1、Designator: Meta Bold 24/26Revision Note: Meta Black 14/16STP-NU-042NEW MATERIALS FOR ASME SUBSECTION NHSTP-NU-042 NEW MATERIALS FOR ASME SUBSECTION NH Prepared by: Kazuhiko Suzuki and Tai Asayama Japan Atomic Energy Agency Robert W. Swindeman Cromtech Inc Douglas L. Marriott Stress Engineering Serv
2、ices Inc Date of Issuance: June 30, 2011 This report was prepared as an account of work sponsored by the U.S. Department of Energy (DOE) and the ASME Standards Technology, LLC (ASME ST-LLC). This report was prepared as an account of work sponsored by an agency of the United States Government. Neithe
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12、hnology, LLC Three Park Avenue, New York, NY 10016-5990 ISBN No. 978-0-7918-3388-9 Copyright 2011 by ASME Standards Technology, LLC All Rights Reserved New Materials for ASME Subsection NH STP-NU-042 iii TABLE OF CONTENTS Foreword vii Abstract . viii PART I . 1 1 SELECTION OF CANDIDATE MATERIALS AND
13、 CORRESPONDING TIME AND TEMPERATURE OPERATING CONDITIONS . 2 1.1 Considerations in Selecting the Candidate Materials 2 1.1.1 Corrosive Oxidation . 2 1.1.2 High Temperature Strength 3 1.1.3 Low Temperature Strength and Other Properties . 3 1.1.4 Workability and Weldability 3 1.2 Operating Time and Te
14、mperature Conditions . 4 2 REVIEW OF AVAILABLE JAPANESE DATA ON HASTELLOY XR AND INCONNEL 617 AND REQUIRED R&D . 5 2.1 Review of Japanese information on Hastelloy XR and Inconel 617 . 5 2.1.1 Environmental Effects 5 2.1.2 Unique Tensile Stress-Strain Relationship Due To Dynamic Recrystalization . 10
15、 2.1.3 Very significant creep 14 2.1.4 Creep Analysis Method: Creep Constitutive Equation and Related Hardening/Flow Rules, and a Creep Analysis-Based Method of Evaluating Creep Damage and Creep Strain 19 2.1.5 Thermal Aging Effect on Low Temperature Strength . 20 2.2 Required R&D . 23 3 ESTIMATION
16、OF STRENGTH CHARACTERISTICS 24 3.1 Creep rupture strength data on Hastelloy XR 24 3.2 Extrapolation Technique . 25 3.3 Estimation of Creep Rupture Strength at 800C and 100,000h . 26 References - Part I 27 PART II 28 1 SELECTION OF CANDIDATE MATERIALS 29 1.1 Identification of Metallic Components and
17、Operational Requirements 29 1.2 Required Properties for Construction of Section III Class 1 Components for Elevated Temperature Service 33 1.3 A Brief Review of Development of the Primary and Alternative Alloys Considered for Structural HTGR Components 33 1.4 Selection of Candidate Materials and Cod
18、e Status 34 1.4.1 Currently Approved Materials 34 1.4.2 Primary Candidate Materials 34 1.4.3 Alternate Materials . 34 1.5 Summary . 35 References - PART II, Section 1 36 2 REVIEW OF AVAILABLE DATA FOR CANDIDATE MATERIALS . 42 STP-NU-042 New Materials for ASME Subsection NH iv 2.1 Needed Properties f
19、or Construction of Section III Subsection NH Components for Elevated Temperature Service . 42 2.1.1 Current Requirements for ASME III-NH . 42 2.1.2 Other Considerations Regarding Current and Future Data Needs for ASME III-NH 42 2.1.3 Summary of materials properties needs for modern design analysis:
20、. 45 3 ESTIMATE OF STRENGTH CHARACTERISTICS . 47 3.1 Benchmark Comparison of Candidate Materials with Respect to Creep-Rupture Strength 47 3.2 Review of Available Data for New Materials Relative to the Needs for Incorporation into ASME III-NH 48 3.2.1 Cold Work Effects 48 3.2.2 Tensile Properties .
21、48 3.2.3 Tensile Reduction Factors. 50 3.2.4 Creep and Stress-Rupture . 50 3.2.5 Tensile Stress-Strain Curves . 54 3.2.6 Creep Strain versus Time Data . 55 3.2.7 Relaxation Data . 57 3.2.8 Strain-Controlled Fatigue Data . 59 3.2.9 Creep-Fatigue Interaction . 60 3.2.10 Multiaxial Stress And Strain .
