Enrico Zio

Articles in Scholarly Journals [Incomplete List]

  1. Bootstrap and Order Statistics for Quantifying Thermal-Hydraulic Code Uncertainties in the Estimation of Safety Margins
    Science and Technology of Nuclear Installations, vol. 2008, Article ID 340164, 9 pages, 2008
  2. Validation of Infinite Impulse Response Multilayer Perceptron for Modelling Nuclear Dynamics
    Science and Technology of Nuclear Installations, vol. 2008, Article ID 681890, 10 pages, 2008
  3. From complexity science to reliability efficiency: a new way of looking at complex network systems and critical infrastructures
    International Journal of Critical Infrastructures, vol. 3, no. 3/4, p. 488, 2007
  4. Human Reliability Analysis by Fuzzy "CREAM"
    Risk Analysis, vol. 27, no. 1, pp. 137–154, 2007
  5. Simulating the dynamics of the neutron flux in a nuclear reactor by locally recurrent neural networks
    Annals of Nuclear Energy, vol. 34, no. 6, pp. 483–495, 2007
  6. Recognizing signal trends on-line by a fuzzy-logic-based methodology optimized via genetic algorithms
    Engineering Applications of Artificial Intelligence, vol. 20, no. 6, pp. 831–849, 2007
  7. A support vector machine integrated system for the classification of operation anomalies in nuclear components and systems
    Reliability Engineering & System Safety, vol. 92, no. 5, pp. 593–600, 2007
  8. A Monte Carlo simulation approach to the availability assessment of multi-state systems with operational dependencies
    Reliability Engineering & System Safety, vol. 92, no. 7, pp. 871–882, 2007
  9. Importance measures-based prioritization for improving the performance of multi-state systems: application to the railway industry
    Reliability Engineering & System Safety, vol. 92, no. 10, pp. 1303–1314, 2007
  10. Importance measures and genetic algorithms for designing a risk-informed optimally balanced system
    Reliability Engineering & System Safety, vol. 92, no. 10, pp. 1435–1447, 2007
  11. Accounting for components interactions in the differential importance measure
    Reliability Engineering & System Safety, 2006
  12. Basics of genetic algorithms optimization for RAMS applications
    Reliability Engineering & System Safety, vol. 91, no. 9, pp. 977–991, 2006
  13. ESREL 2005—Post-conference publication
    International Journal of Pressure Vessels and Piping, vol. 83, no. 4, pp. 227–229, 2006
  14. Assessment of the availability of an offshore installation by Monte Carlo simulation
    International Journal of Pressure Vessels and Piping, vol. 83, no. 4, pp. 312–320, 2006
  15. Risk-informed optimisation of railway tracks inspection and maintenance procedures
    Reliability Engineering & System Safety, vol. 91, no. 1, pp. 20–35, 2006
  16. A combination of Monte Carlo simulation and cellular automata for computing the availability of complex network systems
    Reliability Engineering & System Safety, vol. 91, no. 2, pp. 181–190, 2006
  17. Neuro-fuzzy pattern classification for fault diagnosis in nuclear components
    Annals of Nuclear Energy, vol. 33, no. 5, pp. 415–426, 2006
  18. Quantitative developments in the cognitive reliability and error analysis method (CREAM) for the assessment of human performance?
