Technical Needs for Prototypic Prognostic Technique Demonstration for Advanced Small Modular Reactor Passive Components

This report identifies a number of requirements for prognostics health management of passive systems in AdvSMRs, documents technical gaps in establishing a prototypical prognostic methodology for this purpose, and describes a preliminary research plan for addressing these technical gaps. AdvSMRs span multiple concepts; therefore a technology- and design-neutral approach is taken, with the focus being on characteristics that are likely to be common to all or several AdvSMR concepts. An evaluation of available literature is used to identify proposed concepts for AdvSMRs along with likely operational characteristics. Available operating experience of advanced reactors is used in identifying passive components that may be subject to degradation, materials likely to be used for these components, and potential modes of degradation of these components. This information helps in assessing measurement needs for PHM systems, as well as defining functional requirements of PHM systems. An assessment of current state-of-the-art approaches to measurements, sensors and instrumentation, diagnostics and prognostics is also documented. This state-of-the-art evaluation, combined with the requirements, may be used to identify technical gaps and research needs in the development, evaluation, and deployment of PHM systems for AdvSMRs. A preliminary research plan to address high-priority research needs for the deployment of PHM systemsmore » to AdvSMRs is described, with the objective being the demonstration of prototypic prognostics technology for passive components in AdvSMRs. Greater efficiency in achieving this objective can be gained through judicious selection of materials and degradation modes that are relevant to proposed AdvSMR concepts, and for which significant knowledge already exists. These selections were made based on multiple constraints including the analysis performed in this document, ready access to laboratory-scale facilities for materials testing and measurement, and potential synergies with other national laboratory and university partners.« less

[1]  Georgy Toshinsky,et al.  Modular Lead-Bismuth Fast Reactors in Nuclear Power , 2012 .

[2]  Ayman Abdalla,et al.  Sensitivity Analysis of Fuel Centerline Temperatures in SuperCritical Water-cooled Reactors (SCWRs) , 2012 .

[3]  G. Biswas,et al.  PHM Integration with Maintenance and Inventory Management Systems , 2006, 2007 IEEE Aerospace Conference.

[4]  Hoon Sohn,et al.  A review of structural health monitoring literature 1996-2001 , 2002 .

[5]  Aziz I. Asphahani,et al.  Research Opportunities in Corrosion Science and Engineering , 2011 .

[6]  G. Sasikala,et al.  A Comparative Study of the Creep Rupture Properties of Type 316 Stainless Steel Base and Weld Metals , 1993 .

[7]  Sabu John,et al.  A Review of Passive Wireless Sensors for Structural Health Monitoring , 2013 .

[8]  Johan Carlsson,et al.  Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects, severe safety and economical issues , 2006 .

[9]  Kazimierz Sobczyk,et al.  Stochastic Modeling of Microstructures , 2001 .

[10]  H. Macpherson The Molten Salt Reactor Adventure , 1985 .

[11]  Fredric A. Simonen,et al.  Probabilistic Fracture Mechanics Evaluation of Selected Passive Components – Technical Letter Report , 2007 .

[12]  Piero Baraldi,et al.  Ensemble of bootstrapped models for the prediction of the remaining useful life of a creeping turbine blade , 2012, 2012 IEEE Conference on Prognostics and Health Management.

[13]  Robert Dobson,et al.  In-core high temperature measurement using fiber-Bragg gratings for nuclear reactors , 2012 .

[14]  Robert M. Pap,et al.  A Hierarchical Data Structure Representation For Fusing Multisensor Information , 1989, Defense, Security, and Sensing.

[15]  V. S. Stepanov,et al.  Use of lead-bismuth coolant in nuclear reactors and accelerator-driven systems , 1997 .

[16]  R. Maxwell European nuclear society , 1975 .

[17]  Belle R. Upadhyaya,et al.  Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration , 2011 .

[18]  Robert B. Abernethy,et al.  The new Weibull handbook , 1993 .

[19]  Thomas R. Shrout,et al.  Piezoelectric accelerometers for ultrahigh temperature application , 2010 .

[20]  Sandia Report,et al.  Sodium Fast Reactor Safety and Licensing Research Plan - Volume I , 2012 .

[21]  Robert S. Fielder,et al.  High-temperature fiber optic sensors for harsh environment applications , 2004, SPIE Optics East.

