1、 STP-NU-037 OPERATING CONDITION ALLOWABLE STRESS VALUES IN ASME SECTION III SUBSECTION NH Prepared by: R. W. Swindeman Cromtech Inc Date of Issuance: May 12, 2010 This report was prepared as an account of work sponsored by the U.S. Department of Energy (DOE) and the ASME Standards Technology, LLC (A
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11、orm, in an electronic retrieval system or otherwise, without the prior written permission of the publisher. ASME Standards Technology, LLC Three Park Avenue, New York, NY 10016-5990 ISBN No. 978-0-7918-3323-0 Copyright 2010 by ASME Standards Technology, LLC All Rights Reserved Operating Condition Al
12、lowable Stress Values STP-NU-037 TABLE OF CONTENTS Foreword vii Abstract .viii PART I . 1 1 INTRODUCTION . 2 2 EVALUATION OF CONSISTENCIES IN THE CURRENT VALUES 4 2.1 304H Stainless Steel 4 2.2 316H Stainless Steel 5 2.3 Alloy 800H5 2.4 2 Cr-1Mo Steel 6 2.5 9Cr-1Mo-V Steel. 7 2.6 Summary of the Eval
13、uations . 7 3 AVAILABILITY OF THE ORIGINAL AND AUGMENTED DATABASES NEEDED TO ESTABLISH So, Stand Sr8 4 AN OVERVIEW OF STRESS-RUPTURE DATABASES BY MEANS OF THE LARSON-MILLER PARAMETER . 11 5 SUMMARY. 14 References - PART I 15 PART II AND PART III 17 1 INTRODUCTION . 18 2 EVALUATION OF THE 304H STAINL
14、ESS STEEL DATABASE 19 2.1 Expected Minimum Stress-to-Rupture for 304H Stainless Steel 19 2.2 Minimum Time to Tertiary Creep for 304H Stainless Steel . 22 2.3 Average Time to 1% Strain for 304H Stainless Steel . 25 2.4 Assessment of the Database for 304H Stainless Steel. 26 3 EVALUATION OF THE 316H S
15、TAINLESS STEEL DATABASE 28 3.1 Expected Minimum Stress-to-Rupture for 316H Stainless Steel 28 3.2 Minimum Time to Tertiary Creep for 316H Stainless Steel . 30 3.3 Average Time to 1% Strain for 316H Stainless Steel . 33 3.4 Assessment of the Database for 316H Stainless Steel. 35 4 EVALUATION OF THE 2
16、 Cr-1Mo STEEL DATABASE. 36 4.1 Expected Minimum Stress-to-Rupture for 2 Cr-1Mo Steel. 36 4.2 Minimum Time to Tertiary Creep for 2 Cr-1 Mo Steel. 39 4.3 Average Time to 1% Strain for 2 Cr-1Mo Steel 41 4.4 Assessment of the Database for 2 Cr-1Mo Steel. 42 5 EVALUATION OF THE ALLOY 800H DATABASE 44 6 E
17、VALUATION OF THE 9Cr-1Mo-V STEEL DATABASE . 46 iii STP-NU-037 Operating Condition Allowable Stress Values 7 RECOMMENDED ACTION FOR THE CORRECTION OF CURRENTLY LISTED VALUES FOR So, Stand Sr48 References - PART II AND PART III52 Appendix 1 - Criteria for Setting the Stress Allowables in ASME Section
18、2D Table 1A and 1B and ASME Section III, Subsection NH.54 Acknowledgments.56 LIST OF TABLES Table 1 - Comparison of Allowable Stresses for 304H in ASME Section III, Subsection NH4 Table 2 - Comparison of Allowable Stresses for 316H in ASME Section III, Subsection NH5 Table 3 - Comparison of Allowabl
19、e Stresses for Alloy 800H in ASME Section III, Subsection NH6 Table 4 - Comparison of Allowable Stresses for 2 Cr-1Mo Steel in ASME Section III, Subsection NH 6 Table 5 - Comparison of Allowable Stresses for 9Cr-1Mo-V Steel in ASME Section III, Subsection NH 7 Table 6 - Comparison of the Data that P
20、roduced the N-47 Code Case with New Data for Re-evaluation by Booker .9 Table 7 - Comparison of the Data that Produced the N-47 Code Case with Data for Re-evaluation by McCoy for Alloy 800H in ASME III Code Case N-4710 Table 8 - Comparison of Data That Produced the ASME III-NH Stress Allowables for
21、9Cr-1Mo-V Steel with Data that Could be Used for Re-evaluation .10 Table 9 - Effect of Censoring on the Larson-Miller Lot Constant, C, and Strength at 105hr and 649C (1200F) for 304 Stainless Steel 19 Table 10 - Summary of the Larson-Miller Lot Constants for the Rupture Life of 304H Stainless Steel
