4103 Fax: 0151 951 4004 E-mail: [email protected] Available on the Internet from: http://www.open.gov.uk/hse/nsd ii FOREWORD This report sets out the findings of a review by the Health and Safety Executive’s Nuclear Installation Inspectorate, in consultation with the environment agencies, of the Magnox Electric plc (Magnox Electric) decommissioning and waste management strategies for its nuclear licensed sites. The review was undertaken in accordance with the 1995 White Paper “Review of Radioactive Waste Management Policy: Final Conclusions”, Cm 2919, which stated that the Government would ask all nuclear operators to draw up strategies for the decommissioning of their redundant plant and that the Health and Safety Executive (HSE) would review these strategies on a quinquennial basis in consultation with the environment agencies. The Magnox Electric strategy upon which this review is based was prepared subsequent to the merger of Magnox Electric with British Nuclear Fuels plc (BNFL) but whilst it still remained a separate nuclear site licensee under the Nuclear Installations Act 1965 (as amended). This report therefore considers Magnox Electric’s decommissioning and waste management strategies as of April 2000 for its nuclear licensed sites at: Berkeley, Bradwell, Dungeness A, Hinkley Point A, Hunterston A, Oldbury, Sizewell A, Trawsfynydd and Wylfa; and at the Berkeley Centre; and for the financial liabilities for waste and decommissioning on other nuclear licensed sites (e.g. -
Containing Alloys in Hydrochloric Acid, Hydrogen Chloride and Chlorine (Ceb-3)
CORROSION RESISTANCE OF NICKEL AND NICKEL- CONTAINING ALLOYS IN HYDROCHLORIC ACID, HYDROGEN CHLORIDE AND CHLORINE (CEB-3) A PRACTICAL GUIDE TO THE USE OF NICKEL-CONTAINING ALLOYS NO 279 Distributed by Produced by NICKEL INCO INSTITUTE CORROSION RESISTANCE OF NICKEL AND NICKEL-CONTAINING ALLOYS IN HYDROCHLORIC ACID, HYDROGEN CHLORIDE AND CHLORINE (CEB-3) A PRACTICAL GUIDE TO THE USE OF NICKEL-CONTAINING ALLOYS NO 279 This handbook was first published prior to 1985 by INCO, The International Nickel Company, Inc. Today this company is part of Vale S.A. The Nickel Institute republished the handbook in 2020. Despite the age of this publication the information herein is considered to be generally valid. Material presented in the handbook has been prepared for the general information of the reader and should not be used or relied on for specific applications without first securing competent advice. The Nickel Institute, their members, staff and consultants do not represent or warrant its suitability for any general or specific use and assume no liability or responsibility of any kind in connection with the information herein. Nickel Institute [email protected] www.nickelinstitute.org Nickel-clad steel jacketed reactor used for organic chlorinations. It was built in accordance with the A.P.I. A.S.M.E. code for unfired pressure vessels and operates at a temperature of 650° F, and pressures of 25 lb. per sq. in in the body and 125 Ib per sq. in. in the jacket. Page 2 Resistance of Nickel and High Nickel Alloys to Corrosion by Hydrochloric Acid, Hydrogen Chloride and Chlorine† CONTENTS HYDROCHLORIC ACID ................................................. -
Enghandbook.Pdf
785.392.3017 FAX 785.392.2845 Box 232, Exit 49 G.L. Huyett Expy Minneapolis, KS 67467 ENGINEERING HANDBOOK TECHNICAL INFORMATION STEELMAKING Basic descriptions of making carbon, alloy, stainless, and tool steel p. 4. METALS & ALLOYS Carbon grades, types, and numbering systems; glossary p. 13. Identification factors and composition standards p. 27. CHEMICAL CONTENT This document and the information contained herein is not Quenching, hardening, and other thermal modifications p. 30. HEAT TREATMENT a design standard, design guide or otherwise, but is here TESTING THE HARDNESS OF METALS Types and comparisons; glossary p. 34. solely for the convenience of our customers. For more Comparisons of ductility, stresses; glossary p.41. design assistance MECHANICAL PROPERTIES OF METAL contact our plant or consult the Machinery G.L. Huyett’s distinct capabilities; glossary p. 53. Handbook, published MANUFACTURING PROCESSES by Industrial Press Inc., New York. COATING, PLATING & THE COLORING OF METALS Finishes p. 81. CONVERSION CHARTS Imperial and metric p. 84. 