Year |
Citation |
Score |
2020 |
Singh V, Wheeler AM, Upadhyaya BR, Chvála O, Greenwood MS. Plant-level dynamic modeling of a commercial-scale molten salt reactor system Nuclear Engineering and Design. 360: 110457. DOI: 10.1016/J.Nucengdes.2019.110457 |
0.365 |
|
2019 |
Wang H, Peng MJ, Wesley Hines J, Zheng GY, Liu YK, Upadhyaya BR. A hybrid fault diagnosis methodology with support vector machine and improved particle swarm optimization for nuclear power plants. Isa Transactions. PMID 31171304 DOI: 10.1016/J.Isatra.2019.05.016 |
0.368 |
|
2018 |
Singh V, Lish MR, Wheeler AM, Chvála O, Upadhyaya BR. Dynamic Modeling and Performance Analysis of a Two-Fluid Molten-Salt Breeder Reactor System Nuclear Technology. 202: 15-38. DOI: 10.1080/00295450.2017.1416879 |
0.321 |
|
2018 |
Singh V, Wheeler AM, Lish MR, Chvála O, Upadhyaya BR. Nonlinear dynamic model of Molten-Salt Reactor Experiment – Validation and operational analysis Annals of Nuclear Energy. 113: 177-193. DOI: 10.1016/J.Anucene.2017.10.047 |
0.352 |
|
2017 |
Wood RT, Upadhyaya BR, Floyd DC. An autonomous control framework for advanced reactors Nuclear Engineering and Technology. 49: 896-904. DOI: 10.1016/J.Net.2017.07.001 |
0.407 |
|
2017 |
Singh V, Lish MR, Chvála O, Upadhyaya BR. Dynamics and control of molten-salt breeder reactor Nuclear Engineering and Technology. 49: 887-895. DOI: 10.1016/J.Net.2017.06.003 |
0.343 |
|
2017 |
Welz Z, Coble J, Upadhyaya B, Hines W. Maintenance-based prognostics of nuclear plant equipment for long-term operation Nuclear Engineering and Technology. 49: 914-919. DOI: 10.1016/J.Net.2017.06.001 |
0.318 |
|
2015 |
Upadhyaya BR, Lish MR, Wesley Hines J, Tarver RA. Instrumentation and control strategies for an integral pressurized water reactor Nuclear Engineering and Technology. 47: 148-156. DOI: 10.1016/J.Net.2015.01.001 |
0.377 |
|
2015 |
Lish MR, Upadhyaya BR, Hines JW. Development of I2S-LWR instrumentation systems Annals of Nuclear Energy. DOI: 10.1016/J.Anucene.2016.06.029 |
0.323 |
|
2014 |
Sun J, Liao H, Upadhyaya BR. A robust functional-data-analysis method for data recovery in multichannel sensor systems. Ieee Transactions On Cybernetics. 44: 1420-31. PMID 25051452 DOI: 10.1109/Tcyb.2013.2285876 |
0.397 |
|
2014 |
Perillo SR, Upadhyaya BR, Hines JW. Faulty measurement substitution and control reconfiguration by using a multivariate flow control loop. Isa Transactions. 53: 568-77. PMID 24411932 DOI: 10.1016/J.Isatra.2013.12.013 |
0.412 |
|
2014 |
Upadhyaya BR, Mehta C, Bayram D. Integration of time series modeling and wavelet transform for monitoring nuclear plant sensors Ieee Transactions On Nuclear Science. 61: 2628-2635. DOI: 10.1109/Tns.2014.2341035 |
0.408 |
|
2012 |
Li F, Upadhyaya BR, Perillo SRP. Fault diagnosis of helical coil steam generator systems of an integral pressurized water reactor using optimal sensor selection Ieee Transactions On Nuclear Science. 59: 403-410. DOI: 10.1109/Tns.2012.2185509 |
0.383 |
|
2011 |
Li F, Upadhyaya BR. Design of Sensor Placement for an Integral Pressurized Water Reactor Using Fault Diagnostic Observability and Reliability Criteria Nuclear Technology. 173: 17-25. DOI: 10.13182/Nt11-A11480 |
0.354 |
|
2011 |
Perillo SRP, Upadhyaya BR, Li F. Control and instrumentation strategies for multi-modular integral nuclear reactor systems Ieee Transactions On Nuclear Science. 58: 2442-2451. DOI: 10.1109/Tns.2011.2160969 |