[22]  Olaf Wedemeyer,et al.  Gas/liquid oxygen-transfer to flowing lead alloys , 2011 .

[23]  Michael Pecht,et al.  Physics-of-failure-based prognostics for electronic products , 2009 .

[24]  Jerome Peter Lynch,et al.  An overview of wireless structural health monitoring for civil structures , 2007, Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences.

[25]  Myung-Hyun Kim,et al.  Performance Analysis of a Pb-Bi Cooled Fast Reactor - PEACER-300 in Proliferation Resistance and Transmutation Aspects , 2006 .

[26]  R. C. Kryter,et al.  Current applications of vibration monitoring and neutron noise analysis , 1990 .

[27]  Jeffrey W. Griffin,et al.  Materials issues in high temperature ultrasonic transducers for under-sodium viewing , 2012 .

[28]  P. H. Hutton,et al.  Continuous AE crack monitoring of a dissimilar metal weldment at Limerick Unit 1 , 1993 .

[29]  Kathy McCarthy,et al.  Idaho National Laboratory , 2009 .

[30]  Steven R. Doctor,et al.  Proactive Management of Materials Degradation - A Review of Principles and Programs , 2008 .

[31]  Robert Hill,et al.  Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios. , 2008 .

[32]  F. Delage,et al.  Sodium fast reactor evaluation: Core materials , 2009 .

[33]  A. P. Berens,et al.  Statistical Methods for Estimating Crack Detection Probabilities , 1983 .

[34]  James J. Sienicki,et al.  Status report on the Small Secure Transportable Autonomous Reactor (SSTAR) /Lead-cooled Fast Reactor (LFR) and supporting research and development. , 2008 .

[35]  M. J. Driscoll,et al.  ASSESSMENT OF GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO 2 CYCLE , 2006 .

[36]  Van Uffelen Paul,et al.  Analysis of Reactor Fuel Rod Behaviour , 2010 .

[37]  M. Yetisir,et al.  The Supersafe© Reactor: A Small Modular Pressure Tube SCWR , 2012 .

[38]  Krishna R. Pattipati,et al.  An interacting multiple model approach to model-based prognostics , 2003, SMC'03 Conference Proceedings. 2003 IEEE International Conference on Systems, Man and Cybernetics. Conference Theme - System Security and Assurance (Cat. No.03CH37483).

[39]  Jan Drewes Achenbach,et al.  Structural Health Monitoring and Damage Prognosis in Fatigue , 2008 .

[40]  Peter Bajcsy,et al.  Multisensor raster and vector data fusion based on uncertainty modeling , 2004, 2004 International Conference on Image Processing, 2004. ICIP '04..

[41]  Zdzislaw Mazur,et al.  Failure analysis of a gas turbine blade made of Inconel 738LC alloy , 2005 .

[42]  Dan Ilas,et al.  Preliminary Nuclear Design Studies for a Small Modular Advanced High Temperature Reactor (SmAHTR) , 2010 .

[43]  M. Lowe,et al.  Defect detection in pipes using guided waves , 1998 .

[44]  Ian Mckirdy Summary of Planned Implementation for the HTGR Lessons Learned Applicable to the NGNP , 2011 .

[45]  Yoshiaki Oka,et al.  Super Light Water Reactors and Super Fast Reactors: Supercritical-Pressure Light Water Cooled Reactors , 2010 .

[46]  S. H. Jeong,et al.  Analysis of Heavy Eutectic Loop for Investigation of Operability and Safety , 2003 .

[47]  Santanu Das,et al.  Bayesian Statistic Based Multivariate Gaussian Process Approach for Offline/Online Fatigue Crack Growth Prediction , 2011 .

[48]  Alain Delchambre,et al.  Long-term radiation effects on fibre Bragg grating temperature sensors in a low flux nuclear reactor , 2004 .

[49]  David Lewis Moses,et al.  Very High-Temperature Reactor (VHTR) Proliferation Resistance and Physical Protection (PR&PP) , 2011 .

[50]  P. G. Bently A review of acoustic emission for pressurised water reactor applications , 1981 .

[51]  Satnam Singh,et al.  A prognostic framework for health management of coupled systems , 2011, 2011 IEEE Conference on Prognostics and Health Management.

[52]  P. Wilcox,et al.  The excitation and detection of Lamb waves with planar coil electromagnetic acoustic transducers , 2005, IEEE Transactions on Ultrasonics, Ferroelectrics and Frequency Control.

