DOCSLIB.ORG

Literature Survey on the Stress Corrosion Cracking of Low-Alloy Steels in High-Temperature Water

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Literature Survey on the Stress Corrosion Cracking of Low-Alloy Steels in High-Temperature Water CH0200021 O o hi Q> PAUL SCHERRER INSTITUT PSI Bericht Nr. 02-06 CQ February 2002 5) ISSN 1019-0643 a Nuclear Energy and Safety Division Laboratory for Materials Behaviour Literature Survey on the Stress Corrosion Cracking of Low-Alloy Steels in High-Temperature Water H.P. Seifert Paul Scherrer Institut CH - 5232 Villigen PSI 33/13 Telefon 056 310 21 11 Telefax 056 310 21 99 Literature Survey on the Stress Corrosion Cracking of Low-Alloy Steels in High-Temperature Water H.P. Seifert Nuclear Energy and Safety Division Laboratory for Materials Behaviour Structural Integrity Group Abstract The present report is a summary of a literature survey on the stress corrosion cracking (SCC) behaviour/ mechanisms in low-alloy steels (LAS) in high-temperature water with special emphasis to primary-pressure-boundary components of boiling water reactors (BWR). A brief overview on the current state of knowledge concerning SCC of low-alloy reactor pressure vessel and piping steels under BWR conditions is given. After a short introduction on general aspects of SCC, the main influence parameter and available quantitative literature data concerning SCC of LAS in high-temperature water are discussed on a phenomenological basis followed by a summary of the most popular SCC models for this corrosion system. The BWR operating experience and service cracking incidents are discussed with respect to the existing laboratory data and background knowledge. Finally, the most important open questions and topics for further experimental investigations are outlined. TABLE OF CONTENTS ABSTRACT 2 INDEX 4 0. ABBREVIATIONS 6 1. INTRODUCTION 8 1.1 REPORT OUTLINE 8 1.2 REFERENCES 9 2. GENERAL ASPECTS OF STRESS CORROSION CRACKING 10 2.1 ENVIRONMENTALLY-ASSISTED CRACKING 10 2.2 BASIC ASPECTS AND CHARACTERISTIC FEATURES OF SCC 12 2.3 LABORATORY EAC TEST METHODS AND THEIR RELEVANCE TO LWR COMPONENTS .. 17 3. SCC/SICC OF LOW-ALLOY STEELS IN HIGH-TEMPERATURE WATER 19 3.1 MAIN INFLUENCING FACTORS FOR SCC/SICC 19 3.2 SCC/SICC SUSCEPTIBILITY CONDITIONS 19 3.3. ENVIRONMENTAL PARAMETERS 22 3.4 MECHANICAL/LOADING PARAMETERS 30 3.5 MATERIAL PARAMETERS 32 3.6 INCUBATION PERIOD 36 3.7. QUANTITATIVE SCC/SICC CRACK GROWTH RATE DATA 36 4. MECHANISTICAL ASPECTS OF EAC OF LAS 41 4.1 CRACK GROWTH MECHANISMS 41 4.2 LOCAL CRACK-TIP CHEMISTRY AND MASS TRANSPORT 58 4.3 CRACK-TIP ELECTRO- AND WATER CHEMISTRY IN LAS UNDER LWR CONDITIONS 63 4.4 DISCUSSION OF SOME SPECIFIC ASPECTS OF CRACK CHEMISTRY AND EAC 64 5. LWR OPERATING EXPERIENCE AND EAC CRACKING INCIDENTS 74 5.1 EAC CRACKING INCIDENTS IN LWR 74 5.2 OPERATING EXPERIENCE VS. LABORATORY BACKGROUND KNOWLEDGE 78 5.3 POSSIBLE EAC PREVENTION STRATEGIES AND MITIGATION ACTIONS 81 6. OPEN QUESTIONS AND NEEDS FOR FUTURE WORK 83 6.1 CORROSION FATIGUE/ STRAIN-INDUCED CORROSION CRACKING 83 6.2 STRESS CORROSION CRACKING 85 7. EXTENDED SUMMARY AND CONCLUSIONS 87 8. ACKNOWLEDGEMENT 91 9. REFERENCES 92 INDEX ABSTRACT 2 