0.377 |
|
2011 |
Hines JW, Coble J, Upadhyaya B. Application of monitoring and prognostics to small modular reactors 2011 Future of Instrumentation International Workshop, Fiiw 2011 - Proceedings. 99-102. DOI: 10.1109/FIIW.2011.6476808 |
0.31 |
|
2009 |
Li F, Upadhyaya BR, Coffey LA. Model-based monitoring and fault diagnosis of fossil power plant process units using Group Method of Data Handling. Isa Transactions. 48: 213-9. PMID 19084227 DOI: 10.1016/J.Isatra.2008.10.014 |
0.407 |
|
2009 |
Upadhyaya BR, Perillo SRP, Xu X, Li F. Advanced control design, optimal sensor placement, and technology demonstration for small and medium nuclear power reactors International Conference On Nuclear Engineering, Proceedings, Icone. 5: 763-773. DOI: 10.1115/ICONE17-75343 |
0.354 |
|
2009 |
Ayaz E, Ztrk A, Seker S, Upadhyaya BR. Fault detection based on continuous wavelet transform and sensor fusion in electric motors Compel - the International Journal For Computation and Mathematics in Electrical and Electronic Engineering. 28: 454-470. DOI: 10.1108/03321640910929326 |
0.371 |
|
2008 |
Lopez LANM, Ting DKS, Upadhyaya BR. Removing Eddy-Current probe wobble noise from steam generator tubes testing using Wavelet Transform Progress in Nuclear Energy. 50: 828-835. DOI: 10.1016/J.Pnucene.2007.07.008 |
0.335 |
|
2008 |
Carneiro ALG, Silva AAd, Upadhyaya BR. Incipient fault detection of motor-operated valves using wavelet transform analysis Nuclear Engineering and Design. 238: 2453-2459. DOI: 10.1016/J.Nucengdes.2008.03.013 |
0.35 |
|
2007 |
Na MG, Upadhyaya BR. Development Of A Reconfigurable Control For An Sp-100 Space Reactor Nuclear Engineering and Technology. 39: 63-74. DOI: 10.5516/Net.2007.39.1.063 |
0.34 |
|
2006 |
Zhao K, Upadhyaya BR, Wood RT. Robust Dynamic Sensor Fault Detection and Isolation of Helical Coil Steam Generator Systems Using a Subspace Identification Technique Nuclear Technology. 153: 326-340. DOI: 10.13182/Nt06-A3711 |
0.429 |
|
2006 |
Na MG, Upadhyaya BR, Xu X, Hwang IJ. Design of a model predictive power controller for an SP-100 space reactor Nuclear Science and Engineering. 154: 353-366. DOI: 10.13182/Nse06-A2638 |
0.362 |
|
2006 |
Na MG, Upadhyaya BR. Model predictive control of an SP-100 space reactor using support vector regression and genetic optimization Ieee Transactions On Nuclear Science. 53: 2318-2327. DOI: 10.1109/Tns.2006.876517 |
0.343 |
|
2006 |
Na MG, Upadhyaya BR. Application of model predictive control strategy based on fuzzy identification to an SP-100 space reactor Annals of Nuclear Energy. 33: 1467-1478. DOI: 10.1016/J.Anucene.2006.09.011 |
0.354 |
|
2005 |
Goncalves IMM, Ting DKS, Ferreira PB, Upadhyaya BR. Monitoring an Experimental Reactor Using the Group Method of Data Handling Approach Nuclear Technology. 149: 101-109. DOI: 10.13182/Nt05-A3582 |
0.361 |
|
2005 |
Lu B, Upadhyaya BR, Perez RB. Structural integrity monitoring of steam generator tubing using transient acoustic signal analysis Ieee Transactions On Nuclear Science. 52: 484-493. DOI: 10.1109/Tns.2004.843121 |
0.554 |
|
2005 |
Zhao K, Upadhyaya BR. Adaptive fuzzy inference causal graph approach to fault detection and isolation of field devices in nuclear power plants Progress in Nuclear Energy. 46: 226-240. DOI: 10.1016/J.Pnucene.2005.03.006 |
0.377 |
|
2005 |
