ASME STP-NU-063-2013 CORRECT AND EXTEND ALLOWABLE STRESS VALUES FOR 304 AND 316 STAINLESS STEEL《304至316不锈钢用延伸容许应力值和校正》.pdf

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1、STP-NU-063CORRECT AND EXTEND ALLOWABLE STRESS VALUES FOR 304 AND 316 STAINLESS STEELSTP-NU-063 CORRECT AND EXTEND ALLOWABLE STRESS VALUES FOR 304 AND 316 STAINLESS STEEL Prepared by: Mainak Sengupta James E. Nestell MPR Associates, Inc. Date of Issuance: June 28, 2013 This report was prepared as an

2、account of work sponsored by the U.S. Department of Energy (DOE) through 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. Neither the United States Government nor any agency thereof, nor any of th

3、eir employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to

4、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. The views and opinions of authors expressed herein do no

5、t necessarily state or reflect those of the United States Government or any agency thereof. Neither ASME, ASME ST-LLC, the authors, nor others involved in the preparation or review of this report, nor any of their respective employees, members or persons acting on their behalf, make any warranty, ex

6、press or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe upon privately owned rights. Reference herein to any specific commercial product,

7、 process or service by trade name, trademark, manufacturer or otherwise does not necessarily constitute or imply its endorsement, recommendation or favoring by ASME ST-LLC or others involved in the preparation or review of this report, or any agency thereof. The views and opinions of the authors, co

8、ntributors and reviewers of the report expressed herein do not necessarily reflect those of ASME ST-LLC or others involved in the preparation or review of this report, or any agency thereof. ASME ST-LLC does not take any position with respect to the validity of any patent rights asserted in connecti

9、on with any items mentioned in this document, and does not undertake to insure anyone utilizing a publication against liability for infringement of any applicable Letters Patent, nor assumes any such liability. Users of a publication are expressly advised that determination of the validity of any su

10、ch patent rights, and the risk of infringement of such rights, is entirely their own responsibility. Participation by federal agency representative(s) or person(s) affiliated with industry is not to be interpreted as government or industry endorsement of this publication. ASME is the registered trad

11、emark of the American Society of Mechanical Engineers. No part of this document may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher. ASME Standards Technology, LLC Two Park Avenue, New York, NY 10016-5990 ISBN No. 978-0

12、-7918-6906-2 Copyright 2013 by ASME Standards Technology, LLC All Rights Reserved Correct and Extend Allowable Stress Values for 304 and 316 SS STP-NU-063 iii TABLE OF CONTENTS Foreword . vii Executive Summary . viii 1 INTRODUCTION 1 1.1 Purpose .1 1.2 Background .1 1.3 Analysis Procedure .1 2 304 S

13、TAINLESS STEEL .3 2.1 Introduction .3 2.2 Database 3 2.3 Allowable Sr Values .3 2.3.1 Time-to-Rupture Analysis .3 2.3.2 Calculations and Results .6 2.4 Allowable St Values 10 2.4.1 Time-to-Tertiary Creep Analysis 10 2.4.2 Time-to-1% Strain Analysis 13 2.4.3 Results .17 2.5 Allowable Smt Values19 3 3

14、16 STAINLESS STEEL .22 3.1 Introduction .22 3.2 Database 22 3.3 Allowable Sr Values .22 3.3.1 Time-to-Rupture Analysis .22 3.3.2 Calculations and Results .25 3.4 Allowable St Values 28 3.4.1 Time-to-Tertiary Creep Analysis 28 3.4.2 Time-to-1% Strain Analysis 31 3.4.3 Results .35 3.5 Allowable Smt Va

15、lues37 STP-NU-063 Correct and Extend Allowable Stress Values for 304 and 316 SS iv 4 CONCLUSION AND RECOMMENDATIONS .39 4.1 Minimum Stress-to-Rupture (Sr) 39 4.2 Temperature and Time Dependent Stress Intensity (St) .39 4.3 Smt .39 References 41 Appendix A 42 Acknowledgments43 Abbreviations and Acron

16、yms 44 LIST OF TABLES Table 2-1 Results from Regression Analysis for 304 SS Rupture Analysis .4 Table 2-2 Results from Regression Analysis for 304 SS Time-to-tertiary Creep Analysis .12 Table 2-3 Stress at 1% Strain in S.I. Units for 304 SS .15 Table 2-4 Stress at 1% strain in Customary Units for 30

