Asme stp nu 042 2011 (american society of mechanical engineers)

STP-NU-042 Designator: Meta Bold 24/26 Revision Note: Meta Black 14/16 NEW MATERIALS FOR ASME SUBSECTION NH STP-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 Services 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 Neither the United States Government nor any agency thereof, nor any of their 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 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 not 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, 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 upon 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 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, contributors and reviewers of the report expressed herein 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 connection 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 such 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 trademark 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 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 TABLE OF CONTENTS Foreword vii Abstract viii PART I 1 SELECTION OF CANDIDATE MATERIALS AND CORRESPONDING TIME AND TEMPERATURE OPERATING CONDITIONS 1.1 Considerations in Selecting the Candidate Materials 1.1.1 Corrosive Oxidation 1.1.2 High Temperature Strength 1.1.3 Low Temperature Strength and Other Properties 1.1.4 Workability and Weldability 1.2 Operating Time and Temperature Conditions REVIEW OF AVAILABLE JAPANESE DATA ON HASTELLOY XR AND INCONNEL 617 AND REQUIRED R&D 2.1 Review of Japanese information on Hastelloy XR and Inconel 617 2.1.1 Environmental Effects 2.1.2 Unique Tensile Stress-Strain Relationship Due To Dynamic Recrystalization 10 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 ESTIMATION 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 800°C and 100,000h 26 References - Part I 27 PART II 28 SELECTION OF CANDIDATE MATERIALS 29 1.1 Identification of Metallic Components and Operational Requirements 29 1.2 Required Properties for Construction of Section III Class 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 Code 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 36 REVIEW OF AVAILABLE DATA FOR CANDIDATE MATERIALS 42 iii STP-NU-042 New Materials for ASME Subsection NH 2.1 Needed Properties for 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: 45 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 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 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 - 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 - Chemical Composition of Hastelloy XR and Hastelloy X Table - Operating Conditions of the Main Components in an HTGR-IS Hydrogen Production System [3] Table - Impurities Levels of JAERI-B Type Helium Table - Candidate Materials Listed for Intermediate and High-Temperature Components for the Very High Temperature NGNP 31 Table - Potential Candidate Materials for Intermediate and High-Temperature Metallic Components in the VHTR Concept of the NGNP Reactor 32 LIST OF FIGURES Figure - Environmental Effects on the Creep Rupture Strength of Inconel 617 and Hastelloy XR at HTGR iv New Materials for ASME Subsection NH STP-NU-042 Figure - Environmental Effect and Test Specimen Configuration Dependence on Low Cycle Fatigue Strength within a Fast-Fast Type Waveform for Inconel 617 at 1000°C [6] Figure - Environmental Effect on Low Cycle Fatigue Strength Under Fast-Fast Type Waveform for Hatelloy XR at 950°C [6] Figure - Environmental Effect on the Cyclic Stress-Strain Relationship of Inconel 617 and Hastelloy XR at HGTR Temperatures [6] Figure - Illustration of Reduced Creep Rupture Strength of Inconnel 617 in HTGR-He Environment at 1000°C and Corresponding Unaffected Strength of Hastelloy XR 10 Figure - Tensile Stress-Strain Curves of Hastelloy XR at Various Temperatures at the Strain Rate Specified in JIS Standards [5] 11 Figure - Tensile Stress-Strain Curves of Hastelloy XR at 950°C at Various Extension Rates [5] 11 Figure - Extension Rate Dependence of Yield Strength and Tensile Strength of Hastelloy XR at 800 and 1000°C [4] 12 Figure - Schematic Illustration of Extension Rate (Strain Rate) Dependence 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 950°C 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 Waveform for Inconel 617 at 1000°C in 99.99% Helium [6] 15 Figure 12 - Effects of Strain Hold Time and Strain Rate on Low Cycle Fatigue Lives in the socalled 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 