[53]  Timothy Abram,et al.  Generation-IV nuclear power: A review of the state of the science , 2008 .

[54]  Lalita Udpa,et al.  Time‐of‐Flight Measurements from Eddy Current Tests , 2003 .

[55]  Kevan D. Weaver,et al.  A Comparison of Long-Lived, Proliferation Resistant Fast Reactors , 2001 .

[56]  Huairui Guo,et al.  Predicting remaining useful life of an individual unit using proportional hazards model and logistic regression model , 2006, RAMS '06. Annual Reliability and Maintainability Symposium, 2006..

[57]  Jeffrey W. Griffin,et al.  A Bayesian Prognostic Algorithm for Assessing Remaining Useful Life of Nuclear Power Components , 2010 .

[58]  Naoto Kasahara,et al.  Evaluation on double-wall-tube residual stress distribution of sodium-heated steam generator by neutron diffraction and numerical analysis , 2012 .

[59]  H.K. Lee,et al.  Reusing OE-Scheduler in Aperiodic Environments , 2006, 2006 IEEE International Conference on Electro/Information Technology.

[60]  Subhas Chandra Mukhopadhyay,et al.  Sensors and Technologies for Structural Health Monitoring: A Review , 2011 .

[61]  E. L. Harder,et al.  The Institute of Electrical and Electronics Engineers, Inc. , 2019, 2019 IEEE International Conference on Software Architecture Companion (ICSA-C).

[62]  Werner Maschek,et al.  Heterogeneous cores for improved safety performance A case study : The supercritical water fast reactor , 2006 .

[63]  James J. Sienicki,et al.  Power Optimization in the STAR-LM Modular Natural Convection Reactor System , 2002 .

[64]  Jr B. F. Spencer,et al.  Structural Health Monitoring Using Smart Sensors , 2007 .

[65]  Yu-Chi Ho,et al.  Simple Explanation of the No Free Lunch Theorem of Optimization , 2001 .

[66]  Frank L. Lewis,et al.  Intelligent Fault Diagnosis and Prognosis for Engineering Systems , 2006 .

[67]  U. S. Doe A Technology Roadmap for Generation IV Nuclear Energy Systems , 2002 .

[68]  David Eugene Holcomb,et al.  HTGR Measurements and Instrumentation Systems , 2012 .

[69]  Baldev Raj,et al.  Assessment of microstructures and mechanical behaviour of metallic materials through non-destructive characterisation , 2003 .

[70]  Christopher Grandy,et al.  Simulator platform for fast reactor operation and safety technology demonstration , 2012 .

[71]  K. Bhanu Sankara Rao,et al.  Plant life management (PLiM) practices for sodium cooled fast neutron spectrum nuclear reactors (SFRs) , 2010 .

[72]  Alfons Weisenburger,et al.  Corrosion, Al containing corrosion barriers and mechanical properties of steels foreseen as structural materials in liquid lead alloy cooled nuclear systems , 2011 .

[73]  Stephen J. Mihailov,et al.  Fiber Bragg Grating Sensors for Harsh Environments , 2012, Sensors.

[74]  Ryan M. Meyer,et al.  Technical Needs for Enhancing Risk Monitors with Equipment Condition Assessment for Advanced Small Modular Reactors , 2013 .

[75]  S. Zinkle,et al.  Structural materials for fission & fusion energy , 2009 .

[76]  P. Ramuhalli,et al.  Maximum likelihood wavelet fusion for aerospace NDE applications , 2005, 2005 IEEE International Conference on Electro Information Technology.

[77]  Wargha Peiman,et al.  Supercritical-water experimental setup for in-pile operation , 2013 .

[78]  Kenneth L. Peddicord,et al.  STAR - H2 : the secure transportable autonomous reactor for hydrogen production and desalinization. , 2002 .

[79]  Stergios I. Roumeliotis,et al.  Extended Kalman filter for frequent local and infrequent global sensor data fusion , 1997, Other Conferences.

[80]  Stephen D. Unwin,et al.  Physics-Based Stress Corrosion Cracking Component Reliability Model cast in an R7-Compatible Cumulative Damage Framework Draft Report Supporting Technology Inputs to the Risk- Informed Safety Margin Characterization Pathway of the DOE Light Water Reactor Sustainability Program , 2011 .

