ASME STP-NU-044-2011 NON DESTRUCTIVE EXAMINATION (NDE) AND IN-SERVICE INSPECTION (ISI) TECHNOLOGY FOR HIGH TEMPERATURE REACTORS《高温反应堆的非破坏性测试(NDE)和在役检测技术(ISI)》.pdf

1、STP-NU-044NON DESTRUCTIVE EXAMINATION (NDE) AND IN-SERVICE INSPECTION (ISI) TECHNOLOGY FOR HIGH TEMPERATURE REACTORSSTP-NU-044 NON DESTRUCTIVE EXAMINATION (NDE) AND IN-SERVICE INSPECTION (ISI) TECHNOLOGY FOR HIGH TEMPERATURE REACTORS Prepared by: Bruce Bishop, Ralph Hill, Zoran Kuljis, Edward L. Ple

2、ins and Sten Caspersson Westinghouse Electric Company, LLC Neil Broom, John Fletcher and Kobus Smit PBMR Date of Issuance: December 15, 2011 This report was prepared as an account of work sponsored by the United States Nuclear Regulatory Commission (NRC) and the ASME Standards Technology, LLC (ASME

3、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 ac

4、curacy, 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 n

5、ot 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 not necessarily state or reflect those of the United States Government or any agency thereof. Neither ASME, ASM

6、E 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 usefulne

7、ss 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 im

8、ply 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 do not necessarily reflect those of ASME ST-LLC or ot

9、hers 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

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12、, 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. 978-0-7918-3412-1 Copyright 2011 by ASME Standards Technology, LLC All Rights Reserved NDE and ISI Technology fo

13、r HTRs STP-NU-044 iii TABLE OF CONTENTS Foreword v Executive Summary and Conclusions . vi 1 Introduction 1 1.1 Task 12 Scope of Work . 1 1.2 Assumptions 1 1.3 Task 12 Part 1 Approach . 2 1.4 Task 12 Part 2 Approach . 3 2 Part 1- Assessment of Past HTGR Reactor Experience / Studies and Potential HTGR

14、 Material Degradation Mechanisms . 4 2.1 Assessment of Past HTGR Reactor Experience/Studies . 4 2.2 Potential HTGR Material Degradation Mechanisms. 5 3 Part 1 Evaluation of HTGR Examination Methods and ISI Strategy . 11 3.1 Available Non Destructive Examination Techniques . 11 3.2 Environmental Cond

15、itions . 15 3.3 Flaw Acceptance Resolution . 16 3.4 Degradation Mechanisms and NDE/NDM Techniques 16 3.4.1 High Energy Radiation Embrittlement (RE) 16 3.4.2 Thermal Transients and Thermal Stratification Cycling and Striping (TT and TASCS) 17 3.4.3 Flow Induced Vibrations (FIV) 17 3.4.4 Self Welding

16、and Fretting Fatigue (SF) . 17 3.4.5 Mechanical Fatigue (MF) . 17 3.4.6 Stress Corrosion Cracking (SCC) . 18 3.4.7 Creep and Creep Fatigue (CF) 18 3.5 Advanced Material Characterization . 19 3.5.1 Non Destructive Characterization 19 3.5.2 NDE Techniques for Fast Neutron Embrittlement of RPV Steels .

17、 20 3.5.3 Advanced Mechanical Testing with Micro Samples 21 4 Part 1 - HTGR NDE and ISI Technology Assessment Road Map 24 4.1 Technology Road Map Short Term Needs . 24 4.1.1 Helium Leak Monitoring 24 4.1.2 Development of Non-Contact UT with Laser UT and EMAT . 24 4.1.3 Infrared Monitoring 25 4.1.4 T

18、hin Wall Inspection Techniques . 25 4.1.5 Remote Delivery Robotics . 25 4.2 Technology Road Map Long Term Needs . 25 4.2.1 Creep Monitoring . 26 4.2.2 Continuous Material Monitoring 26 5 Part 2 - Methods and Requirements for Examination of Metallic Materials . 27 5.1 Deterministic Piping Analysis Me

19、thods of Current ASME Code . 27 5.2 Reliability-Based Load and Resistance Factor Design (LRFD) Methods . 28 5.3 Technical Basis for Advanced Inspection Requirements 30 STP-NU-044 NDE and ISI Technology for HTRs iv 5.4 LRFD Development of Advance Inspection Requirements 32 6 Integrated Technology Roa

20、d Map . 34 6.1 Complete CRTD-86 LRFD Design Methodology 34 6.2 Phase 1 LRFD Development Activities 35 6.3 Short Term NDE and NDM Development Activities . 35 6.4 Phase 2 LRFD Activities . 35 6.5 Long Term NDE and NDM Development Activities . 35 6.6 Phase 3 LRFD Activities . 35 Appendix A: Table IGA-2

21、300-1 Degradation Mechanism Attributes and Attribute Criteria 37 Appendix B: NDE and ISI Technology for HTRs, Scope Description 45 References 46 Acknowledgments 48 Abbreviations and Acronyms . 49 LIST OF TABLES Table 1 - Summary of DMA Results for PBMR 8 Table 2 - NDE Technique Applicability to HTGR

22、 Components for ISI / Monitoring 9 Table 3 - NDE/NDM Techniques Applicable to HTGR 12 Table 4 - Micro Sample Techniques 22 Table 5 - Sample Target Reliability Levels and Partial Safety Factors for Demonstration Purposes 31 Table 6 - Research Activities to Complete ASME LRFD Code for Class 2/2 . 34 L

