1、Designator: Meta Bold 24/26Revision Note: Meta Black 14/16STP-NU-019-1VERIFICATION OF ALLOWABLE STRESSESIN ASME SECTION IIISUBSECTION NH FOR GRADE 91 STEELSTP-NU-019-1 VERIFICATION OF ALLOWABLE STRESSES IN ASME SECTION III SUBSECTION NH FOR GRADE 91 STEEL Prepared by: R. W. Swindeman Cromtech Inc M.
2、 J. Swindeman University of Dayton Research Institute B. W. Roberts BW Roberts Consultants B. E. Thurgood Bpva Engineering D. L. Marriott Stress Engineering Services STP-NU-019-1 Allowable Stresses in Section III-NH for Grade 91 Date of Issuance: March 19, 2009 This report was prepared as an account
3、 of work sponsored by U.S. Department on Energy (DOE) and the ASME Standards Technology, LLC (ASME ST-LLC). Neither ASME, ASME ST-LLC, Cromtech, Inc., University of Dayton Research Institute, BW Roberts Consultants, Bpva Engineering, Stress Engineering Services, nor others involved in the preparatio
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10、t the prior written permission of the publisher. ASME Standards Technology, LLC Three Park Avenue, New York, NY 10016-5990 ISBN No. 978-0-7918-3221-9 Copyright 2009 by ASME Standards Technology, LLC All Rights Reserved ii Allowable Stresses in Section III-NH for Grade 91 STP-NU-019-1 Summary of Chan
11、ges March 19, 2009 STP-NU-019-1 VERIFICATION OF ALLOWABLE STRESSES IN ASME SECTION III SUBSECTION NH FOR GRADE 91 STEEL The following changes have been made to the first revision of STP-NU-019. Rev. 1 Page Location Change v-vi Table of Contents Updated to reflect changes 6 paragraph 2, line 1 Correc
12、ted from reference 15 to 14 6 figure 2 Replaced with correct figure 7 figure 3 Replaced with correct figure 8 paragraph 2, line 2 Corrected “if” to “of” 8 paragraph 4, line 3 Corrected “Fave” to “Fave” 9 equation (3) Improved formatting 9 equation (4) Improved formatting 9 equation (5) Improved form
13、atting 9 equation (6) Improved formatting 10 paragraph 1, line 4 Correct “Cave” to “Cave” 11 paragraph 1, line 4 Corrected from reference 13 to 14 11 figure 7 Replaced with correct figure 12 figure 9 Replaced with correct figure 13 figure 12 Replaced with correct figure 14 paragraph 1, line 7 Correc
14、ted figure number from 4 to 14. iii STP-NU-019-1 Allowable Stresses in Section III-NH for Grade 91 Rev. 1 Page Location Change 19 figure 20 Replaced with correct figure 20 figure 22 Replaced with correct figure 24 figure 24 Replaced with correct figure 31 title Deleted “FISH” and “B” from title. 45
15、title Deleted “FISH” and “B” from title. 76 figure 26 Replaced with correct figure 77 equation (11) Improved formatting 77 equation (12) Improved formatting 79 figure 30 Replaced with correct figure 81 paragraph 3, line 6 Replaced “105” with “100,000” 81 paragraph 3, line 8 Replaced “104” with “10,0
16、00” 82 equation (13) Improved formatting 83 figure 31 Replaced with correct figure 96 figure 41 Replaced with correct figure iv Allowable Stresses in Section III-NH for Grade 91 STP-NU-019-1 TABLE OF CONTENTS Foreword . ix Abstract x PART I - BASE METAL . 1 1 INTRODUCTION . 2 2 IDENTIFICATION OF MAT
17、ERIALS 3 3 AVAILABLE SOURCES FOR CREEP-RUPTURE DATA 4 4 GENERAL TRENDS IN THE CREEP BEHAVIOR OF GR 91 STEEL. 5 5 CHARACTERISTICS OF THE CREEP DATABASE FOR ALLOY GR 91 6 6 DATA ANALYSIS PROCEDURES. 8 6.1 Criteria for Setting StValues. 8 6.2 Procedures for Estimating the Average Strength for 1% Strain
18、 and the Minimum Strength for the Onset of Tertiary Creep .8 6.3 Selection of Analysis Methods 8 7 RESULTS 10 7.1 Time to 1% Total Strain, t1%:. 10 7.2 Time to the Initiation of Tertiary Creep, t3:. 12 7.3 Stress-Rupture, tR15 8 EVALUATION OF THE CRITERIA CONTROLLING ST22 9 SUMMARY AND RECOMMENDATIO
19、NS 25 References - Part 1 . 26 Appendix 1 Parametric Constants . 28 Appendix 2 Stress-to-Rupture Curves. 29 Appendix 3 - Fish Grade 91B Data 31 Appendix 4 - NIMS Data . 46 Appendix 5 - ORNL Data. 50 Appendix 6 - Japanese Grade 91 Data (JP) 57 Appendix 7 - Japanese Grade 91 Data (JCF) .64 Appendix 8
20、- German Grade 91 Data. 68 PART II - WELDMENTS 69 1 INTRODUCTION . 70 2 IDENTIFICATION OF FILLER METALS FOR GR 91 71 3 BACKGROUND AND SOURCES FOR WELDMENT CREEP-RUPTURE DATA . 72 4 CHARACTERISTICS OF THE CREEP-RUPTURE DATABASE FOR ALLOY GR 91 WELD METAL AND WELDMENTS 73 5 DATA EVALUATION .75 v STP-N
21、U-019-1 Allowable Stresses in Section III-NH for Grade 91 5.1 Criterion for Setting the Weldment Stress Rupture Factor Values 75 5.2 Evaluation Methods .75 5.3 Estimation of Stress Rupture Factors.79 5.4 Comparison of the Stress Rupture Factors with Other Assessments .80 6 DISCUSSION OF EVALUATION .