[81]  Yong-Moo Cheong,et al.  Ultrasonic guided wave parameters for detection of axial cracks in feeder pipes of PHWR nuclear power plants. , 2004, Ultrasonics.

[82]  Kune Y. Suh,et al.  The concept of proliferation-resistant, environment-friendly, accident-tolerant, continual and economical reactor (PEACER) , 2000 .

[83]  C. Forsberg,et al.  Nuclear-Renewables Energy System for Hydrogen and Electricity Production , 2012 .

[84]  A. J. Goodjohn Summary of Gas-Cooled reactor programs , 1991 .

[85]  Ryan M. Meyer,et al.  Online Condition Monitoring to Enable Extended Operation of Nuclear Power Plants , 2014 .

[86]  S. Hannula,et al.  ASTM Special Technical Publication , 1986 .

[87]  Takamichi Iwamura,et al.  RAPID-L and RAPID Operator Free Fast Reactor Concepts Without Any Control Rods , 2003 .

[88]  R. Staehle,et al.  Quantitative Micro‐Nano (QMN) Approach to SCC Mechanism and Prediction‐Starting a Third Meeting , 2011 .

[89]  Daniel T Ingersoll,et al.  Deliberately Small Reactors and the Second Nuclear Era , 2009 .

[90]  Fredric A. Simonen,et al.  Evaluation of Environmental Effects on Fatigue Life of Piping , 2001 .

[91]  Kai Goebel,et al.  A Survey of Artificial Intelligence for Prognostics , 2007, AAAI Fall Symposium: Artificial Intelligence for Prognostics.

[92]  Sarat C. Dass,et al.  Particle-Filter-Based Multisensor Fusion for Solving Low-Frequency Electromagnetic NDE Inverse Problems , 2011, IEEE Transactions on Instrumentation and Measurement.

[93]  W. C. Haase,et al.  Advances in through-the-case eddy current sensors , 2013, 2013 IEEE Aerospace Conference.

[94]  Craig F. Smith,et al.  Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design , 2010 .

[95]  Gyuhae Park,et al.  Sensing Network Paradigms for Structural Health Monitoring , 2006 .

[96]  V. S. Stepanov,et al.  SVBR-100 module-type fast reactor of the IV generation for regional power industry , 2011 .

[97]  P. Runow,et al.  The use of acoustic emission methods as aids to the structural integrity assessment of nuclear power plants , 1985 .

[98]  Simon J. Watson,et al.  Physics of Failure approach to wind turbine condition based maintenance , 2009 .

[99]  Ines Latka,et al.  Inscription and characterization of Bragg gratings in single-crystal sapphire optical fibres for high-temperature sensor applications , 2009 .

[100]  James F. Manwell,et al.  Condition monitoring and prognosis of utility scale wind turbines , 2006 .

[101]  Joseph L. Rose,et al.  The upcoming revolution in ultrasonic guided waves , 2011, Smart Structures and Materials + Nondestructive Evaluation and Health Monitoring.

[102]  J. G. Murray,et al.  Core Knowledge on Instrumentation and Control Systems in Nuclear Power Plants , 2011 .

[103]  Farid Vakili Tahami,et al.  Creep Constitutive Equation for 2- Materials of Weldment-304L Stainless Steel , 2012 .

[104]  F. Carré,et al.  Structural materials challenges for advanced reactor systems , 2009 .

[105]  William J. O’Donnell,et al.  Historical Context of Elevated Temperature Structural Integrity for Next Generation Plants: Regulatory Safety Issues in Structural Design Criteria of ASME Section III Subsection NH , 2008 .

[106]  E. C. Bradley,et al.  Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High Temperature Reactor (SmAHTR) , 2011 .

[107]  David W. Engel,et al.  Survey and Evaluate Uncertainty Quantification Methodologies , 2012 .

[108]  Glenn Shafer,et al.  A Mathematical Theory of Evidence , 2020, A Mathematical Theory of Evidence.

[109]  D. Villiers,et al.  In-core temperature measurement for the PBMR using fibre-bragg gratings , 2009 .

[110]  Baldev Raj,et al.  Lessons Learned from Sodium-Cooled Fast Reactor Operation and Their Ramifications for Future Reactors with Respect to Enhanced Safety and Reliability , 2008 .