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 900°C and Comparison of the Observed Relaxation Curve with One Estimated Using Creep Data [6] 16 Figure 15 - Temperature and Stress Dependences of Reciprocal Time Constant in Primary Creep Regime r for Hastelloy XR in the High Temperature Region of 800°C 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 Fatigue 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 950°C in an HTGR-He Environment [6] 23 Figure 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 v STP-NU-042 New Materials for ASME Subsection NH Figure 24 - Comparisons of the Strength Based on 100,000 Hours for Alloys Intended for Service at Temperatures Around 800°C 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-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 Alloy 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 of Alloy 800H 54 Figure 34 - Tensile Yield Curves for Alloy 230 at 871°C (1600°F) 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 871°C 56 Figure 37 - Creep Curves for Alloy 556 at Three Temperatures 57 Figure 38 - Relaxation Behavior for Alloy 556 near 871°C 58 Figure 39 - Start of a 0.50 Hour Relaxation-Hold C-F Test on Alloy 556 at 871°C 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 Cycles 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 800°C 64 vi New Materials for ASME Subsection NH STP-NU-042 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 STLLC) 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 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 11 titled “New Materials for ASME Subsection NH.” 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 and serve as important technical bases for new rules These new rules will be developed under ASME’s 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 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 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 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 notfor-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 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 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 codes and standards Visit www.stllc.asme.org for more information vii STP-NU-042 New Materials for ASME Subsection NH ABSTRACT When selecting candidate materials, their resistance to environmental degradation caused by exposure to an HTGR helium atmosphere is a key factor Improving the resistance of commercially available Nickel base super alloys to corrosive oxidation in low oxidizing potential atmospheres such as HTGR-He was discussed in Part I of this report, with reference to, for example, the improved Hastelloy X resulting in Hastelloy XR With regard to the operating temperature, the required primary helium coolant temperature in the SI process (or IS process) was identified as being 950°C at the reactor outlet Review of the available information on Hastelloy XR and Inconel 617 as candidate materials was made in Part I of this report, and several critical issues discussed Information on Inconel 617 is from a Japanese project Those issues were identified with help from the author’s experiences in developing the HTTR high temperature structural design guide Some R&D needed to obtain approval for Subsection NH construction was then pointed out With estimating the strength characteristics, the design creep rupture strength was identified as being 14MPa for Hastelloy XR, even in the HTGR-He atmosphere The OSDP (Orr-Sherby-Dorn Parameter) method was applied to Hastelloy XR as an extrapolation technique to gain creep rupture strength values, primarily because of scarcity of data on the longer rupture life region In Part II of this report, the bounding conditions were briefly summarized for the Next Generation Nuclear Plant (NGNP) that is the leading candidate in the Department of Energy Generation IV reactor program Metallic materials essential to the successful development and proof of concept for the NGNP were identified The literature bearing on the materials technology for high-temperature gas-cooled reactors was reviewed with emphasis on the needs identified for the NGNP Several materials were identified for a more thorough study of their databases and behavioral features relative to the requirements ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NH Material properties required for the design and construction of components meeting the rules of ASME Section III Subsection NH (ASME III-NH) were reviewed in Part II An overview of the data available for candidate “new materials” for