All Stories

  1. Technical analysis for optimum hydrogen production using nuclear–renewable hybrid energy system
  2. Classification of LOCA events in pressurized water reactors using neural networks
  3. Advances in neutron imaging for non-destructive testing: Developing techniques, challenges, and future directions
  4. Nuclear waste for hydrogen production: methods, advantages, and future perspectives
  5. Enhancing safety of nuclear power plant by human error detection and identification through AI techniques
  6. Nuclear safeguards: Technology, challenges, and future perspectives
  7. A comprehensive dosimetry analysis of barakah nuclear power plant: Integrating gaseous and liquid radionuclide dispersion across multiple units
  8. Improving anti-corrosion and mechanical properties of mild steel pipelines by using polyurea with nanoparticles
  9. MXenes: Innovative solutions for the removal of radionuclides from water - A review
  10. mechanical and thermal behavior of fiber-reinforced silica xerogel composites
  11. Enhancement in the safety and reliability of Pressurized Water reactors using Machine Learning approach
  12. A preliminary safety inspection methodology in the UAE using AIMS-PSA for risk assessment of APR1400 LOCA transients
  13. An investigation of the simulation response of GEM-based detector for the fast neutrons by employment of GEANT4 & MCNP MC codes
  14. Implications of using nanoparticles on the performance and safety of nuclear systems
  15. Utilizing MATLAB machine learning models to categorize transient events in a nuclear power plant using generic pressurized water reactor simulator
  16. A Methodology for Safety Inspection Analysis Based on Risk Insight and Defense-in-Depth Concept for APR1400 Nuclear Power Plant
  17. Investigation of mechanical and thermal behavior of fiber-reinforced silica aerogel composites
  18. Characterization of NaI(Tl) Scintillator Detectors in Gamma Spectroscopy Investigations
  19. Nucleotide detection mechanism and comparison based on low-dimensional materials: A review
  20. An Insight into the Effect of Sharp and Round Edges on the Flow Field-A CFD Simulation
  21. Operator Protection from Gamma Rays Using Ordinary Glass and Glass Doped with Nanoparticles
  22. Lattice Dynamics and Ab Initio Molecular Dynamics Study of Sio2-Tio2 and Sio2-Al2o3 Binary Slag Systems: Structural Physical and Electronic Properties Calculation by Density Functional Theory
  23. Study on EOPs for PORV-Break LOCA in Generic PWR Simulator
  24. Total Effective Dose Analysis in Case of LOCA for TMI-2 Nuclear Power Plant
  25. Nuclear design of an integrated small modular reactor based on the APR-1400 for RO desalination purposes
  26. Estimation of public exposure during normal operation of unit-1 Barakah Nuclear Power Plant using GALE and HOTSPOT
  27. Investigation of Loss of Feedwater (LOFW) Accident in the APR-1400 Using Fault Tree Analysis
  28. Comparison of different glass materials to protect the operators from gamma-rays in the PET using MCNP code
  29. Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software
  30. Editorial: Advances in Nuclear Power Engineering
  31. Computational analysis of high carbon steel for optimal design
  32. Direct Observation of Austenite and Pearlite Formation in Thermally Simulated Coarse Grain Heat-Affected Zone of Pearlite Railway Steel
  33. Neutronics design study of an advanced lead-cooled modular nuclear reactor (ALMANAR)
  34. Atomistic Simulations of Nanoindentation Response of Irradiation Defects in Iron
  35. Field-Induced Nonlinearities in Silicon Waveguides Embedded in Lateral p-n Junctions
  36. Effect of Grain Boundary on Diffusion of P in Alpha-Fe: A Molecular Dynamics Study
  37. An analytical method for the solution of two phase Stefan problem in cylindrical geometry
  38. Sensitivity analysis of APR-1400’s Reactor Protection System by using RiskSpectrum PSA
  39. Radioactivity investigation of water and aerosols in Sharjah, United Arab Emirates
  40. Classical molecular dynamics study for defect sink behavior in oxide dispersed strengthened alloys
  41. Molecular dynamics studies and irradiation effects in ODSS alloys
  42. Station black out concurrent with PORV failure using a Generic Pressurized Water Reactor simulator
  43. Analytical analysis of latent heat thermal energy storage model for solar thermal power plants
  44. Uncertainty reduction using multivariate reliability models
  45. Calculation and updating of Common Cause Failure unavailability by using alpha factor model
  46. A novel method for analytical solution of transient heat conduction and Stefan problem in cylindrical coordinate
  47. A Hybrid Approach for Reliability Analysis Based on Analytic Hierarchy Process and Bayesian Network
  48. Modeling of common cause failures (CCFs) by using beta factor parametric model
  49. Prioritization of Underlying Precursors in Nuclear Accidents
  50. Study on nuclear accident precursors using AHP and BBN, a case study of Fukushima accident
  51. Estimation of Surface Heat Flux and Surface Temperature during Inverse Heat Conduction under Varying Spray Parameters and Sample Initial Temperature
  52. Reliability analysis of nuclear I&C architecture using Bayesian networks
  53. A computer based living probabilistic safety assessment (LPSA) method for nuclear power plants
  54. Reliability Data Update Method (RDUM) based on living PSA for emergency diesel generator of Daya Bay nuclear power plant
  55. Quantitative and qualitative analysis of safety parameters in nuclear power plants
  56. Advancement in living probabilistic safety assessment to increase safety of nuclear power plants
  57. The unexpected and facile molybdenum mediated formation of tri- and tetracyclic pentathiepins from pyrazine-alkynes and sulfur
  58. Sensitivity Study on Availability of I&C Components Using Bayesian Network
  59. Reliability data update method for emergency diesel generator of Daya Bay Nuclear Power Plant
  60. A methodology for Living Probabilistic Safety Assessment (LPSA) based on Advanced Control Room Operator Support System (ACROSS)
  61. Role of Risk Manager for Online Risk Monitoring
  62. Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR)
  63. Study on the Evaluation and Simulation of Steady State Behavior and Reactor Safety Concept for Integral Pressurized Water Reactor
  64. Neutronics and Thermal Hydraulic Coupling Methods for the Nuclear Reactor Core
  65. Preliminary Assessment of Mean Steam Line Break Accident in an Integral Pressurized Water Reactor(IPWR)
  66. Reliability Data Update Method with Gamma Distribution
  67. Estimation of Failure Rate with the Help of Risk Monitors
  68. Loss of Feed Water Accident in an Integral Pressurized Water Reactor (IPWR)
  69. Normal Operational State Results of Integral Pressurized Water Reactor by Using Relap5/Mod3.4
  70. Calculation and Updating of Reliability Parameters in Probabilistic Safety Assessment
  71. A Methodology for Updating Living Probabilistic Safety Assessment
  72. A Review on Specific Features of Small and Medium Sized Nuclear Power Plants
  73. A Review: Advancement in Probabilistic Safety Assessment and Living Probabilistic Safety Assessment