    Annals of Nuclear Energy, vol. 33, no. 10, pp. 894–910, 2006
  19. A Study of the Bootstrap Method for Estimating the Accuracy of Artificial Neural Networks in Predicting Nuclear Transient Processes
    IEEE Transactions on Nuclear Science, vol. 53, no. 3, pp. 1460–1478, 2006
  20. Selecting Features for Nuclear Transients Classification by Means of Genetic Algorithms
    IEEE Transactions on Nuclear Science, vol. 53, no. 3, pp. 1479–1493, 2006
  21. Optimal Design of Reliable Network Systems in Presence of Uncertainty
    IEEE Transactions on Reliability, vol. 54, no. 2, pp. 243–253, 2005
  22. Genetic algorithm optimization of a model-free fuzzy control system
    Annals of Nuclear Energy, vol. 32, no. 7, pp. 712–728, 2005
  23. Identification of nuclear transients via optimized fuzzy clustering
    Annals of Nuclear Energy, vol. 32, no. 10, pp. 1068–1080, 2005
  24. An extended classifiability index for feature selection in nuclear transients
    Annals of Nuclear Energy, vol. 32, no. 15, pp. 1632–1649, 2005
  25. First-order differential sensitivity analysis of a nuclear safety system by Monte Carlo simulation
    Reliability Engineering & System Safety, vol. 90, no. 2-3, pp. 162–168, 2005
  26. Multiobjective spare part allocation by means of genetic algorithms and Monte Carlo simulation
    Reliability Engineering & System Safety, vol. 87, no. 3, pp. 325–335, 2005
  27. Solving advanced network reliability problems by means of cellular automata and Monte Carlo sampling
    Reliability Engineering & System Safety, vol. 89, no. 2, pp. 219–226, 2005
  28. Evolutionary fuzzy clustering for the Classification of transients in nuclear components
    Progress in Nuclear Energy, vol. 46, no. 3-4, pp. 282–296, 2005
  29. Monte Carlo estimation of the differential importance measure: application to the protection system of a nuclear reactor
    Reliability Engineering & System Safety, vol. 86, no. 1, pp. 11–24, 2004
  30. Estimation of the importance measures of multi-state elements by Monte Carlo simulation
    Reliability Engineering & System Safety, vol. 86, no. 3, pp. 191–204, 2004
  31. Using genetic algorithms for calibrating simplified models of nuclear reactor dynamics
    Annals of Nuclear Energy, vol. 31, no. 11, pp. 1219–1250, 2004
  32. A soft-computing based classification procedure for the identification of transients in the steam generator of a pressurized water reactor
    Annals of Nuclear Energy, vol. 31, no. 13, pp. 1429–1446, 2004
  33. A fuzzy modeling approach to the identification of transients in nuclear components
    Annals of Nuclear Energy, vol. 31, no. 18, pp. 2093–2112, 2004
  34. Model identification by neuro-fuzzy techniques: Predicting the water level in a steam generator of a PWR
    Progress in Nuclear Energy, vol. 44, no. 3, pp. 237–252, 2004
  35. Optimal Reliability/Availability of Uncertain Systems via Multi-Objective Genetic Algorithms
    IEEE Transactions on Reliability, vol. 53, no. 3, pp. 424–434, 2004
  36. A multiobjective genetic algorithm approach to the optimization of the technical specifications of a nuclear safety system
    Reliability Engineering & System Safety, vol. 84, no. 1, pp. 87–99, 2004
  37. International Journal of Reliability, Quality and Safety Engineering, vol. 10, no. 3, p. 289, 2003
  38. Fuzzy logic for signal prediction in nuclear systems
    Progress in Nuclear Energy, vol. 43, no. 1-4, pp. 373–380, 2003
  39. Power density axial oscillations induced by Xenon dynamics: Parameter identification via genetic algorithms
    Progress in Nuclear Energy, vol. 43, no. 1-4, pp. 365–372, 2003
  40. Modeling the effects of the engineered barriers of a radioactive waste repository by Monte Carlo simulation
    Annals of Nuclear Energy, vol. 30, no. 4, pp. 473–496, 2003
  41. Model-free fuzzy tracking control of a nuclear reactor
    Annals of Nuclear Energy, vol. 30, no. 9, pp. 953–981, 2003
  42. Model parameters estimation and sensitivity by genetic algorithms