22、84 7 CONCLUSIONS AND RECOMMENDATIONS.86 References - Part II .87 Appendix 1 - A Listing of Products, Filler Metals and Weld Processes.90 Appendix 2 - Sketches of Typical Weld Metal and Weldment Specimen Locations .92 Appendix 3 - Chemistries for Filler Metals or Deposited Weld Metal.98 Appendix 4 -
23、A Compilation of Stress Rupture Testing Data on Gr 91 Weldments and Gr 9 and Gr 91 Weld Metals 100 Acknowledgments.106 Abbreviations and Acronyms .107 LIST OF TABLES Table 1 - Chemical Specifications for Grade 91 (wt %).3 Table 2 - Average Lot Constants for Different Products 18 Table 3 - Comparison
24、 of the Strength for 100,000 Hour Estimate by Different Methods21 Table 4 - Chemistries for Grade 91 Steel and Filler Metals .71 Table 5 - Estimated Stress Rupture Factors for Gr 91 Weldments .80 LIST OF FIGURES Figure 1 - Definitions for Components of Creep used in ASME Section III Subsection NH 5
25、Figure 2 - Distribution of Time to 1% Strain (t1%) Data with Temperature6 Figure 3 - The Distribution of the Time to T3 Data with Temperature 7 Figure 4 - The Distribution of the Time Rupture Data with Temperature7 Figure 5 - Fit of the Larson Miller Parameter to the Time to Tertiary, t3, for 27 Lot
26、s (left) Global; (right) Lot-Centered 10 Figure 6 - Histogram of Residuals (left) and Frequency Graph for Residuals (right) 10 Figure 7 - Stress Versus t1%Based on the Larson Miller Parameter.11 Figure 8 - The Fit of Data to the OSD Parameter (left) and Residual Frequency Graph (right).11 Figure 9 -
27、 Stress vs. t1%Based on the Orr-Sherby-Dorn Parameter12 Figure 10 - Fit of the Larson Miller Parameter to the Time to Tertiary, t3, for 27 Lots (left) Global; (right) Lot-Centered. 12 Figure 11 - Distribution of Larson Miller Parameter Lot Constants for Tertiary Creep with Product Form (left) and Pe
28、rcentage Distribution of Residuals for all Lots (right) .13 vi Allowable Stresses in Section III-NH for Grade 91 STP-NU-019-1 Figure 12 - Stress vs. the Time to the Initiation of Tertiary Creep for Several Temperatures Based on the Larson Miller Lot-Centered Model . 13 Figure 13 - Fit of the Orr-She
29、rby-Dorn Parameter to the Time to Tertiary Creep. 14 Figure 14 - Average Stress to Produce the Initiation of Tertiary Creep vs. Time for Several Temperatures Based on the Orr-Sherby-Dorn Parametric Model 14 Figure 15 - The Leyda-Rowe Correlation Between t3and tR(left) and Histogram of the t3/tRRatio
30、 Values for 312 Data (right). 15 Figure 16 - Fit of the Larson Miller Parameter to Rupture Data: (left) Global Fit; (right) Lot-Centered Fit 16 Figure 17 - The Distribution of Residuals for the Fit of the Larson Miller Parameter Lot-Centered Procedure to Rupture Data: Count vs. Range Histogram (left
31、); Percent vs. Range Graph (right). 16 Figure 18 - Plots Showing the Characteristics of the Fit of the Larson Miller Lot-Center Model to Rupture Data: (a) Residuals vs. Temperature; (b) Residuals vs. Stress; (c) Residuals vs. Observed Rupture Life: and (d) Rupture Life vs. Calculated Rupture Life 17
32、 Figure 19 - Correlation of the Larson Miller Parameter Lot Constants with Ultimate Tensile Strength (left) and Product Thickness (right). 18 Figure 20 - Average Stress vs. Time to Rupture Based on the Larson Miller Lot-Centered Model 19 Figure 21 - Fit of the Orr-Sherby-Dorn Parameter to Rupture Da
33、ta 19 Figure 22 - Average Stress vs. Time to Rupture Based on the Orr-Sherby-Dorn Model. 20 Figure 23 - Stress vs. Time Curves Plotted According to ASME III-NH Time-Dependent Criteria. 23 Figure 24 - Comparison of Current StValues with Values Based on the Larson Miller Parameter and New Database 24
34、Figure 25 - The Distribution of the Rupture Data with Filler Metal, Weld Process, Test Temperature and PWHT Temperature . 74 Figure 26 - Correlation of Gr 91 Cross Weld Rupture Data with the ASME III-NH Model . 76 Figure 27 - Gr 91 Cross Weld Rupture Data and Calculated Isothermal Curves Based on OS