22、in Terms of the Data Sources and Products .22 Table 11 - Ratio of Time to Tertiary Creep to Time to Rupture for 304H Stainless Steel at Several Temperatures23 Table 12 - Summary of the Larson-Miller Lot Constants for the Rupture Life of 316H Stainless Steel in Terms of the Data Sources.30 Table 13 -
23、 Summary of the Larson-Miller Lot Constants for the Rupture Life of 2 Cr-1Mo Steel in Terms of the Products and Heat Treatments39 Table 14 - Summary of Suggested Action Regarding Changes to the BPV III-NH Stress Allowables to Accommodate the Needs for the Generation IV Reactor Concepts.51 LIST OF FI
24、GURES Figure 1 - Stress versus the Larson Miller Parameter for the Combined 304H Stainless Steel Rupture Database- 75 Lots, 1170 Data, 179,000 hr Longest Life 11 Figure 2 - Stress versus the Larson Miller Parameter for the Combined 316H Stainless Steel Rupture Database- 106 Lots, 1940 Data, 222,000
25、hr Longest Life 12 Figure 3 - Stress versus the Larson Miller Parameter for the Combined 2 Cr-1Mo Steel (Gr 22 Class 1) Rupture Database- 189 Lots, 1623 Data, 213,000 hr Longest Life 12 iv Operating Condition Allowable Stress Values STP-NU-037 Figure 4 - Stress versus the Larson Miller Parameter for
26、 the Combined Alloy 800H Rupture Database- 83 Lots, 1170 Data, 194,000 hr Longest Life 13 Figure 5 - Stress versus the Larson Miller Parameter for the Combined 9Cr-1Mo-V Steel (Gr 91) Rupture Database- 104 Lots, 1600 Data, 110,000 hr Longest Life 13 Figure 6 - Stress versus the Larson-Miller Paramet
27、er for Rupture of 304H Stainless Steel 20 Figure 7 - Distribution of Residuals from the Fit of the Larson-Miller Parameter to Rupture Life Data for 304H Stainless Steel. 20 Figure 8 - Distribution of the Lot Constants for the Rupture Life of 304H Stainless Steel According to the Source of the Ruptur
28、e Data. 21 Figure 9 - Distribution of the Lot Constants for the Rupture Life of 304 Stainless Steel According to the Product 21 Figure 10 - Comparison of BPV III-NH Minimum Stress-to-Rupture Values with the Values Estimated from the Analysis of the Expanded Database for 304H Stainless Steel 22 Figur
29、e 11 - Time to Tertiary Creep versus Time to Rupture for 304H Stainless Steel at 593C (1100F) 23 Figure 12 - Stress versus the Larson-Miller Parameter for the Time to Tertiary Creep, t3, of 304H Stainless Steel. 24 Figure 13 - Fit of Linear f(S) Model to Log Stress versus the Larson-Miller Parameter
30、 for the Time to Tertiary Creep, t3, of 304H Stainless Steel . 24 Figure 14 - Comparison of the StValues from BPV III-NH Table I-14.4 for 304H with Estimations Based on 80% of the Minimum Stress for Tertiary Creep 25 Figure 15 - Comparison of the Stress for 1% Strain from the Isochronous Stress vers
31、us Strain Curves with the Stresses from BPV III-NH Table I-14.4 for 304H Stainless Steel . 26 Figure 16 - Stress versus the Larson-Miller Parameter for Rupture of 316H Stainless Steel 28 Figure 17 - Distribution of Residuals from the Fit of the Larson-Miller Parameter to Rupture Life Data for 316H S
32、tainless Steel. 29 Figure 18 - Distribution of the Lot Constants for the Rupture Life of 316H Stainless Steel According to the Source of the Rupture Data. 29 Figure 19 - Comparison of BPV III-NH Minimum Stress-to-Rupture Values with the Values Estimated from the Analysis of the Expanded Database for
33、 316H Stainless Steel 30 Figure 20 - Time to Tertiary Creep versus Time to Rupture for 316H Stainless Steel 31 Figure 21 - Stress versus the Larson-Miller Parameter for the Time to Tertiary Creep, t3, of 316H Stainless Steel. 31 Figure 22 - Distribution of Residuals from the Fit of the Larson-Miller