[111]  R. J. Baumhardt,et al.  Five years operating experience at the Fast Flux Test Facility , 1987 .

[112]  Hee Cheon No,et al.  A REVIEW OF HELIUM GAS TURBINE TECHNOLOGY FOR HIGH-TEMPERATURE GAS-COOLED REACTORS , 2007 .

[113]  Henry Ward Beecher Eyes and Ears , 2001 .

[114]  Jerome P. Lynch,et al.  A summary review of wireless sensors and sensor networks for structural health monitoring , 2006 .

[115]  J. M. Beck,et al.  High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant , 2011 .

[116]  P. J. Finck,et al.  Advanced burner test reactor preconceptual design report. , 2008 .

[117]  Young-Ha Hwang,et al.  Analysis of a J69-T-25 engine turbine blade fracture , 2002 .

[118]  D. Buckthorpe,et al.  RAPHAEL: Synthesis of achievements on materials and components and future direction ☆ , 2012 .

[119]  Dan Eliezer,et al.  The applicability of Norton's creep power law and its modified version to a single-crystal superalloy type CMSX-2 , 1996 .

[120]  Tomohiro Furukawa,et al.  Compatibility of FBR materials with sodium , 2009 .

[121]  Jin Jiang,et al.  Nuclear plant temperature instrumentation , 2009 .

[122]  Yasushi Tsuboi,et al.  Design Features, Economics, and Licensing of the 4S Reactor , 2010 .

[123]  Y. I. Chang,et al.  Small Modular Fast Reactor design description. , 2005 .

[124]  George Vachtsevanos,et al.  Methodologies for uncertainty management in prognostics , 2009, 2009 IEEE Aerospace conference.

[125]  A. M. Yacout,et al.  Design of the 4S Reactor , 2012 .

[126]  K. A. Bartels,et al.  Magnetostrictive sensor technology and its applications , 1998 .

[127]  Byeng D. Youn,et al.  A generic probabilistic framework for structural health prognostics and uncertainty management , 2012 .

[128]  Peter Cawley,et al.  A review of non-destructive techniques for the detection of creep damage in power plant steels , 2010 .

[129]  V. V. Orlov Fast neutron reactors , 1974 .

[130]  K. Chiang,et al.  On-line and real-time corrosion monitoring techniques of metals and alloys in nuclear power plants and laboratories , 2010 .

[131]  Asok Ray,et al.  Stochastic modeling of fatigue damage dynamics for failure prognostics and risk analysis , 1995, Proceedings of 1995 American Control Conference - ACC'95.

[132]  S. C. Lu,et al.  Theoretical and user's manual for pc-PRAISE: A probabilistic fracture mechanics computer code for piping reliability analysis , 1992 .

[133]  Jinsuo Zhang,et al.  Review of the studies on fundamental issues in LBE corrosion , 2008 .

[134]  N W Brown,et al.  The secure, transportable, autonomous reactor (STAR): a small proliferation-resistant reactor system for developing countries , 1999 .

[135]  Asok Ray,et al.  Stochastic modeling of fatigue crack dynamics for on-line failure prognostics , 1996, IEEE Trans. Control. Syst. Technol..

[136]  Michael Pecht,et al.  A life consumption monitoring methodology for electronic systems , 2003 .

[137]  P. Cawley,et al.  Rapid, Long Range Inspection of Chemical Plant Pipework Using Guided Waves , 2001 .

[138]  Alexander V. Usynin,et al.  A Generic Prognostic Framework for Remaining Useful Life Prediction of Complex Engineering Systems , 2007 .

[139]  Jamie B. Coble,et al.  Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications , 2012 .

[140]  Ryan M. Meyer,et al.  A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants , 2012 .

[141]  Hong feng Wang Decision of Prognostics and Health management under Uncertainty , 2011 .

[142]  Anton Moisseytsev,et al.  SSTAR: The US lead-cooled fast reactor (LFR) , 2007 .

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

[144]  Kevan D. Weaver,et al.  Conceptual Design of a 500 MWe Traveling Wave Demonstration Reactor Plant , 2011 .

[145]  George F. Flanagan,et al.  Sodium fast reactor safety and licensing research plan. Volume II. , 2012 .

[146]  Lee M. Hively,et al.  Emerging Technologies in Instrumentation and Controls , 2003 .