23、IST OF FIGURES Figure 1 - Steel Vessel Modular HTGR Pressure Boundary (PBMR Brayton Cycle Concept) 7 Figure 2 - Reliability Density Functions of Resistance R and Load L . 29 Figure 3 - HTGR NDE/NDM/ISI/LRFD Technology Road Map 36 NDE and ISI Technology for HTRs STP-NU-044 v FOREWORD This document is

24、 the result of work resulting from a Cooperative Agreement between the United States Nuclear Regulatory Commission (NRC) 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 necessa

25、ry 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. This report is the result of work performed under Task 12 titled “Non Destructive Examination (NDE) and In-service Inspect

26、ion (ISI) Technology for High Temperature Reactors.” 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 an

27、d 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 gover

28、nment 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 commer

29、cialization 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 4. ASME Standards promote safety, reliability and component interchangeability

30、in 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 code

31、s 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

32、, 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 com

33、mercialized 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. STP-NU-044 NDE and ISI Technology for HTRsvi EXECUTIVE SUMMARY AND CONCLUSIONS The

34、Gen IV / NGNP Materials Project Task 12 (Non Destructive Examination (NDE) and In-service Inspection (ISI) Technology for High Temperature Reactors) is sponsored through a Cooperative Agreement between the ASME Standards Technology, LLC (ASME ST-LLC) and the United States Nuclear Regulatory Commissi

35、on (NRC). The results of the task are intended to complement the efforts of previous tasks sponsored by the U.S. Department of Energy (DOE) supporting the Generation IV / Next Generation Nuclear Plants (NGNP). The objective of Task 12 is to provide support to the NRC in developing a technical basis

36、document to update and expand codes and standards for NDE and ISI methods and monitoring in next generation HTGRs that operate at elevated temperatures and to identify technology gaps where future research is needed (Appendix B). The findings of this study will assist codes and standards committees

37、and jurisdictional authorities in adopting improved NDE methods into codes and standards. The approach recommended in this report reflects the Reliability and Integrity Management (RIM) strategy which forms the basis for the ASME Section XI Division 2 rewrite (ISI Code for HTGRs). This report identi

38、fies several Non Destructive Examination (NDE) technologies applicable to components of High Temperature Gas-cooled Reactors (HTGRs) for in-service inspection. Several of the technologies identified may require additional technology development to support the transition from laboratory applications

39、to field deployable systems. Other technologies may need additional development to harden the sensors for use in the harsh environments anticipated in an HTGR. Other technologies may only need additional code rules for the application of the technology for HTGR applications. Part 1 of Task 12 provid

40、es an assessment of past HTGR reactor experience and identifies potential material degradation mechanisms and susceptibility criteria for the current design concepts. The assessment focuses on the PBMR design and service conditions but also encompasses ANTARES (AREVA) and GT-MHR (General Atomics) de

41、sign and service conditions. All three concepts use currently available technology and fit within the current NGNP design envelope. Part 1 also provides an evaluation of appropriate NDE methods and ISI strategy. For the steel vessel HTGR concept, this paper proposes an approach which requires the ow

42、ner to establish combinations of strategies for the reliability and integrity management (RIM) of passive components to achieve reliability goals. HTGRs are expected to be designed to accommodate both outage-based and on-line monitoring and examination. To emphasize this approach this report introdu

43、ces the concept of Non Destructive Monitoring (NDM), analogous to Non Destructive Examination (NDE), where NDM is defined as the targeted on-line monitoring of active degradation mechanisms at potentially susceptible regions. To provide a technical basis for the assessment of the applicability of ex

44、isting and new technologies for in-service inspection and monitoring of HTGRs it was important to understand the potential degradation that HTGRs are subject to as a consequence of the design assumptions and service environment. Based on existing experience in Light Water Reactors (LWR) and current

45、advancement of new material monitoring technologies, preferable technologies were selected for application in HTGRs. The needs for further developments were established to address the environmental specifics, such as elevated temperatures and a need for more extensive monitoring through prolonged op

46、erating cycles. Design and operating conditions characteristic of pressurized components in the steel vessel HTGR concepts have shown similar environmental conditions (inspected surface temperature) experienced in the existing LWRs during scheduled maintenance cycles. This has allowed utilizing the

47、existing experiences from non destructive inspections (NDE) accumulated with LWR in-service inspection (ISI) programs. Specific environmental conditions and a need for on-line monitoring during the prolonged operating cycles expected in HTGRs have identified the recommendation of further development

48、s. Areas of further NDE/NDM development include advancement in helium leak monitoring, non-contact UT (Laser UT and EMAT) and further extension of acoustic emission for crack detection, leak detection and loose part monitoring. The need for further improvement of remote robotic mechanisms to support

49、 elevated NDE and ISI Technology for HTRs STP-NU-044 vii temperature environments was also identified. Recommendations were made to continue to follow advancements and new developments in the field of material characterization, with monitoring of acoustic and electromagnetic properties combined with advanced mechanical testing with micro sampling. The original ASME work scope for Part 2 of Task 12 was to identify appropriate new construction and in-service NDE methods for examination of metallic materials (e.g., acoustic emission, ultrasonic). Studies would be b