Technical Needs for Prototypic Prognostic Technique Demonstration for Advanced Small Modular Reactor Passive Components
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Ryan M. Meyer | Jamie B. Coble | Leonard J. Bond | Pradeep Ramuhalli | Mark R. Mitchell | David W. Wootan | Evelyn H. Hirt | Eric J. Berglin | Charles H. Henager | L. Bond | C. Henager | P. Ramuhalli | J. Coble | R. Meyer | D. Wootan | E. Berglin | E. Hirt | M. R. Mitchell
[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 .