    Annals of Nuclear Energy, vol. 30, no. 14, pp. 1437–1456, 2003
  43. Sensitivity analysis and fuzzy modelling for passive systems reliability assessment
    Annals of Nuclear Energy, vol. 31, no. 3, pp. 277–301, 2003
  44. Monte Carlo simulation of contaminant release from a radioactive waste deposit
    Mathematics and Computers in Simulation, vol. 62, no. 3-6, pp. 421–430, 2003
  45. Designing optimal degradation tests via multi-objective genetic algorithms
    Reliability Engineering & System Safety, vol. 79, no. 1, pp. 87–94, 2003
  46. Variance decomposition-based sensitivity analysis via neural networks
    Reliability Engineering & System Safety, vol. 79, no. 2, pp. 229–238, 2003
  47. Monte Carlo simulation analysis of the effects of different system performance levels on the importance of multi-state components
    Reliability Engineering & System Safety, vol. 82, no. 1, pp. 63–73, 2003
  48. Generalised importance measures for multi-state elements based on performance level restrictions
    Reliability Engineering & System Safety, vol. 82, no. 3, pp. 287–298, 2003
  49. Fuzzy identification of transients in nuclear power plants
    Nuclear Engineering and Design, vol. 225, no. 2-3, pp. 285–294, 2003
  50. The analytic hierarchy process as a systematic approach to the identification of important parameters for the reliability assessment of passive systems
    Nuclear Engineering and Design, vol. 226, no. 3, pp. 311–336, 2003
  51. Biased Monte Carlo unavailability analysis for systems with time-dependent failure rates
    Reliability Engineering & System Safety, vol. 76, no. 1, pp. 11–17, 2002
  52. Simulation modelling of repairable multi-component deteriorating systems for 'on condition' maintenance optimisation
    Reliability Engineering & System Safety, vol. 76, no. 3, pp. 255–264, 2002
  53. Condition[hyphen]based maintenance optimization by means of genetic algorithms and Monte Carlo simulation
    Reliability Engineering & System Safety, vol. 77, no. 2, pp. 151–165, 2002
  54. Selected papers from ESREL 2001
    Reliability Engineering & System Safety, vol. 77, no. 3, pp. 211–215, 2002
  55. Procedures of Monte Carlo transport simulation for applications in system engineering
    Reliability Engineering & System Safety, vol. 77, no. 3, pp. 217–228, 2002
  56. Solving the inverse problem of parameter estimation by genetic algorithms: the case of a groundwater contaminant transport model
    Annals of Nuclear Energy, vol. 29, no. 8, pp. 967–981, 2002
  57. Groundwater contaminant transport in presence of colloids I. A stochastic nonlinear model and parameter identification
    Annals of Nuclear Energy, vol. 28, no. 8, pp. 777–803, 2001
  58. Groundwater contaminant transport in presence of colloids II: sensitivity and uncertainty analysis on literature case studies
    Annals of Nuclear Energy, vol. 28, no. 18, pp. 1799–1807, 2001
  59. Effects of model variability on the safeguard analysis of gamma-contaminated truck loads
    Mathematics and Computers in Simulation, vol. 55, no. 1-3, pp. 159–166, 2001
  60. Looking at Monte Carlo simulation for describing nonlinear sorption in groundwater contaminant transport
    Mathematics and Computers in Simulation, vol. 55, no. 1-3, pp. 167–176, 2001
  61. Multiobjective optimization by genetic algorithms: application to safety systems
    Reliability Engineering & System Safety, vol. 72, no. 1, pp. 59–74, 2001
  62. Optimizing maintenance and repair policies via a combination of genetic algorithms and Monte Carlo simulation
    Reliability Engineering & System Safety, vol. 68, no. 1, pp. 69–83, 2000
  63. System unavailability calculations in biased Monte Carlo simulation: a possible pitfall
    Annals of Nuclear Energy, vol. 27, no. 17, pp. 1577–1588, 2000
  64. Monte Carlo biasing in reliability calculations with deterministic repair times
    Annals of Nuclear Energy, vol. 27, no. 7, pp. 639–648, 2000