INDEX 4 0. ABBREVIATIONS 6 1. INTRODUCTION 8 1.1 REPORT OUTLINE 8 1.2 REFERENCES 9 2. GENERAL ASPECTS OF STRESS CORROSION CRACKING 10 2.1 ENVIRONMENTALLY-ASSISTED CRACKING 10 2.1.1 Types of EAC 10 2.1.2 Classical and Non-Classical SCC 10 2.2 BASIC ASPECTS AND CHARACTERISTIC FEATURES OF SCC 12 2.2.1 SCC Fracture Features 13 2.2.2 Crack Initiation vs. Crack Growth 13 2.2.3 SCC Crack Growth Rate vs. Stress Intensity Factor Curves 75 2.3 LABORATORY EAC TEST METHODS AND THEIR RELEVANCE TO LWR COMPONENTS .. 17 3. SCC/SICC OF LOW-ALLOY STEELS IN HIGH-TEMPERATURE WATER.. 19 3.1 MAIN INFLUENCING FACTORS FOR SCC/SICC 19 3.2 SCC/SICC SUSCEPTIBILITY CONDITIONS 19 3.3. ENVIRONMENTAL PARAMETERS 22 3.3.1 Temperature 22 3.3.2 ECP and Oxygen Content 25 3.3.3 Sulphate Concentration of Environment 27 3.3.4 Possible Irradiation Effects on EAC 28 3.4 MECHANICAL/LOADING PARAMETERS 30 3.4.1 Critical Strain-rates and Strains 30 3.4.2 Stress Intensity Factor Threshold for SCC KJSCC 32 3.5 MATERIAL PARAMETERS 32 3.5.1 Steel Sulphur-Content, MnS-Inclusions 32 3.5.2 Yield Strength Rp, Micro structure 34 3.5.3 Dynamic Strain Ageing, Free Nitrogen and Carbon Content in Steel 35 3.6 INCUBATION PERIOD 36 3.7. QUANTITATIVE SCC/SICC CRACK GROWTH RATE DATA 36 3.7.1 SICC Crack Growth Rates 36 3.7.2 SCC Crack Growth Rates andKiscc 37 3.7.3 Possible Reasons for Data Scatter and High SCC Crack Growth Rates 39 4. MECHANISTICAL ASPECTS OF EAC OF LAS 41 4.1 CRACK GROWTH MECHANISMS 41 4.1.1 Film Rupture / Anodic Dissolution Mechanism (FRAD) 41 4.1.2 Hydrogen-Assisted EAC (HAEAC) 46 4.1.2.1 Sources of Hydrogen in LAS under LWR Conditions 46 4.1.2.2 Effects of Hydrogen [see references in 20, 140-144, 160-163] 46 4.1.2.3 General Aspects of HAEAC in Aqueous Environments 47 4.1.2.4 HAEAC Model for LAS under LWR Conditions 49 4.1.2.5 HAEAC vs. FRAD 50 4.1.3 Dynamic Strain Ageing (DSA) 52 4.1.3.1 Background 52 4.1.3.2 Phenomenological and Microscopical Features of DSA 52 4.3.1.3 Physical Metallurgy of DSA 53 4.1.3.5 Possible Interaction between DSA and EAC in LAS 57 4.2 LOCAL CRACK-TIP CHEMISTRY AND MASS TRANSPORT 58 4.2.1 Basic Concepts of Crack Chemistry in Low-Alloy Steels under LWR Conditions 58 4.2.2 Differential Aeration Cell at the Crack Mouth 60 4.2.3 Dissolution Cell at the Crack-Tip 60 4.2.4 Mass Transport Process in the Crack Enclave 61 4.2.5 Critical Crack-Tip Sulphur-Anion Concentration for EAC 61 4.3.6 Critical Crack Growth Rate for EAC 62 4.3 CRACK-TIP ELECTRO- AND WATER CHEMISTRY IN LAS UNDER LWR CONDITIONS 63 4.3.1 Crack-Tip ECP 63 4.3.2 Crack-Tip pH and Crack-Tip Sulphur-Anion Concentration 63 4.3.3 Crack-Tip Conductivity 63 4.4 DISCUSSION OF SOME SPECIFIC ASPECTS OF CRACK CHEMISTRY AND EAC 64 4.4.1 ECP and Dissolved Oxygen Content 64 4.4.2 Impurity Content and Conductivity 64 4.4.3 Effect of MnS-Inclusions 65 4.4.4 Asymmetry of Transients and Hysteresis Effects 66 4.4.5 Effect of Flow Rate 69 5. LWR OPERATING EXPERIENCE AND EAC CRACKING INCIDENTS 74 5.1 EAC CRACKING INCIDENTS IN LWR 74 5.1.1 Common Features of EAC Cracking Incidents 74 5.1.2 EAC of BWR RPV Feedwater Nozzles 76 5.1.3 SICC of Thin-Walled Pipings in German BWR 77 5.2 OPERATING EXPERIENCE VS. LABORATORY BACKGROUND