22、62 3.2.11 Stress-Rupture Factors for Weldments . 62 3.2.12 Fine-Grained Strip Products for Compact Heat Exchangers 63 3.3 Overview of the Estimates for Data Needs 65 3.3.1 Suggested Testing of Alloy 800H to Support ASME III-NH . 65 3.3.2 Suggested Testing for Alloy 617 66 3.4 Summary 69 References -
23、 Part II, Sections 2&3 70 Appendix A - U. S. Patent of Hastelloy XR . 76 Appendix B - Tests and Estimated Costs 89 Acknowledgments . 94 LIST OF TABLES Table 1 - Chemical Composition of Hastelloy XR and Hastelloy X 3 Table 2 - Operating Conditions of the Main Components in an HTGR-IS Hydrogen Product
24、ion System 3 . 4 Table 3 - Impurities Levels of JAERI-B Type Helium . 6 Table 4 - Candidate Materials Listed for Intermediate and High-Temperature Components for the Very High Temperature NGNP 31 Table 5 - Potential Candidate Materials for Intermediate and High-Temperature Metallic Components in the
25、 VHTR Concept of the NGNP Reactor . 32 LIST OF FIGURES Figure 1 - Environmental Effects on the Creep Rupture Strength of Inconel 617 and Hastelloy XR at HTGR 7 New Materials for ASME Subsection NH STP-NU-042 v Figure 2 - Environmental Effect and Test Specimen Configuration Dependence on Low Cycle Fa
26、tigue Strength within a Fast-Fast Type Waveform for Inconel 617 at 1000C 6 8 Figure 3 - Environmental Effect on Low Cycle Fatigue Strength Under Fast-Fast Type Waveform for Hatelloy XR at 950C 6 . 9 Figure 4 - Environmental Effect on the Cyclic Stress-Strain Relationship of Inconel 617 and Hastelloy
27、 XR at HGTR Temperatures 6 9 Figure 5 - Illustration of Reduced Creep Rupture Strength of Inconnel 617 in HTGR-He Environment at 1000C and Corresponding Unaffected Strength of Hastelloy XR 10 Figure 6 - Tensile Stress-Strain Curves of Hastelloy XR at Various Temperatures at the Strain Rate Specified
28、 in JIS Standards 5 11 Figure 7 - Tensile Stress-Strain Curves of Hastelloy XR at 950C at Various Extension Rates 5 11 Figure 8 - Extension Rate Dependence of Yield Strength and Tensile Strength of Hastelloy XR at 800 and 1000C 4 12 Figure 9 - Schematic Illustration of Extension Rate (Strain Rate) D
29、ependence of Yield Strength and Tensile Strength at the Very High Temperature where Extremely Significant Creep Occurs 12 Figure 10 - Hysteresis Loop of Hastelloy XR at 950C and a Strain Rate of 0.1%/s 5 . 13 Figure 11 - Effect of Strain Hold Time on Low-Cycle-Fatigue Lives Within the Strain Hold Wa
30、veform for Inconel 617 at 1000C in 99.99% Helium 6 15 Figure 12 - Effects of Strain Hold Time and Strain Rate on Low Cycle Fatigue Lives in the so-called Creep Fatigue Interaction Testing for Hastelloy XR in an HTGR-He Environment 4, 9 . 15 Figure 13 - Effects of Strain Hold Time and Strain Rate on
31、Low-Cycle-Fatigue Lines in Creep Fatigue Interaction Testing of SS 304 10 16 Figure 14 - Practically Full Relaxation of Inconel 617 at the High Temperature of 900C and Comparison of the Observed Relaxation Curve with One Estimated Using Creep Data 6 . 16 Figure 15 - Temperature and Stress Dependence
32、s of Reciprocal Time Constant in Primary Creep Regime r for Hastelloy XR in the High Temperature Region of 800C and Above 4 17 Figure 16 - Time to Onset of Tertiary Creep for Hastelloy XR 4 18 Figure 17 - Creep Curve Fitting Using the Garofalo Equation 4 . 20 Figure 18 - Comparison of Low-Cycle Fati
33、gue Strength at Very High Temperature as Received and Aged at the Same Temperature 6 21 Figure 19 - Changes in Range of Stress with Increasing Number of Cycles for Inconel 617 6 22 Figure 20 - Monotonic and Cyclic Stress-Strain Relationship for Hastelloy XR at 950C in an HTGR-He Environment 6 23 Fig
34、ure 21 - Creep Rupture Strength Data on Hastelloy XR . 24 Figure 22 - Helium Pressure Effect on Creep Rupture Strength of Hastelloy XR 4 . 25 Figure 23 - Probability Distribution of Creep Rupture Data for Hastelloy XR 4 26 STP-NU-042 New Materials for ASME Subsection NH vi Figure 24 - Comparisons of
35、 the Strength Based on 100,000 Hours for Alloys Intended for Service at Temperatures Around 800C 47 Figure 25 - Typical Yield Strength vs. Temperature for Several Candidate Alloys . 49 Figure 26 - Typical Ultimate Strength vs. Temperature for Several Candidate Alloys 49 Figure 27 - Temperature-Time-