34、 Parameter to the Time to Tertiary Creep Data for 316H Stainless Steel 32 Figure 23 - Comparison of BPV III-NH StValues from Table I-14.4 (Based on the Lower of 67% of the Minimum Stress to Rupture or 80% of the Average Stress to Produce 1% Strain) with the Values Estimated from the Analysis of the
35、Tertiary Creep Criterion and the Expanded Tertiary Creep Database for 316H Stainless Steel 32 Figure 24 - Stress versus the Larson-Miller Parameter for the Time to 1% Creep for 316H Stainless Steel. 33 v STP-NU-037 Operating Condition Allowable Stress Values Figure 25 - Distribution of Residuals fro
36、m the Fit of the Larson-Miller Parameter to the Time to 1% Strain for 316H Stainless Steel .34 Figure 26 - Comparison of BPV III-NH StValues for 316H Stainless Steel from Table I-14.4 with the Values from the Isochronous Stress-Strain Curves at 1% Strain and New Values Estimated from the LMP Analysi
37、s of the Expanded 1% Strain Database 34 Figure 27 - Stress versus the Larson-Miller Parameter for Rupture of 2 Cr-1Mo Steel .36 Figure 28 - Distribution of Residuals from the Fit of the Larson-Miller Parameter to the Time to Rupture Data for 2 Cr-1Mo Steel Annealed .37 Figure 29 - Histogram Showing
38、the Distribution of Lot Constant with the Product Form for the Larson-Miller Analysis of the Rupture Life of 2 Cr-1 Mo Steel 38 Figure 30 - Histogram Showing the Distribution of Lot Constant with the Heat Treatment for the Larson-Miller Analysis of the Rupture Life of 2 Cr-1 Mo Steel 38 Figure 31 -
39、Comparison of BPV III-NH Minimum Stress-to-Rupture Values with the Values Estimated from the Analysis of the Expanded Database for 2 Cr-1Mo Steel.39 Figure 32 - Time to Tertiary Creep versus Time to Rupture for 2 Cr-1Mo Steel.40 Figure 33 - Larson-Miller Correlation for Tertiary Creep of 2 Cr-1Mo St
40、eel 41 Figure 34 - Time to 1% Strain versus Time to Rupture for 2 Cr-1Mo Steel 41 Figure 35 - Stress versus the Larson-Miller Parameter for 1% Creep of 2 Cr-1Mo Steel 42 Figure 36 - Log Stress versus the Larson-Miller Parameter for Rupture of Alloy 800H44 Figure 37 - Comparison of BPV II-D Table 1B
41、Stresses with the New Fit for the Expanded Database for Alloy 800H 45 Figure 38 - Comparison of the Stress to Produce 1% Strain with Estimates of the StValues Based on Rupture for Alloy 800H to 900C (1650F) 45 Figure 39 - Stress versus the Larson-Miller Parameter for Rupture of 9Cr-1Mo-V Steel46 Fig
42、ure 40 - Comparison of BPV III-NH StValues with 67% of the Minimum Stress-to-Rupture Calculated from the Expanded Database for 9Cr-1Mo-V Steel47 vi Operating Condition Allowable Stress Values STP-NU-037 FOREWORD This document is the result of work resulting from Cooperative Agreement DE-FC07-05ID147
43、12 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. The objective of the project is to provide technical information necessary to update and expand appropriate ASME materials, construction and desig
44、n codes for application in future Gen IV nuclear reactor systems that operate at elevated 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 6
45、titled “Operating Condition Allowable Stress Values.” 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 references for the committees a
46、nd 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 stakeholders from industry and gove
47、rnment 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 development process as well as comme
48、rcialization 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 component interchangeability i
49、n mechanical systems. Established in 1880, the American Society of Mechanical Engineers (ASME) is a professional not-for-profit organization with more than 127,000 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 community. Visit w
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