17、4 SS 15 Table 2-5 Results from Regression Analysis for 304 SS for Time-to-1% Strain .16 Table 3-1 Results from Regression Analysis for 316 SS for Rupture Analysis .23 Table 3-2 Results from Regression Analysis for 316SS for Time-to-Tertiary Creep Analysis 30 Table 3-3 Stress at 1% Strain in S.I. Uni

18、ts for 316 SS .33 Table 3-4 Stress at 1% Strain in Customary Units for 316 SS .33 Table 3-5 Results from Regression Analysis for 316 SS for Time-to-1% Strain Analysis 34 LIST OF FIGURES Figure 2-1 Stress versus LMP for Rupture Analysis of 304 SS .4 Figure 2-2 Normal Probability Distribution of the R

19、upture Data .5 Figure 2-3 Plot of Residual in Log Time versus Temperature in C for the Rupture Data 5 Figure 2-4 Data Points versus Residual in Log Time for the Rupture Analysis .6 Correct and Extend Allowable Stress Values for 304 and 316 SS STP-NU-063 v Figure 2-5 Sr Values for 304 SS in S.I. unit

20、s 7 Figure 2-6 Sr Values for 304 SS in Customary Units .7 Figure 2-7 Sr versus Time from 800F to 1500F in Customary Units 8 Figure 2-8 Comparison of Revised Sr Values with NH 9 Figure 2-9 Stress versus Time-to-Rupture at 1200F (650C) .9 Figure 2-10 Classical Creep Curve Showing t2 Departure from Min

21、imum Creep Rate and tss Time-to-Tertiary Creep .11 Figure 2-11 Stress versus LMP for Time-to-Tertiary Strain Analysis of 304 SS Second Order Polynomial Regression Analysis .12 Figure 2-12 Stress versus LMP for Time-to-Tertiary Strain Analysis of 304 SS Linear Regression Analysis .13 Figure 2-13 Hot

22、Tensile Curve for 304 SS at 1000F 14 Figure 2-14 Hot Tensile Curve for 304 SS at 1300F 14 Figure 2-15 Stress versus LMP for Time-to-1% Strain Analysis of 304 SS - Linear Regression Analysis .16 Figure 2-16 St Values for 304 SS in S.I. Units .17 Figure 2-17 St Values for 304 SS in Customary Units .17

23、 Figure 2-18 St versus Time from 800F to 1500F in Customary Units 18 Figure 2-19 Comparison of Revised St Values with NH 19 Figure 2-20 Smt Values for 304 SS in S.I. Units .20 Figure 2-21 Smt Values for 304 SS in Customary Units .20 Figure 2-22 Smt versus Time from 800F to 1500F in Customary Units 2

24、1 Figure 3-1 Stress versus LMP for Rupture Analysis of 316 SS .23 Figure 3-2 Normal Probability Distribution of the Rupture Data .24 Figure 3-3 Plot of Residual in Log Time versus Temperature in C for the Rupture Data 24 Figure 3-4 Data Points versus Residual in Log Time for the Rupture Analysis .25

25、 Figure 3-5 Sr Values for 316 SS in S.I. Units .26 STP-NU-063 Correct and Extend Allowable Stress Values for 304 and 316 SS vi Figure 3-6 Sr Values for 316 SS in Customary Units .26 Figure 3-7 Sr versus Time from 800F to 1500F in Customary Units 27 Figure 3-8 Comparison of Revised Sr Values with NH

26、27 Figure 3-9 Ratio between Time-to-Tertiary Creep and Time-to-Rupture (t3/tr) versus Temperature for 316 SS Shows Large Variation .28 Figure 3-10 t3/tr versus Rupture Time for 316 SS Shows Greater Variation for Short Rupture Time 29 Figure 3-11 Stress versus LMP for Time-to-Tertiary Strain Analysis

27、 of 316 SS Second Order Polynomial Regression Analysis 30 Figure 3-12 Stress versus LMP for Time-to-Tertiary Strain Analysis of 316 SS Linear Regression Analysis .31 Figure 3-13 Hot Tensile Curve for 316 SS at 1000F 32 Figure 3-14 Hot Tensile Curve for 316 SS at 1300F 32 Figure 3-15 Stress versus LM