KNOWLEDGE 78 5.2.1 Reasons for Higher EAC Cracking Frequency in Laboratory Tests 79 5.2.2 Reasons for High SCC Cracking Susceptibility in Some Lab Tests 80 5.2.3 Summary 80 5.3 POSSIBLE EAC PREVENTION STRATEGIES AND MITIGATION ACTIONS 81 5.3.1 Critical Components 82 5.3.2 Mitigation Actions 82 6. OPEN QUESTIONS AND NEEDS FOR FUTURE WORK 83 6.1 CORROSION FATIGUE/ STRAIN-INDUCED CORROSION CRACKING 83 6.2 STRESS CORROSION CRACKING 85 7. EXTENDED SUMMARY AND CONCLUSIONS 87 8. ACKNOWLEDGEMENT 91 9. REFERENCES 92 0. Abbreviations ASME American Society of Mechanical Engineers ASME BPV ASME Boiler and Pressure Vessel Code ASTM American Society of Testing and Materials ASTME399 Test Method for Plane-Strain Fracture Toughness of Metallic Materials BWR Boiling Water Reactor BWR VIP Boiling Water Reactor Vessel and Internals Project C(T) Compact Tension Specimen CERT Constant Extension Rate Test CF Corrosion Fatigue CGR Crack Growth Rate CODLL Crack Opening Displacement at Load Line DCPD Direct Current Potential Drop Method DO Dissolved Oxygen DSA Dynamic Strain Ageing EAC Environmentally-Assisted Cracking ECP Electrochemical Corrosion Potential EPFM Elastic-Plastic Fracture Mechanics EPRI Electric Power Research Institute FRAD Firm Rupture/Anodic Dissolution Mechanism FW Feed Water GÈ General Electric HAEAC Hydrogen-Assisted EAC Mechanism HAZ Heat-Affected Zone HSK Hauptabteilung für die Sicherheit der Kernanlagen HWC Hydrogen Water Chemistry International Co-operative Group of Environmentally-Assisted Cracking ICG-EAC of LWR Materials IGSCC Intergranular SCC KrThreshold for SCC KTA Kerntechnischer Ausschuss, Germany LAS Low-Alloy Steel LCF Low-Cycle Fatigue LEFM Linear-Elastic Fracture Mechanics LFCF Low-Frequency Corrosion Fatigue LWR Light Water Reactor LWV Labor fur Werkstoffverhalten MPA Staatliche Materialprufungsanstalt, University of Stuttgart, Germany NDT Non-Destructive Testing NRC National Regulatory Commission, USA NWC Normal Water Chemistry PEER Panel of Experts for Evaluation and Review PWHT Post-Weld Heat Treatment PWR Pressurized Water Reactor QA Quality Assurance RPV Reactor Pressure Vessel SCC Stress Corrosion Cracking SEM Scanning Electron Microscopy SHE Standard-Hydrogen-Electrode SICC Strain-Induced Corrosion Cracking SRL Slow Rising Load Test SS Stainless Steel SSRT Slow Strain Rate Test SSY Small Scale Yielding TGSCC Transgranular SCC UTS Ultimate Tensile Strength VGB Technische Vereinigung der Grosskraftwerksbetreiber, Deutschland YS Yield Strength 1. Introduction The reactor pressure vessel (RPV) of both boiling water (BWR) and pressurized water reactors (PWR) is the most critical pressure-boundary component as far as safety and plant life are concerned [1.1, 1.2]. The high standards of safety and reliability on this pressure- boundary component in light water rectors (LWR) require that all potential relevant ageing and degradation mechanism affecting structural integrity are sufficiently understood so that even low probability failures can be ruled out by adequate (counter)measures. RPV structural integrity continues therefore to be a key concern within the context of both reactor safety and evaluation/extension of plant service life.