[147]  Mario D. Carelli,et al.  The Encapsulated Nuclear Heat Source for Proliferation-Resistant Low-Waste Nuclear Energy , 2001 .

[148]  Il Soon Hwang,et al.  Fuel design study and optimization for PEACER development , 2007 .

[149]  Odile Gelineau,et al.  Selection of materials for sodium fast reactor steam generators , 2012 .

[150]  P. Jax,et al.  Acoustic emission inspections of nuclear components considering recent research programmes , 1989 .

[151]  Zheng Liu,et al.  Survey: State of the Art in NDE Data Fusion Techniques , 2007, IEEE Transactions on Instrumentation and Measurement.

[152]  D. Martin,et al.  A Supercritical Water-Cooled Small Modular Reactor , 2011 .

[153]  Michel Lecomte,et al.  ANTARES: The HTR/VHTR project at Framatome ANP , 2006 .

[154]  D. Thompson,et al.  Review of Progress in Quantitative Nondestructive Evaluation , 1982 .

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

[156]  R. Tryon,et al.  Material simulation-based electronic device prognosis , 2005, 2005 IEEE Aerospace Conference.

[157]  Yoichiro Shimazu,et al.  Optimization of flux distribution in a molten-salt reactor with a 2-region core for plutonium burning , 2008 .

[158]  Yoichiro Shimazu,et al.  Reactivity-Initiated-Accident Analysis without Scram of a Molten Salt Reactor , 2008 .

[159]  Bernhard R. Tittmann,et al.  ALUMINUM NITRIDE AS A HIGH TEMPERATURE TRANSDUCER , 2010 .

[160]  Ralph Moir,et al.  Liquid Fluoride Thorium Reactors: An old idea in nuclear power gets reexamined , 2010 .

[161]  D. C. Swanson,et al.  A general prognostic tracking algorithm for predictive maintenance , 2001, 2001 IEEE Aerospace Conference Proceedings (Cat. No.01TH8542).

[162]  Bhaskar Saha,et al.  Model Adaptation for Prognostics in a Particle Filtering Framework , 2011 .

[163]  M. Pecht,et al.  Prognostics and health management using physics-of-failure , 2008, 2008 Annual Reliability and Maintainability Symposium.

[164]  G. Coccoluto,et al.  Ti3SiC2 as a candidate material for lead cooled fast reactor , 2011 .

[165]  D.G. Senesky,et al.  Harsh Environment Silicon Carbide Sensors for Health and Performance Monitoring of Aerospace Systems: A Review , 2009, IEEE Sensors Journal.

[166]  Mark Schwabacher,et al.  A Survey of Data -Driven Prognostics , 2005 .

[167]  klausdieterborchardt European Economic and Social Committee , 2010 .

[168]  Jamie B. Coble,et al.  Adaptive Monitoring, Fault Detection and Diagnostics, and Prognostics System for the IRIS Nuclear Plant , 2010 .

[169]  Murray Wilford Rosenthal An Account of Oak Ridge National Laboratory's Thirteen Research Reactors , 2009 .

[170]  Abdollah A. Afjeh,et al.  Integrating Oil Debris and Vibration Gear Damage Detection Technologies Using Fuzzy Logic , 2004 .

[171]  Michael J. Roemer,et al.  Predicting remaining life by fusing the physics of failure modeling with diagnostics , 2004 .

[172]  C. B. Scruby,et al.  Some applications of laser ultrasound , 1989 .

[173]  D. A. Copinger,et al.  Fort Saint Vrain Gas Cooled Reactor Operational Experience , 2004 .

[174]  M. Rosenthal,et al.  Molten-Salt Reactors—History, Status, and Potential , 1970 .

[175]  Akira Tokuhiro,et al.  Status of Research and Development of the Lead-Alloy-Cooled Fast Reactor , 2003 .

[176]  Dirceu Spinelli,et al.  Creep properties of austenitic stainless-steel weld metals , 2001 .

[177]  Zheng Liu,et al.  Wavelet Neural Network Based Data Fusion for Improved Thickness Characterization , 2004 .

[178]  M.G. Pecht,et al.  Prognostics and health management of electronics , 2008, IEEE Transactions on Components and Packaging Technologies.

[179]  Faramarz Djavanroodi,et al.  Failure assessment of Nimonic 80A gas turbine blade , 2012 .