35、D 76 Figure 28 - Correlation of Gr-91 Cross WeldRupture Data with the Larson Miller Model. 78 Figure 29 - Gr 91 Cross Weld Rupture Data and Calculated Isothermal Curves Based on LMP 78 Figure 30 - Stress vs. the Larson Miller Parameter Adjusted for Lot Constant Differences 79 Figure 31 - Estimated S
36、tress Rupture Factors and Weld Strength Reduction Factors for Gr 91 Weldments vs. Temperatures for 100,000 hr. Duration . 82 Figure 32 - Typical Tensile Speciment Cutting 92 Figure 33 - Typical Weld Metal and Weldment Specimen Cutting . 92 Figure 34 - Typical Weld Metal and Weldment Specimen Cutting
37、 . 92 Figure 35 - Typical Weld Metal and Weldment Specimen Cutting . 93 Figure 36 - Typical Weld Metal and Weldment Specimen Cutting . 93 Figure 37 - Typical Weld Metal and Weldment Specimen Cutting . 94 vii STP-NU-019-1 Allowable Stresses in Section III-NH for Grade 91 Figure 38 - Typical Weld Meta
38、l and Weldment Specimen Cutting94 Figure 39 - Typical Weld Metal and Weldment Specimen Cutting95 Figure 40 - Typical Weld Metal and Weldment Specimen Cutting95 Figure 41 - Typical Weld Metal and Weldment Specimen Cutting96 Figure 42 - Typical Weld Metal and Weldment Specimen Cutting96 Figure 43 - Ty
39、pical Weld Metal and Weldment Specimen Cutting97 viii Allowable Stresses in Section III-NH for Grade 91 STP-NU-019-1 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 (ASM
40、E ST-LLC) for the Generation IV (Gen IV) Reactor Materials Project. 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 eleva
41、ted temperatures. The scope of work is divided into specific areas that are tied to the Generation IV Reactors Integrated Materials Technology Program Plan. This report is the result of work performed under Task 1 titled “Verification of Allowable Stresses in ASME Section III, Subsection NH with Emp
42、hasis on Alloy 800H and Grade 91 Steel (a.k.a., 9Cr-1Mo-V or Modified 9Cr-1Mo).” ASME ST-LLC has introduced the results of the project into the ASME volunteer standards committees developing new code rules for Generation IV nuclear reactors. The project deliverables are expected to become vital refe
43、rences 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 interest, openness, consensus and due process. Through the course of the project ASME ST-LLC has involved key stakehold
44、ers 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 stakeholder involvement is expected to result in consensus building that will ultimately expedite the standards developmen
45、t 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 Vessel Code, which addresses nuclear reactor technology, in 1963. ASME Standards promote safety, reliability and comp
46、onent interchangeability in mechanical systems. The American Society of Mechanical Engineers (ASME) is a not-for-profit professional organization promoting the art, science and practice of mechanical and multidisciplinary engineering and allied sciences. ASME develops codes and standards that enhanc
47、e public safety and provides lifelong learning and technical exchange opportunities benefiting the engineering and technology community. Visit www.asme.org. The ASME Standards Technology, LLC (ASME ST-LLC) is a not-for-profit Limited Liability Company, with ASME as the sole member, formed to carry o
48、ut work related to newly commercialized technology. The ASME ST-LLC mission includes meeting the needs of industry and government by providing new standards-related products and services, which advance the application of emerging and newly commercialized science and technology and providing the rese
49、arch and technology development needed to establish and maintain the technical relevance of codes and standards. Visit www.stllc.asme.org for more information. ix STP-NU-019-1 Allowable Stresses in Section III-NH for Grade 91 ABSTRACT Part I Base Metal - The database for the creep-rupture of 9Cr-1Mo-V (Grade 91) steel was collected and reviewed to determine if it met the needs for recommending time-dependent strength values, St, for coverage in ASME Section III Subsection NH (ASME III-NH) to 650C (1200F) and 600,000 hours. The accumulated database included over 300 tests fo