Load more

Recommended publications
  • Thermal Shock
    TEACHER INSTRUCTIONS Thermal Shock Objective: To illustrate thermal expansion and thermal shock. Background Information: In physics, thermal expansion is the tendency of matter to increase in volume or pressure when heated. For liquids and solids, the amount of expansion will normally vary depending on the material’s coefficient of thermal expansion. When materials contract, tensile forces are created. When things expand, compressive forces are created. Thermal shock is the name given to cracking as a result of rapid temperature change. From the laboratory standpoint, there are three main types of glass used today: borosilicate, quartz, and soda lime or flint glass. Borosilicate glass is made to withstand thermal shock better than most other glass through a combination of reduced expansion coefficient and greater strength, though fused quartz outperforms it in both respects. Some glass-ceramic materials include a controlled proportion of material with a negative expansion coefficient, so that the overall coefficient can be reduced to almost exactly zero over a reasonably wide range of temperatures. Improving the shock resistance of glass and ceramics can be achieved by improving the strength of the materials or by reducing its tendency to uneven expansion. One example of success in this area is Pyrex, the brand name that is well known to most consumers as cookware, but which is also used to manufacture laboratory glassware. Pyrex traditionally is made with a borosilicate glass with the addition of boron, which prevents shock by reducing the tendency of glass to expand. Demo description: Three different types of glass rods will be heated so that students can observe the amount of thermal shock that occurs.
    [Show full text]
  • Area Array Packages with Known Reliably and Mitigation Risks, Allowing Greater Processing Power in a Smaller Board Footprint and Lower System Weight
    National Aeronautics and Space Administration Reliability of CGA/LGA/HDI Package Board/Assembly (Revision A) Reza Ghaffarian, Ph.D. Jet Propulsion Laboratory Pasadena, California Jet Propulsion Laboratory California Institute of Technology Pasadena, California JPL Publication 12-3 2/12 National Aeronautics and Space Administration Reliability of CGA/LGA/HDI Package Board/Assembly (Revision A) NASA Electronic Parts and Packaging (NEPP) Program Office of Safety and Mission Assurance Reza Ghaffarian, Ph.D. Jet Propulsion Laboratory Pasadena, California NASA WBS: 724297.40.43 JPL Project Number: 104593 Task Number: 40.49.02.02 Jet Propulsion Laboratory 4800 Oak Grove Drive Pasadena, CA 91109 http://nepp.nasa.gov This research was carried out at the Jet Propulsion Laboratory, California Institute of Technology, and was sponsored by the National Aeronautics and Space Administration Electronic Parts and Packaging (NEPP) Program. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not constitute or imply its endorsement by the United States Government or the Jet Propulsion Laboratory, California Institute of Technology. Copyright 2013. California Institute of Technology. Government sponsorship acknowledged. Acknowledgments The author would like to acknowledge many people from industry and the Jet Propulsion Laboratory (JPL) who were critical to the progress of this activity. The author extends his appreciation to program managers of the National Aeronautics and Space Administration Electronics Parts and Packaging (NEPP) Program, including Michael Sampson, Ken LaBel, Drs. Charles Barnes and Douglas Sheldon for their continuous support and encouragement. ii OBJECTIVES AND PRODUCTS Commercial-off-the-shelf column grid array (COTS CGA) packaging technologies in high-reliability versions are now being considered for use in a number of National Aeronautics and Space Administration (NASA) electronic systems.