the Next Generation Nuclear Plant (NGNP) was undertaken with respect to meeting the needs for incorporation of the materials into ASME III-NH These materials included alloy 617, alloy 230 and alloy 556 for service to 800°C and above For service below 800°C, an “enhanced strength” stainless steel typical of a new group of such steels was included Although not a new material, alloy 800H was included in the review The data needs identified in the National Laboratories testing plans for the NGNP were considered In these plans, emphasis was placed on alloy 617 which is the leading candidate for the high-temperature metallic components in the NGNP for components operating above 800°C It was found that the plans were very comprehensive and identified the data needs for both incorporation of a new alloy into ASME III-NH and the complementary database needed for the application of the Code A comparison of the strength of several candidate alloys approved for ASME Section I or Section VIII, Division construction was made and this comparison supported the selection of alloy 617 as the leading candidate on the basis of strength With respect to compact heat exchangers, some concerns about the behavioral features of these alloys as fine-grained strip products were developed, and some comparisons were made between candidate alloys developed for high-temperature recuperators viii New Materials for ASME Subsection NH STP-NU-042 PART I Hastelloy XR and Inconel 61 New Materials for ASME Subsection NH STP-NU-042 81 STP-NU-042 New Materials for ASME Subsection NH 82 New Materials for ASME Subsection NH STP-NU-042 83 STP-NU-042 New Materials for ASME Subsection NH 84 New Materials for ASME Subsection NH STP-NU-042 85 STP-NU-042 New Materials for ASME Subsection NH 86 New Materials for ASME Subsection NH STP-NU-042 87 STP-NU-042 New Materials for ASME Subsection NH 88 New Materials for ASME Subsection NH STP-NU-042 APPENDIX B - TESTS AND ESTIMATED COSTS Table 800H-1A Tensile tests on stabilized alloy 800H: Material: Solution annealed plus 980°C for hours Specimen No 800H-1 A1 800H-1 A2 800H-1 A3 800H-1 A4 Temperature °C 23 600 700 800 Cross Head Rate 0.005/min 0.005/min 0.005/min 0.005/min Estimated cost for testing: $2K Table 800H-1B Creep tests on stabilized alloy 800H to check primary creep: Material: Solution annealed plus 980°C for hours Specimen No 800H-1 B1 800H-1 B2 800H-1 B3 800H-1 B4 Temperature °C 600 650 700 750 Stress TBD TBD TBD TBD Expected Time 000 000 000 000 Estimated cost for testing: $5K Table 800H-2: Strain-rate effects on the strength and ductility of alloy 800H: These tests are identical to those listed in the National Laboratories NGNP IHX Materials R&D Plan Table A-28 Estimated cost for testing: $13K Table 800H-3 Diffusional creep in alloy 800H: These tests are identical to those listed in the National Laboratories NGNP IHX Materials R&D Plan Table A29 Estimated cost of testing: $17K Table 800H-4 Multiaxial creep rupture in alloy 800H: The testing is identical to the National Laboratories NGNP IHX Materials R&D Plan Table A31 The estimated cost of testing: $126K 89 STP-NU-042 New Materials for ASME Subsection NH Supplementary multiaxial stress testing of alloy 800H: Material: 800H bar or plate product machined to round notched bars Specimen No Notch Type* Kt Value* 800H-4-1 800H-4-2 800H-4-3 800H-4-4 800H-4-5 800H-4-6 800H-4-7 800H-4-8 TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD Temperature (°C) 760 760 760 760 850 850 850 850 Stress Expected Life (h) 000 3000 0000 30000 000 3000 0000 30000 TBD TBD TBD TBD TBD TBD TBD TBD *See Marriott & Carter, “Specimen Design for Creep Characterization Under Multiaxial Stress,” paper PVP2005-71419 Estimated cost for testing $90K Table 800H-5 Filler metals and weldments for stress factors for alloy 800H: The recommended testing is identical to the National Laboratories NGNP IHX R&D Materials Plan Table A27 The estimated cost of testing: $475K Supplementary creep-rupture testing of filler metals and weldments for alloy 800H: Specimen No Filler Process Type Specimen 800H-5-w1 800H-5-w2 800H-5-w3 800H-5-w4 800H-5-w5 800H-5-w6 800H-5-w7 800H-5-w8 800H-5-w9 800H-5-w1 800H-5-w1 800H-5-w1 82 82 82 82 82 82 82 82 82 82 82 82 GTA GTA GTA GTA GTA GTA GTA GTA GTA GTA GTA GTA Cross Cross Cross Cross Cross Cross Weld Weld Weld Weld Weld Weld of Temperature (°C) 750 750 750 850 850 850 750 750 750 850 850 850 The estimated cost of testing: $172K 90 Stress Expected Life (h) TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD TBD 3000 