Lu B, Upadhyaya BR. Monitoring and fault diagnosis of the steam generator system of a nuclear power plant using data-driven modeling and residual space analysis Annals of Nuclear Energy. 32: 897-912. DOI: 10.1016/J.Anucene.2005.02.003 |
0.379 |
|
2004 |
De Mesquita RN, Ting DKS, Cabral ELL, Upadhyaya BR. Classification of Steam Generator Tube Defects for Real-Time Applications Using Eddy Current Test Data and Self-Organizing Maps Real-Time Systems. 27: 49-70. DOI: 10.1023/B:Time.0000019126.26053.23 |
0.373 |
|
2003 |
Na MG, Sim YR, Park KH, Lee SM, Jung DW, Shin SH, Upadhyaya BR, Zhao K, Lu B. Sensor monitoring using a fuzzy neural network with an automatic structure constructor Ieee Transactions On Nuclear Science. 50: 241-250. DOI: 10.1109/Tns.2003.809471 |
0.553 |
|
2003 |
Upadhyaya BR, Zhao K, Lu B. Fault monitoring of nuclear power plant sensors and field devices Progress in Nuclear Energy. 43: 337-342. DOI: 10.1016/S0149-1970(03)00046-5 |
0.435 |
|
2001 |
Kaistha N, Upadhyaya BR. Incipient fault detection and isolation of field devices in nuclear power systems using principal component analysis Nuclear Technology. 136: 221-230. DOI: 10.13182/Nt01-A3240 |
0.358 |
|
2001 |
Upadhyaya BR, Erbay AS. Component diagnosis and life span estimation for optimal replacement Energy Engineering: Journal of the Association of Energy Engineering. 98: 47-58. DOI: 10.1092/Eh1N-Lbl5-N0Ct-Ewu8 |
0.361 |
|
1999 |
Kavaklioglu K, Upadhyaya BR. Optimal fuzzy control design using simulated annealing and application to feedwater heater control Nuclear Technology. 125: 70-84. DOI: 10.13182/Nt99-A2933 |
0.337 |
|
1999 |
Upadhyaya BR, Yan W, Behravesh MM, Henry G. Development of a diagnostic expert system for eddy current data analysis using applied artificial intelligence methods Nuclear Engineering and Design. 193: 1-11. DOI: 10.1016/S0029-5493(99)00162-4 |
0.34 |
|
1998 |
Na MG, Upadhyaya BR, Choi JI. Adaptive Control for Axial Power Distribution in Nuclear Reactors Nuclear Science and Engineering. 129: 283-293. DOI: 10.13182/Nse98-A1982 |
0.366 |
|
1997 |
Erbay AS, Upadhyaya BR. A Personal Computer-Based On-Line Signal Validation System for Nuclear Power Plants Nuclear Technology. 119: 63-75. DOI: 10.13182/Nt77-A35395 |
0.415 |
|
1996 |
Yan W, Upadhyaya BR. An integrated signal processing and neural networks system for steam generator tubing diagnostics using eddy current inspection Annals of Nuclear Energy. 23: 813-825. DOI: 10.1016/0306-4549(95)00060-7 |
0.336 |
|
1994 |
Kavaklioglu K, Upadhyaya BR. Monitoring Feedwater Flow Rate and Component Thermal Performance of Pressurized Water Reactors by Means of Artificial Neural Networks Nuclear Technology. 107: 112-123. DOI: 10.13182/Nt94-A35003 |
0.367 |
|
1994 |
Holbert KE, Upadhyaya BR. Empirical process modeling technique for signal validation Annals of Nuclear Energy. 21: 387-403. DOI: 10.1016/0306-4549(94)90040-X |
0.412 |
|
1993 |
Liu Y, Upadhyaya BR, Naghedolfeizi M. Chemometric Data Analysis Using Artificial Neural Networks Applied Spectroscopy. 47: 12-23. DOI: 10.1366/0003702934048406 |
0.322 |
|
1992 |
Upadhyaya BR, Eryurek E. Application of Neural Networks for Sensor Validation and Plant Monitoring Nuclear Technology. 97: 170-176. DOI: 10.13182/Nt92-A34613 |
0.368 |
|
1991 |