    [Show full text]
  • Corrosion Fatigue: Type 304 Stainless Steel in Acid-Chloride and Implant Metals in Biological Fluid
    76-9939 BOWERS, Davtd Francis, 1937- CORROSION FATIGUE: TYPE 304 STAINLESS STEEL IN ACID-CHLORIDE AND IMPLANT METALS IN BIOLOGICAL FLUID. The Ohio State University, Ph.D., 1975 Engineering, metallurgy Xerox University Microfilms, Ann Arbor, Michigan 48ioe CORROSION FATIGUE: TYPE 304 STAINLESS STEEL IN ACID-CHLORIDE AND IMPLANT METALS IN BIOLOGICAL FLUID Dissertation Presented in Partial Fulfillment of the Requirements for the Degree Doctor of Philosophy in the Graduate School of The Ohio State University by David Francis Bowers, B.S., M.S. Metallurgical Engineering The Ohio State University 1975 Approved by (dviser Department of Metallurgical Engineering Reading Committee: Dr. Mars G. Fontana Dr. Frank Beck Dr. John P. Hirth To My Wife and Daughter TABLE OF CONTENTS Page ACKNOWLEDGEMENTS.......................................... iv VITA........................................................ vi LIST OF TABLES............................................. viii LIST OF FIGURES... ...................... x INTRODUCTION.................. .. ......................... 1 I. LITERATURE SURVEY..................... 4 1.1 Concepts and Theory of Fatigue Crack Growth.. 4 1.2 Fracture Mechanics Approach to Crack Growth in Engineering Structures..................... 18 1.3 Effect of Microstructure on Fatigue Cracking Growth................................ 24 1.4 Mechanical Variables in Corrosion Fatigue.... 41 1.5 Environmental Interaction with Fatigue Crack Growth.................................... 59 II. EXPERIMENTAL DETAILS...............................
    [Show full text]
  • Tech Spotlight
    impact.qxd 3/12/04 11:25 AM Page 1 TECH SPOTLIGHT Impact Testing notched side by the moving striker by the metrology of the parts that are Wayne Hayward pendulum, and the energy needed to subject to the most wear and tear, and Tinius Olsen Testing Machine Co. break off the free end is the measure some machines were manufactured Horsham, Pennsylvania of the impact strength. This article before strict adherence to the specifi- discusses the equipment, calibration, cations in ASTM E23 was deemed to and procedures for Charpy testing. be critical. Accurate results are not pos- he purpose of impact testing is to sible if the equipment is not operating Tdetermine the toughness of a ma- Impact testing equipment according to the specification; there- terial by measuring the amount of en- Instruments for impact testing of fore, it is strongly recommended that ergy absorbed by a specimen as it frac- metals have been manufactured com- the impact tester be calibrated and/or tures while being struck by a striker mercially since the 1900’s, and several verified by an accredited calibration pendulum moving at high speed. The manufacturers of testing equipment service at regular intervals. impact strength is defined as the max- meet the requirements of ASTM E23, imum amount of energy that can be “Standard Test Methods for Notched Instrument calibration absorbed by the specimen without Bar Impact Testing of Metallic Mate- A calibration swing is performed to fracture. rials.” The standard provides dimen- ensure that energy losses due to In the Charpy impact test, a notch sion and tolerance requirements for windage and friction in the bearings is placed in the specimen.