28、P for Time-to-1% Strain Analysis of 316 SS Second Order Regression Analysis .34 Figure 3-16 St Values for 316 SS in S.I. Units .35 Figure 3-17 St Values for 316 SS in Customary Units .35 Figure 3-18 St versus Time from 800F to 1500F in Customary Units 36 Figure 3-19 Comparison of Revised St Values w

29、ith NH 36 Figure 3-20 Smt Values for 316 SS in S.I. Units .37 Figure 3-21 Smt Values for 316 SS in Customary Units .37 Figure 3-22 Smt versus Time from 800F to 1500F in Customary Units 38 Correct and Extend Allowable Stress Values for 304 and 316 SS STP-NU-063 vii FOREWORD This document is the resul

30、t of work resulting from Cooperative Agreement DE-NE0000288 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

31、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 that are tied to the Generation IV Reactors Integrated Materials Technology Program Plan.

32、This report is the result of work performed under Task 14a titled “Correct and Extend Allowable Stress Values for 304 and 316 Stainless Steel.” ASME ST-LLC has introduced the results of the project into the American Society of Mechanical Engineers (ASME) volunteer standards committees developing new

33、 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 interest, ope

34、nness, 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 stakeholder inv

35、olvement 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 Vessel Cod

36、e, 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 135,000 mem

37、bers and volunteers 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

38、 community. Visit www.asme.org for more information. The ASME Standards Technology, LLC (ASME ST-LLC) is a not-for-profit Limited Liability Company, with ASME as the sole member, formed in 2004 to carry out work related to newly commercialized technology. The ASME ST-LLC mission includes meeting the

39、 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 research and technology development needed to establish and maintain the technical relevance of code

40、s and standards. Visit www.stllc.asme.org for more information. STP-NU-063 Correct and Extend Allowable Stress Values for 304 and 316 SS viii EXECUTIVE SUMMARY This report was undertaken to correct the existing Subsection NH stress values and extend the time-dependent allowable stress values for 304

41、 and 316 stainless steel to 500,000 hours. Extending the Code allowable stress values to 500,000 hours will allow Generation IV plant components to have a 60-year design life. The current stress values in the NH Code are based on an older and obsolete materials property database. The time-dependent

42、data currently available in the public domain for 304 and 316 stainless steel is much larger and has been used for developing the new allowable stress values. The allowable stress values that were corrected and extended are the time-dependent minimum stress-to-rupture strength (Sr), and stress inten

43、sity (St and Smt) values. The values were developed using a Larson-Miller parameter analysis. The Sr and St values at long times and high temperatures are lower than the current Code values, and the long time, high temperature St values are controlled by the time-to-tertiary creep data. The upper li

44、mit on the St values was revised from “minimum stress to 1% strain” to “average stress to 1% strain”. Therefore, the short time, low temperature stress values are higher than the current NH Code. Statistical analyses did not reveal any correlation between the time-to-tertiary creep and time-to-ruptu

45、re. Correct and Extend Allowable Stress Values for 304 and 316 SS STP-NU-063 1 1 INTRODUCTION 1.1 Purpose This report presents revised allowable stress values for 304 and 316 stainless steel for inclusion in the ASME Boiler and Pressure Vessel Code (ASME BPV Code), Section III, Subsection NH Compone

46、nts in Elevated Temperature Service. 1.2 Background The U.S. Department of Energy (DOE) has established a program to develop next generation nuclear reactors. This program, known as Generation IV (Gen IV), addresses research and development (R&D) activities that are necessary to develop high efficie

47、ncy, next generation nuclear power plants such as high temperature gas-cooled and liquid-cooled reactors. One of the challenges identified by this program was the development of necessary codes and standards to support the design and construction of Gen IV reactors. Therefore, a three-year collabora

48、tive effort was established between DOE and ASME to address technical issues related to codes and standards applicable to the Generation IV program. A number of tasks were identified by ASME Standards Technology, LLC (ASME ST-LLC) as high priority items for Gen IV reactors. One of these tasks is Tas

49、k 14a. The purpose of Task 14a is to correct and extend the allowable stress values for Type 304 and 316 stainless steels (SS) to 500,000 hours in ASME BPV Code, Section III, Subsection NH. A precursor to this task was ASME ST-LLC Task 6 (STP-NU-037), which reviewed the current creep property databases for materials in NH for consistency, and for the feasibility of extending allowable stress values for a design life of 500,000 hours from 300,000 h