36、Precipitation (TTP) Diagram for Alloy 617 by Wu et. al. 17. Long-Time Aging at ORNL by McCoy 21 50 Figure 28 - Stress vs. the Larson-Miller Parameter for Rupture of Alloy 617 (Arrows show the Larson-Miller parameter at 100,000 hours) 51 Figure 29 - Stress vs. Larson-Miller parameter for Rupture of A
37、lloy 230 52 Figure 30 - Stress vs. the Larson-Miller Parameter for Rupture of Alloy X . 52 Figure 31 - Stress vs. Larson-Miller Parameter for Rupture of Alloy 556 . 53 Figure 32 - Stress vs. Larson-Miller Parameter for Rupture of NF 709 . 53 Figure 33 - Stress vs. Larson-Miller Parameter for Rupture
38、 of Alloy 800H 54 Figure 34 - Tensile Yield Curves for Alloy 230 at 871C (1600F) and Above 34 . 55 Figure 35 - Two Creep Curves for Alloy 617 Showing the Variability in Primary Creep . 56 Figure 36 - Creep Curves for Alloy 230 at 871C 56 Figure 37 - Creep Curves for Alloy 556 at Three Temperatures 5
39、7 Figure 38 - Relaxation Behavior for Alloy 556 near 871C . 58 Figure 39 - Start of a 0.50 Hour Relaxation-Hold C-F Test on Alloy 556 at 871C and 0.62% Strain Range 58 Figure 40 - Comparison of Continuous Cycling Low Cycle Fatigue Data for some Nickel Base Alloys 59 Figure 41 - Typical Stress vs. Cy
40、cles Behavior for Alloy 556 . 60 Figure 42 - Damage Interaction Diagram for Alloy 800 and Alloy 800H Determined from Three Analyses 61 Figure 43 - Stress vs. Larson-Miller Parameter for 0.08 to 0.13 mm Foils 64 Figure 44 - Comparison of Creep Curves for Alloy 625 and Alloy 214 Foils at 800C . 64 New
41、 Materials for ASME Subsection NH STP-NU-042 vii FOREWORD This document is the result of work resulting from Cooperative Agreement DE-FC07-05ID14712 between the U.S. Department of Energy (DOE) and ASME Standards Technology, LLC (ASME ST-LLC) for the Generation IV (Gen IV) Reactor Materials Project.
42、The objective of the project is to provide technical information necessary to update and expand appropriate ASME materials, construction and design codes for application in future Gen IV nuclear reactor systems that operate at elevated temperatures. The scope of work is divided into specific areas t
43、hat are tied to the Generation IV Reactors Integrated Materials Technology Program Plan. This report is the result of work performed under Task 11 titled “New Materials for ASME Subsection NH.” ASME ST-LLC has introduced the results of the project into the ASME volunteer standards committees develop
44、ing new code rules for Generation IV nuclear reactors. The project deliverables are expected to become vital references for the committees and serve as important technical bases for new rules. These new rules will be developed under ASMEs voluntary consensus process, which requires balance of intere
45、st, openness, consensus and due process. Through the course of the project, ASME ST-LLC has involved key stakeholders from industry and government to help ensure that the technical direction of the research supports the anticipated codes and standards needs. This directed approach and early stakehol
46、der involvement is expected to result in consensus building that will ultimately expedite the standards development process as well as commercialization of the technology. ASME has been involved in nuclear codes and standards since 1956. The Society created Section III of the Boiler and Pressure Ves
47、sel Code, which addresses nuclear reactor technology, in 1963. ASME Standards promote safety, reliability and component interchangeability in mechanical systems. Established in 1880, the American Society of Mechanical Engineers (ASME) is a professional not-for-profit organization with more than 127,
48、000 members promoting the art, science and practice of mechanical and multidisciplinary engineering and allied sciences. ASME develops codes and standards that enhance public safety, and provides lifelong learning and technical exchange opportunities benefiting the engineering and technology communi
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