    [Show full text]
  • Corrosion-Fatigue Evaluation of Uncoated Weathering Steel Bridges
    applied sciences Article Corrosion-Fatigue Evaluation of Uncoated Weathering Steel Bridges Yu Zhang, Kaifeng Zheng, Junlin Heng * and Jin Zhu Department of Bridge Engineering, School of Civil Engineering, Southwest Jiaotong University, Chengdu 610031, China * Correspondence: [email protected]; Tel.: +86-182-8017-6652 Received: 19 July 2019; Accepted: 19 August 2019; Published: 22 August 2019 Featured Application: The new findings highlight the enhancement in corrosion-fatigue performance of steel bridges by using the uncoated weathering steel. Besides, an innovative approach has been established to simulate the corrosion-fatigue process in uncoated weathering steel bridges, providing deep insights into the service life of the bridges. The approaches suggested in the article can be used (not limited to) as a reference for the research and design of uncoated weathering steel bridges. Abstract: Uncoated weathering steel (UWS) bridges have been extensively used to reduce the lifecycle cost since they are maintenance-free and eco-friendly. However, the fatigue issue becomes significant in UWS bridges due to the intended corrosion process utilized to form the corrodent-proof rust layer instead of the coating process. In this paper, an innovative model is proposed to simulate the corrosion-fatigue (C-F) process in UWS bridges. Generally, the C-F process could be considered as two relatively independent stages in a time series, including the pitting process of flaw-initiation and the fatigue crack propagation of the critical pitting flaw. In the proposed C-F model, Faraday’s law has been employed at the critical flaw-initiation stage to describe the pitting process, in which the pitting current is applied to reflect the pitting rate in different corrosive environments.
    [Show full text]
  • MATERIAL SCIENCE Module 3 Thermal Shock Thermal Shock DOE-HDBK-1017/2-93 TABLE of CONTENTS
    Department of Energy Fundamentals Handbook MATERIAL SCIENCE Module 3 Thermal Shock Thermal Shock DOE-HDBK-1017/2-93 TABLE OF CONTENTS TABLE OF CONTENTS LIST OF FIGURES .................................................. ii LIST OF TABLES ................................................... iii REFERENCES .................................................... iv OBJECTIVES ..................................................... v THERMAL STRESS ................................................ 1 Thermal Shock ............................................... 1 Summary ................................................... 5 PRESSURIZED THERMAL SHOCK .................................... 6 Definition ................................................... 6 Evaluating Effects of PTS ....................................... 6 Locations of Primary Concern ..................................... 8 Summary ................................................... 8 Rev. 0 Page i MS-03 LIST OF FIGURES DOE-HDBK-1017/2-93 Thermal Shock LIST OF FIGURES Figure 1 Stress on Reactor Vessel Wall .................................... 4 Figure 2 Heatup Stress Profile .......................................... 7 Figure 3 Cooldown Stress Profile ........................................ 7 MS-03 Page ii Rev. 0 Thermal Shock DOE-HDBK-1017/2-93 LIST OF TABLES LIST OF TABLES Table 1 Coefficients of Linear Thermal Expansion ............................ 2 Rev. 0 Page iii MS-03 REFERENCES DOE-HDBK-1017/2-93 Thermal Shock REFERENCES Academic Program for Nuclear Power Plant Personnel, Volume
    [Show full text]
  • Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering
    metals Article Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering Irena Vlˇcková 1,*, Petr Jonšta 2, ZdenˇekJonšta 2, Petra Vá ˇnová 2 and Tat’ána Kulová 2 1 RMTSC, Material & Metallurgical Research Ltd., Remote Site Ostrava, VÚHŽ a.s., Dobrá 739 51, Czech Republic 2 Department of Materials Engineering, VŠB-Technical University of Ostrava, Ostrava 708 33, Czech Republic; [email protected] (P.J.); [email protected] (Z.J.); [email protected] (P.V.); [email protected] (T.K.) * Correspondence: [email protected]; Tel.: +420-558601257 Academic Editor: Hugo F. Lopez Received: 21 September 2016; Accepted: 8 December 2016; Published: 16 December 2016 Abstract: Significant structural steels for nuclear power engineering are chromium-nickel austenitic stainless steels. The presented paper evaluates the kinetics of the fatigue crack growth of AISI 304L and AISI 316L stainless steels in air and in corrosive environments of 3.5% aqueous NaCl solution after the application of solution annealing, stabilizing annealing, and sensitization annealing. Comparisons were made between the fatigue crack growth rate after each heat treatment regime, and a comparison between the fatigue crack growth rate in both types of steels was made. For individual heat treatment regimes, the possibility of the development of intergranular corrosion was also considered. Evaluations resulted in very favourable corrosion fatigue characteristics of the 316L steel. After application of solution and stabilizing annealing at a comparable DK level, the fatigue crack growth rate was about one half compared to 304L steel. After sensitization annealing of 316L steel, compared to stabilizing annealing, the increase of crack growth rate during corrosion fatigue was slightly higher.