1 TABLE OF CONTENTS Introduction 3 Steelmaking 4 Metals and Alloys 13 Designations for Chemical Content 27 Designations for Heat Treatment 30 Testing the Hardness of Metals 34 Mechanical Properties of Metal 41 Manufacturing Processes 53 Manufacturing Glossary 57 Conversion Coating, Plating, and the Coloring of Metals 81 Conversion Charts 84 Links and Related Sites 89 Index 90 Box 232 • Exit 49 G.L. Huyett Expressway • Minneapolis, Kansas 67467 785-392-3017 • Fax 785-392-2845 • [email protected] • www.huyett.com INTRODUCTION & ACKNOWLEDGMENTS This document was created based on research and experience of Huyett staff. Invaluable technical information, including statistical data contained in the tables, is from the 26th Edition Machinery Handbook, copyrighted and published in 2000 by Industrial Press, Inc. -
Gasket CRITERIA
Gasket CRITERIA. designcriteria 04-14_inside 3/24/2016 1:46 PM Page 1 GasketDesignCriteria TableofContents Page ManufacturingUnits 2 Introduction 3 SectionI-GasketSelection 4 Change Gasket ................................................................................................................................ 6 Sheet Materials ................................................................................................................................ 8 Thermiculite® .................................................................................................................................... 9 PTFE Products - Sigma® ................................................................................................................... 12 PTFE Products - Fluoroseal .............................................................................................................. 14 Flexitallic Flexicarb® .......................................................................................................................... 15 Compressed Fiber Gasket ................................................................................................................ 16 Core4 Sheet Products ...................................................................................................................... 17 Sheet Materials Chemical Compatibility Chart ................................................................................. 18 Insulating Sets ................................................................................................................................. -
Nuclear Fuel Cycle Information System
IAEA-TECDOC-1613 Nuclear Fuel Cycle Information System A Directory of Nuclear Fuel Cycle Facilities 2009 Edition April 2009 IAEA-TECDOC-1613 Nuclear Fuel Cycle Information System A Directory of Nuclear Fuel Cycle Facilities 2009 Edition April 2009 The originating Section of this publication in the IAEA was: Nuclear Fuel Cycle and Materials Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria NUCLEAR FUEL CYCLE INFORMATION SYSTEM: A DIRECTORY OF NUCLEAR FUEL CYCLE FACILITIES 2009 EDITION IAEA, VIENNA, 2009 ISBN 978–92–0–102109–0 ISSN 1011–4289 © IAEA, 2009 Printed by the IAEA in Austria April 2009 FOREWORD In recent years, there have been rising expectations for nuclear power all over the world to meet the ever increasing demand for electricity. Several countries with nuclear power have declared intentions to build new nuclear power plants to replace their existing capacities or to add new capacities. Several other countries without nuclear power are taking an active interest in launching nuclear power programmes. Nuclear power and nuclear fuel cycle go hand in hand. Hence implementations of such nuclear power programmes cannot be considered without parallel development in the nuclear fuel cycle area. The worldwide nuclear fuel cycle industry comprises several global players which are operating on a commercial basis in more than one country and many other domestic players which are active only in their respective countries. Knowing the current status and the future outlook of the nuclear fuel cycle industry is important not only for meeting the needs of global nuclear power development but also for facilitating the multilateral approach to the nuclear fuel cycle currently being discussed with a focus on ‘assurance of fuel supply’ and ‘non-proliferation of nuclear materials’.