Berkan RC, Upadhyaya BR, Tsoukalas LH, Kisner RA. Reconstructive inverse dynamics control and application to xenon-induced power oscillations in pressurized water reactors Nuclear Science and Engineering. 109: 188-199. DOI: 10.13182/Nse91-A28517 |
0.373 |
|
1991 |
Berkan RC, Upadhyaya BR, Tsoukalas LH, Kisner RA, Bywater RL. Advanced Automation Concepts for Large-Scale Systems Ieee Control Systems. 11: 4-12. DOI: 10.1109/37.92985 |
0.399 |
|
1990 |
Holbert KE, Upadhyaya BR. An integrated signal validation system for nuclear power plants Nuclear Technology. 92: 411-427. DOI: 10.13182/Nt90-A16242 |
0.411 |
|
1990 |
Eryurek E, Upadhyaya BR. Sensor validation for power plants using adaptive backpropagation neural network Ieee Transactions On Nuclear Science. 37: 1040-1047. DOI: 10.1109/23.106752 |
0.381 |
|
1988 |
Hashemian HM, Thie JA, Upadhyaya BR. Reactor sensor surveillance using noise analysis Nuclear Science and Engineering. 98: 96-102. DOI: 10.13182/Nse88-A28489 |
0.334 |
|
1988 |
Hashemian HM, Thie JA, Upadhyaya BR, Holbert KE. Sensor response time monitoring using noise analysis Progress in Nuclear Energy. 21: 583-592. DOI: 10.1016/0149-1970(88)90080-7 |
0.389 |
|
1988 |
Glöckler O, Upadhyaya BR. Results and interpretation of multivariate autoregressive analysis applied to the loft reactor process noise data Progress in Nuclear Energy. 21: 447-456. DOI: 10.1016/0149-1970(88)90062-5 |
0.461 |
|
1988 |
Upadhyaya BR, Shieh DJ, Sweeney FJ, Glöcker O. Analysis of in-core dynamics in pressurized water reactors with application to parameter monitoring Progress in Nuclear Energy. 21: 261-269. DOI: 10.1016/0149-1970(88)90043-1 |
0.331 |
|
1987 |
Shieh DJ, Upadhyaya BR, Sweeney FJ. Application of noise analysis technique for monitoring the moderator temperature coefficient of reactivity in pressurized water reactors Nuclear Science and Engineering. 95: 14-21. DOI: 10.13182/Nse87-A20429 |
0.355 |
|
1986 |
Shieh D, Upadhyaya BR. Stochastic estimation approach for the evaluation of thermal-hydraulic parameters in pressurized water reactors Nuclear Technology. 73: 19-29. DOI: 10.13182/Nt86-A16198 |
0.35 |
|
1985 |
Sweeney FJ, Upadhyaya BR, Shieh DJ. In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise Progress in Nuclear Energy. 15: 201-208. DOI: 10.1016/0149-1970(85)90041-1 |
0.355 |
|
1985 |
Sweeney FJ, Upadhyaya BR, Shieh DJ. In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise Nuclear Engineering and Design. 89: 101-106. DOI: 10.1016/0029-5493(85)90146-3 |
0.355 |
|
1984 |
Upadhyaya BR, Skorska M. Sensor fault analysis using decision theory and data-driven modeling of pressurized water reactor subsystems Nuclear Technology. 64: 70-77. DOI: 10.13182/Nt84-A33327 |
0.467 |
|
1982 |
Upadhyaya BR, March-Leuba J, Fry DN, Kitamura M. Application of noise analyses methods to monitor stability of boiling water reactors Progress in Nuclear Energy. 9: 619-630. DOI: 10.1016/0149-1970(82)90081-6 |
0.376 |
|
1980 |
Upadhyaya BR, Kitamura M, Kerlin TW. Multivariate signal analysis algorithms for process monitoring and parameter estimation in nuclear reactors Annals of Nuclear Energy. 7: 1-11. DOI: 10.1016/0306-4549(80)90002-X |
0.416 |
|
1979 |
Upadhyaya BR. Spectral domain estimation of autoregressive moving-average models using shuttle iterative methods Computers & Electrical Engineering. 6: 163-173. DOI: 10.1016/0045-7906(79)90005-3 |
0.369 |
|
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