    [Show full text]
  • Thermal Shock-Resistant Cement
    BNL-101087-2012-IR Thermal Shock-resistant Cement T. Sugama, T. Pyatina, S. Gill February 2012 Sustainable Energy Technologies Department/Energy Conversion Group Brookhaven National Laboratory U.S. Department of Energy DOE office of Energy Efficiency and Renewable Energy Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. 1 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, 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 any third party’s use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
    [Show full text]
  • Corrosion Science 173 (2020) 108828
    Corrosion Science 173 (2020) 108828 Contents lists available at ScienceDirect Corrosion Science journal homepage: www.elsevier.com/locate/corsci The oxidation effect on the cracking behavior of a Co-based alloy under thermal shocks T Junxia Wena,b,c,d, Rui Caoa,b,*, Hongyan Chee, Hao Donge, Haiyan Zhanga,b, Yingjie Yana,b, Yanfei Gaoc,**, Peter K Liawc,** a State Key Laboratory of Advanced Processing and Recycling of Non-ferrous Metal, Lanzhou University of Technology, Lanzhou, 730050, Gansu, China b School of Materials Science and Engineering, Lanzhou University of Technology, Lanzhou, 730050, Gansu, China c Department of Materials Science and Engineering, The University of Tennessee, Knoxville, TN, 37996, USA d School of Mechanical and Electrical Engineering, Liuzhou Vocational & Technical College, Liuzhou 545006, Guangxi, China e Advanced Technology & Materials Limited Company, China Iron & Steel Research Institute Group, Beijing, 100081, China ARTICLE INFO ABSTRACT Keywords: Oxidation and cracking behavior during thermal-shock experiments of a new Co-based alloy were analyzed in Co-based alloy the present work. Comparing to the static conditions, the oxidation behavior during thermal shocks is stress- Thermal shock assisted and crack-accelerated. Cracks during the thermal shocks were initiated from the sample surfaces and Oxidation their growth are driven by various stresses, including those induced by volume change, mismatch of coefficients Crack of thermal expansion (CTEs), and temperature gradient between the matrix and the internal oxides. It is found Thermal fatigue that the crack propagation correlates to these stresses in the classic Paris’ law. 1. Introduction also different from that in the static oxidation. The cyclic oxidation behavior of the Co-based alloy has been well investigated by Barrett The Co-based alloy has a good combination of high-temperature and Lowel [13].