  65. A Monte Carlo methodological approach to plant availability modeling with maintenance, aging and obsolescence
    Reliability Engineering & System Safety, vol. 67, no. 1, pp. 61–73, 2000
  66. Genetic algorithms and Monte Carlo simulation for optimal plant design
    Reliability Engineering & System Safety, vol. 68, no. 1, pp. 29–38, 2000
  67. The impact of the operating environment on the design of redundant configurations
    Reliability Engineering & System Safety, vol. 63, no. 2, pp. 155–160, 1999
  68. Neural network approach to sensitivity and uncertainty analysis
    Reliability Engineering & System Safety, vol. 64, no. 1, pp. 59–71, 1999
  69. A comparison between the advection-dispersion and the Kolmogorov-Dmitriev model for groundwater contaminant transport
    Annals of Nuclear Energy, vol. 26, no. 12, pp. 1083–1096, 1999
  70. Developing utility functions for environmental decision making
    Progress in Nuclear Energy, vol. 34, no. 4, pp. 387–411, 1999
  71. Dynamic simulation of a steam generator by neural networks
    Nuclear Engineering and Design, vol. 187, no. 2, pp. 197–213, 1999
  72. Sensitivity and uncertainty analysis within a methodology for evaluating environmental restoration technologies
    Computer Physics Communications, vol. 117, no. 1-2, pp. 1–10, 1999
  73. Contaminant transport in bidimensional porous media via biased Monte Carlo simulation
    Annals of Nuclear Energy, vol. 25, no. 16, pp. 1301–1316, 1998
  74. The cell-to-boundary method in the frame of memorization-based Monte Carlo algorithms. A new computational improvement in dynamic reliability
    Mathematics and Computers in Simulation, vol. 47, no. 2-5, pp. 347–360, 1998
  75. Monte Carlo simulation of the effects of human intrusion on groundwater contaminant transport
    Mathematics and Computers in Simulation, vol. 47, no. 2-5, pp. 361–369, 1998
  76. A concept paper on dynamic reliability via Monte Carlo simulation
    Mathematics and Computers in Simulation, vol. 47, no. 2-5, pp. 371–382, 1998
  77. Accounting for expert-to-expert variability: A potential source of bias in performance assessments of high-level radioactive waste repositories
    Annals of Nuclear Energy, vol. 24, no. 10, pp. 751–762, 1997
  78. Modelling the transport of contaminants in groundwater as a branching stochastic process
    Annals of Nuclear Energy, vol. 24, no. 8, pp. 625–644, 1997
  79. Approaching the inverse problem of parameter estimation in groundwater models by means of artificial neural networks
    Progress in Nuclear Energy, vol. 31, no. 3, pp. 303–315, 1997
  80. Monte Carlo approach to PSA for dynamic process systems
    Reliability Engineering & System Safety, vol. 52, no. 3, pp. 227–241, 1996
  81. On the use of the analytic hierarchy process in the aggregation of expert judgments
    Reliability Engineering & System Safety, vol. 53, no. 2, pp. 127–138, 1996
  82. Two methods for the structured assessment of model uncertainty by experts in performance assessments of radioactive waste repositories
    Reliability Engineering & System Safety, vol. 54, no. 2-3, pp. 225–241, 1996
  83. Biasing the transition probabilities in direct Monte Carlo
    Reliability Engineering & System Safety, vol. 47, no. 1, pp. 59–63, 1995
  84. The cell-to-boundary method in Monte Carlo-based dynamic PSA
    Reliability Engineering & System Safety, vol. 48, no. 3, pp. 199–204, 1995
  85. Approaching system evolution in dynamic PSA by neural networks
    Reliability Engineering & System Safety, vol. 49, no. 1, pp. 91–99, 1995
  86. Approximate physical modelling in dynamic PSA using artificial neural networks
    Reliability Engineering & System Safety, vol. 45, no. 1-2, pp. 47–56, 1994
  87. Identification of a line break by a neural network methodology
    Annals of Nuclear Energy, vol. 21, no. 4, pp. 249–258, 1994
  88. Nonlinear Monte Carlo reliability analysis with biasing towards top event
    Reliability Engineering & System Safety, vol. 40, no. 1, pp. 31–42, 1993