Proactive Management of Materials Degradation - A Review of Principles and Programs

The U.S. Nuclear Regulatory Commission (NRC) has undertaken a program to lay the technical foundation for defining proactive actions so that future degradation of materials in light water reactors (LWRs) is limited and, thereby, does not diminish either the integrity of important LWR components or the safety of operating plants. This technical letter report was prepared by staff at Pacific Northwest National Laboratory in support of the NRC Proactive Management of Materials Degradation (PMMD) program and relies heavily on work that was completed by Dr. Joseph Muscara and documented in NUREG/CR-6923. This report concisely explains the basic principles of PMMD and its relationship to prognostics, provides a review of programs related to PMMD being conducted worldwide, and provides an assessment of the technical gaps in PMMD and prognostics that need to be addressed. This technical letter report is timely because the majority of the U.S. reactor fleet is applying for license renewal, and many plants are also applying for increases in power rating. Both of these changes could increase the likelihood of materials degradation and underline, therefore, the interest in proactive management in the future.

[1]  Tai-hyun Kim,et al.  Current Status of Continued Operation for Kori unit 1 beyond Design Life , 2006 .

[2]  R. C. Kryter,et al.  Insights gained from aging research , 1992 .

[3]  Leo Christodoulou,et al.  Materials Damage Prognosis - Proceedings of a Symposium of the Materials Science and Technology 2004 Conference: Preface , 2005 .

[4]  Samuel H. Huang,et al.  System health monitoring and prognostics — a review of current paradigms and practices , 2006 .

[5]  Eberhard Roos,et al.  Planning and use of condition-dependent NDT for the interaction between fracture mechanics and quantitative NDT , 2001 .

[6]  Steven R. Doctor.  Measurement Challenges Associated With Irradiated Reactor Components , 1997 .

[7]  Eberhard Roos,et al.  Lifetime management for mechanical systems, structures and components in nuclear power plants , 2006 .

[8]  Michael F. Hessheimer,et al.  An International Standard Problem: Analysis of 1:4-Scale Prestressed Concrete Containment Vessel Model under Severe Accident Conditions , 2005 .

[9]  Gerd Dobmann,et al.  Aging material evaluation and studies by non-destructive techniques (AMES-NDT) — a European network project , 2001 .

[10]  Steven R. Doctor,et al.  From NDE to Prognostics: A Revolution in Asset Management for Generation IV Nuclear Power Plants , 2007 .

[11]  L. Bond,et al.  Prognostics and Condition-Based Maintenance: A New Approach to Precursive Metrics , 2004 .

[12]  Hong Sung-Yull,et al.  The Status of Plant Life Assessment Program of Wolsong Unit 1 , 2006 .

[13]  Leonard J. Bond.  Predictive engineering for aging infrastructure , 1999, Smart Structures.

[14]  A. Urmanov.  Electronic Prognostics for Computer Servers , 2007, 2007 Annual Reliability and Maintainability Symposium.

[15]  Tapio Planman,et al.  Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants , 2005 .

[16]  Michael Kröning,et al.  Nondestructive characterization of materials (ultrasonic and micromagnetic techniques) for strength and toughness prediction and the detection of early creep damage , 1995 .

[17]  Norio Nakagawa,et al.  On-Line NDE and Structural Health Monitoring for Advanced Reactors , 2006 .

[18]  Jangbom Chai,et al.  NERI Final Project Report: On-Line Intelligent Self-Diagnostic Monitoring System for Next Generation Nuclear Power Plants , 2003 .

[19]  Fu-Kuo Chang,et al.  Structural Health Monitoring , 2016 .

[20]  M. B. Bakirov,et al.  Managing the service life of heat-exchanging and mechanical equipment and pipelines operating at Russian nuclear power stations , 2007 .

[21]  Steven R. Doctor,et al.  Improved Economics of Nuclear Plant Life Management , 2007 .

[22]  H. M. Hashemian,et al.  On-line testing of calibration of process instrumentation channels in nuclear power plants. Phase 2, Final report , 1995 .

[23]  Akihiro Yamamoto,et al.  SCAP: the NEA project on stress corrosion cracking and cable ageing , 2007 .

[24]  Norbert Meyendorf,et al.  Nondestructive characterization of materials A growing demand for describing damage and service-life-relevant aging processes in plant components , 1997 .

[25]  Bryan Johnson,et al.  Predictive maintenance : The effect on a Company's Bottom line , 2000 .

[26]  Sevini Filippo.  Application of Surveillance Programme Results to Reactor Pressure Vessel Integrity Assessment" - Results of a Co-ordinated project , 2005 .

[27]  Hans J. Weber.  Role of nondestructive evaluation in civil aviation: historical development, current status, future challenges , 1995, Smart Structures.

[28]  H. M. Hashemian,et al.  Long term performance and aging characteristics of nuclear plant pressure transmitters , 1993 .

[29]  A. Burton Johnson,et al.  Program Plan for Acquiring and Examining Naturally Aged Materials and Components from Nuclear Reactors , 2002 .

[30]  Noriyoshi Maeda,et al.  Research Activities for Nuclear Power Plant Aging Promoted by PLEC, JAPEIC, Japan , 2004 .

[31]  P. Contri,et al.  Optimal Integration of Maintenance Programs with other Safety Related Programs in a Plant Life Management Framework , 2007 .

[32]  G. R. Forrer,et al.  In-service inspection of nuclear plants. , 1972 .

[33]  Leonard J. Bond,et al.  The nuclear education and staffing challenge: Rebuilding critical skills in nuclear science and technology , 2005 .

[34]  Barry Marsden,et al.  Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs , 2008 .

[35]  James B. Roberto,et al.  Basic research needs for advanced nuclear energy systems , 2007 .

[36]  Jaharlal Koley,et al.  Regulatory practices for nuclear power plants in India , 2006 .

[37]  Gerd Dobmann.  NDE for material characterisation of ageing due to thermal embrittlement, fatigue and neutron degradation , 2006 .

[38]  K Kussmaul.  25th Water Reactor Safety Information Meeting , 1999 .