[180]  T. Schulenberg,et al.  Supercritical water-cooled reactor (SCWR) development through GIF collaboration , 2009 .

[181]  Zheng Liu,et al.  Data Fusion Method for the Optimal Mixing of Multi‐Frequency Eddy Current Signals , 2003 .

[182]  W. Chambers San Antonio, Texas , 1940 .

[183]  John C. Pearson,et al.  Neural Network Approach To Sensory Fusion , 1988, Defense, Security, and Sensing.

[184]  James R. Wolf Supercritical Water Reactor , 2011 .

[185]  Jamie B. Coble,et al.  Merging Data Sources to Predict Remaining Useful Life – An Automated Method to Identify Prognostic Parameters , 2010 .

[186]  Ryan M. Meyer,et al.  Materials Degradation and Detection (MD2): Deep Dive Final Report , 2013 .

[187]  Laure Martinelli,et al.  Oxidation of steels in liquid lead bismuth: Oxygen control to achieve efficient corrosion protection , 2011 .

[188]  Ryan M. Meyer,et al.  Lifecycle Prognostics Architecture for Selected High-Cost Active Components , 2011 .

[189]  M. Koppen No-Free-Lunch theorems and the diversity of algorithms , 2004 .

[190]  X. E. Gross NDT Data Fusion , 1997 .

[191]  Shujun Zhang,et al.  Piezoelectric Materials for High Temperature Sensors , 2011 .

[192]  Pradeep Ramuhalli,et al.  Combining multiple nondestructive inspection images with a generalized additive model , 2008 .

[193]  Han-Ok Kang,et al.  RESEARCH ACTIVITIES ON A SUPERCRITICAL PRESSURE WATER REACTOR IN KOREA , 2007 .

[194]  M. Abu-Khader Recent advances in nuclear power: A review , 2009 .

[195]  James E. Cahalan,et al.  Preliminary assessment of the BREST reactor design and fuel cycle concept. , 2000 .

[196]  Yoshiaki Oka,et al.  Startup Thermal Considerations for Supercritical-Pressure Light Water-Cooled Reactors , 2001 .

[197]  Andrea Muñoz Trallero C-14 Production in Lead-Cooled Reactors , 2010 .

[198]  C. J. Dale,et al.  Application of the proportional hazards model in the reliability field , 1985 .

[199]  B. G. Park,et al.  Partitioning and Transmutation of Spent Nuclear Fuel by PEACER , 2002 .

[200]  Jake K. Aggarwal,et al.  Physics-based integration of multiple sensing modalities for scene interpretation , 1997 .

[201]  F. H. Southworth,et al.  The Next Generation Nuclear Plant (NGNP) Project , 2003 .

[202]  Peter L. Andresen,et al.  Fundamental modeling of environmental cracking for improved design and lifetime evaluation in BWRs , 1994 .

[203]  Mongi A. Abidi,et al.  Data fusion in robotics and machine intelligence , 1992 .

[204]  Sz. Czifrus,et al.  The Simplified Supercritical Water-Cooled Reactor (SSCWR), a new SCWR design , 2010 .

[205]  Rodney Cannon Schmidt,et al.  Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety. , 2011 .

[206]  Dominique Hittner,et al.  High and very high temperature reactor research for multipurpose energy applications , 2011 .

[207]  Matthew R Denman,et al.  Sodium Fast Reactor Fuels and Materials: Research Needs. , 2011 .

[208]  Michael Rieth,et al.  Creep of the austenitic steel AISI 316 L(N). Experiments and models , 2004 .

[209]  Maurice Goursat,et al.  Subspace-Based Algorithms for Structural Identification, Damage Detection, and Sensor Data Fusion , 2007, EURASIP J. Adv. Signal Process..

[210]  Anindya Ghoshal,et al.  Technological assessment of high temperature sensing systems under extreme environment , 2012 .

[211]  Robert W. Schleicher,et al.  Configuring EM2 to Meet the Challenges of Economics, Waste Disposition and Non-Proliferation Confronting Nuclear Energy in the U.S. , 2012 .

[212]  Abdul Waris,et al.  Comparative Study on 233 U and Plutonium Utilization in Molten Salt Reactor , 2010 .

[213]  Vaclav Dostal,et al.  A supercritical carbon dioxide cycle for next generation nuclear reactors , 2004 .