    [Show full text]
  • Supply Chain Packaging Guide
    Secondary Packaging Supply Chain Standards July 7, 2021 Business Confidential | ©2021 Walmart Stores, Inc. 177 // 338 Secondary Packaging Supply Chain Standards - Update Summary These standards have included multiple clarifications of what is required and what is NOT ALLOWED. These changes have been updated throughout the published standards to provide clarity to suppliers. The pages have been reorganized to provide a better flow. PAGE 2021 UPDATES Changes to Supply Chain Standards 185 SQEP Phase 2 and Phase 3 Defect Description/Definitions Added 202 General Case Markings Updated for Dates, Unprocessed Meats, and Cylindrical Items 210-213 Updated Pallet Standards 218 Update "Palletized Shipments" to "Unitized Shipments" 227 Add Inbound Appointment Scheduling Standard 228 Update TV Test Standards 235-237 Add Direct Store Delivery (DSD) aka Direct To Store (DTS) Standards 239 Update SIOC Standards 240 Add eCommerce Product Specific Requirement Standards 241-244 Add Drop Ship Vendor (DSV) Standards 268 Add Jewelry Distribution Center Standards 269-271 Add Optical Distribution Center Standards 275 Add Goods Not For Resale (GNFR) Standards 277-278 Update Meat/Poultry/Seafood Case and Pallet Label Standards 284 Add HACCP Pallet Placard for GCC Shipments 311-312 Add Frozen Seafood Carton Marking Requirements Appendix D Update Receiving Pulp Temperature Range Business Confidential | © 2021 Walmart Stores, Inc. The examples shown are for reference only. Supply Chain Standards 178 // 338 Table of Contents Supply Chain Stretch Wrap . 219 Produce Shipments . 280 Contact Information . 179 Trailer Loading . 220 Automated Grocery Handling . 281 Walmart Retail Link Resources . 180 Trailer Measurements. 221 Grocery Import Distribution Center (GIDC) . 282 Walmart Distribution Center Overview .
    [Show full text]
  • The Environmental Effect on Corrosion Fatigue Behavior of Austenitic Stainless Steels
    The Environmental Effect on Corrosion Fatigue Behavior of Austenitic Stainless Steels by Lun Yu B.S. Nuclear Engineering (2013) Shanghai Jiao Tong University SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF DOCTOR OF PHILOSOPHY IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY September, 2017 © 2017 Massachusetts Institute of Technology. All rights reserved. Signature of Author: _____________________________________________________________ Lun Yu Department of Nuclear Science and Engineering August 25, 2017 Certified by: __________________________________________________________________ Ronald G. Ballinger Professor of Nuclear Science and Engineering, Materials Science and Engineering Thesis Supervisor Certified by: ___________________________________________________________________ Michael P. Short Assistant Professor of Nuclear Science and Engineering Thesis Reader Accepted by: ___________________________________________________________________ Ju Li Battelle Energy Alliance Professor of Nuclear Science and Engineering, Professor of Materials Science and Engineering Chair, Department Committee on Graduate Students This page was left blank intentionally The Environmental Effect on Corrosion Fatigue Behavior of Austenitic Stainless Steels by Lun Yu Submitted to the Department of Nuclear Science and Engineering on September 1, 2017 in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy in Nuclear Science and
    [Show full text]
  • Galling and Galling Resistance of Stainless Steels
    Stainless Steel Advisory Service Tel: 0114 267 1265 Fax 0114 266 1252 A service provided by the SSAS Information Sheet No.5.60 th British Stainless Steel Association Issue 02 12 March 2001 Page 1 of 1 Galling and Galling Resistance of Stainless Steels Introduction Galling, or cold welding as it is sometimes referred to as, is a form of severe adhesive wear. Adhesive wear occurs between two metal surfaces that are in relative motion to each other and under sufficient load to permit the transfers of material between themselves. This is a solid-phase welding process. The load must be sufficient, during relative motion, to disrupt the protective oxide layer covering surface asperities of the metal and permit metal to metal contact. Under high stress and poor lubrication conditions, stronger bonds may form over a larger surface area. Large fragments or surface protrusions may be formed and the result is galling of the surfaces. Severe galling can result in the seizure of metal components. Materials which are highly ductile or which possess low work-hardening rates tend to be prone to galling. Austenitic stainless steels show a tendency to gall under certain conditions. Factors Affecting Wear and Galling The factors affecting wear and galling are related to design, lubrication, environment, and steel properties. The material properties relevant to the issue of galling of stainless steels include: - • design tolerances and surface finish of the steel • surface properties (hardness) and structure of the steel • applied load • contact area and degree of movement. Design tolerances should provide sufficient clearance. The contact load on sliding components should be kept to a minimum, while the contact area should be maximised.
    [Show full text]