0000 30000 3000 0000 30000 3000 0000 30000 3000 0000 30000 New Materials for ASME Subsection NH STP-NU-042 Table 617-1A Tensile tests on stabilized alloy 617: Material: Solution annealed plus 980°C for hours Specimen No 61 7-1 A1 61 7-1 A2 61 7-1 A3 61 7-1 A4 Temperature °C 23 700 800 900 Cross Head Rate 0.005/min 0.005/min 0.005/min 0.005/min Estimated cost for testing: $2K Table 617-1B Creep tests on stabilized alloy 617 to check primary creep: Material: Solution annealed plus 980°C for hours Specimen No 61 7-1 B1 61 7-1 B2 61 7-1 B3 61 7-1 B4 Temperature °C 750 800 850 900 Stress TBD TBD TBD TBD Expected Time 000 000 000 000 Estimated cost for testing: $5K Table 617-2 Effect of temperature and strain rate on the tensile stress-strain curves for alloy 617: The tests are identical to the National Laboratories NGNP IHX Materials R&D Plan Table A1 Estimated cost for testing: $20K Supplemental testing to check strain-rate dependence of ultimate strength & ductility Specimen No 61 7-2-1 61 7-2-2 61 7-2-3 61 7-2-4 61 7-2-5 61 7-2-6 61 7-2-7 61 7-2-8 61 7-2-9 61 7-2-1 61 7-2-1 61 7-2-1 61 7-2-1 61 7-2-1 61 7-2-1 61 7-2-1 Temperature (°C) 750 750 750 750 800 800 800 800 850 850 850 850 900 900 900 900 Crosshead Rate /min 0.5 0.05 0.005 0.0005 0.5 0.05 0.005 0.0005 0.5 0.05 0.005 0.0005 0.5 0.05 0.005 0.0005 Estimated cost of testing: $16K 91 STP-NU-042 New Materials for ASME Subsection NH Table 617-3 Grain size and diffusional effects in creep of alloy 617: These tests are identical to those listed in the National Laboratories NGNP IHX R&D Materials Plan Table A24 and A25 Estimated cost of testing: $460K Table 617-4 Multiaxial creep rupture in alloy 617: The majority of testing is blended into the tables that focus on the development of the UCM and are included in the National Laboratories NGNP IHX Materials R&D Plan Tables A5 to Table A14 and the tube-burst and multiaxial creep tests in Table A15 and A21 The estimated cost of testing: $520K Supplementary multiaxial stress testing of alloy 617 Material: 617 bar or plate product machined to round notched bars Specimen No 800H-4-1 800H-4-2 800H-4-3 800H-4-4 800H-4-5 800H-4-6 800H-4-7 800H-4-8 Notch Type* TBD TBD TBD TBD TBD TBD TBD TBD Kt Value* TBD TBD TBD TBD TBD TBD TBD TBD Temperature (°C) 760 760 760 760 850 850 850 850 Stress TBD TBD TBD TBD TBD TBD TBD TBD Expected Life (h) 000 3000 0000 30000 000 3000 0000 30000 *See Marriott & Carter, “Specimen Design for Creep Characterization Under Multiaxial Stress,” paper PVP2005-71419 Estimated cost for testing $90K Table 617-5 Filler metals and weldments for alloy 617: The recommended testing is identical to the National Laboratories NGNP IHX R&D Materials Plan Table A2 and Table A3 The estimated cost of testing: $2400K for A2 and $300K for A3 Table 617-6 Long-time creep-rupture testing: The recommended testing is identical to the National Laboratories NGNP IHX R&D Materials Plan Table A17 and A13a The estimated cost of testing: $800K for A17 and $420K for A13a Table 617-7 Fatigue and creep-fatigue testing: The recommended testing is identical to the National Laboratories NGNP IHX R&D Materials Plan Table A19, A20, A23 The estimated cost of testing: $70K for A19 (Tests in helium not included.), $80K for A20 (Tests in helium not included.), and $200K for A23 92 New Materials for ASME Subsection NH STP-NU-042 Note on cost estimates Elevated temperature tensile tests are priced at $500 each No distinction is made between rupture testing and creep testing The estimate for creep-rupture testing is $1 /h plus a $200 set-up charge for tests lasting less than 00 hours Tube-burst and multiaxial creep tests performed in creep frames are priced at $2/h Multiaxial tests, fatigue test and creep-fatigue tests are priced at $1 0/h The cost of specimen preparation and materials are not included Calibrations and record keeping in conformance with NQA-1 and other standards are included The cost of scientific personnel, project management overhead and the like are not included 93 STP-NU-042 New Materials for ASME Subsection NH ACKNOWLEDGMENTS The authors acknowledge, with deep appreciation, the following individuals for their technical and editorial peer review of this document: ? Robert I Jetter, P.E ? Ting-Leung (Sam) Sham, Ph.D ? Weiju Ren, Ph.D The authors further acknowledge, with deep appreciation, the activities of ASME ST-LLC and ASME staff and volunteers who have provided valuable technical input, advice and assistance with review of, commenting on, and editing of, this document 94 A21 91 Q