All Stories

  1. Nuclear reactor cladding enhancement via DES electrodeposition: Electrochemical kinetics and surface architecture of Cr-coated Zr-4 claddings
  2. Probabilistic Failure Analysis of SiC‐CMC/Nb Fuel Claddings Under Loss‐Of‐Coolant Accident Conditions
  3. Critical roles of mass, spring, and damping ratios in nonlinear energy sink vortex-induced vibrational control: CFD & optimization
  4. Excess reactivity control using innovative burnable absorber configuration for a 24-month cycle APR-1400
  5. Advanced fuel performance analysis of multi-layered coated accident-tolerant fuel (ATF) cladding using a coupled multiphysics approach
  6. Performance Analysis of an Enhanced Cr-Coated Fuel Cladding System
  7. Impact of in-core fuel management on the radial peaking factor in the APR-1400 with accident-tolerance fuel cladding
  8. Unveiling the electrochemical excellence of sulfur and nitrogen-enriched 3D porous carbon nanofibers in high-performance energy storage devices
  9. Evaluation of high-temperature oxidation behaviour of ATF claddings during severe accidents in nuclear power plants
  10. Graphene-nuclear nexus: a critical review
  11. Thermomechanical analysis of SiC-based duplex claddings with varying thickness ratio for accident-tolerant nuclear fuel systems
  12. Correction: Alrwashdeh, M.; Alameri, S.A. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core. Energies 2022, 15, 8008
  13. Effectiveness re-evaluation on the intentional primary system depressurization during Zion-like Westinghouse PWR station blackout considering pressure dependence of radionuclides release
  14. Engineering the growth and electrochemical assessments of phosphorous-doped nitrogen-based carbon nanofibers with 3D-interconnected weaving network structure for high-energy symmetric supercapacitors
  15. Unveiling the redox electrochemical kinetics of interconnected wrinkled microspheres of binary Cu2-xSe/Ni1-xSe as battery-type electrode for advanced supercapatteries
  16. Correction: A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design
  17. Electrochemical reduction of gaseous nitric oxide into ammonia: a review
  18. Part Strength Control Element Assemblies Effectiveness in APR1400 Reactivity Management During Transient Operation
  19. Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400
  20. The effects of cladding thermo-physical and thermo-chemical properties on the coping time during a PWR unmitigated LB-LOCA
  21. A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design
  22. Thermal analysis of baffle jetting in fuel rod assembly
  23. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core
  24. Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions
  25. SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis
  26. Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis
  27. Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor
  28. Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly
  29. CONSOLIDATION OF REACTOR PHYSICS EDUCATION – THE KHALIFA UNIVERSITY STUDENT FIELD TRIPS CASE STUDY
  30. Overall efficiency analysis of an innovative load-following nuclear power plant-thermal energy storage coupled cycle
  31. Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors
  32. Prismatic-core advanced high temperature reactor and thermal energy storage coupled system – A preliminary design
  33. Emerging areas of nuclear power applications
  34. Evaluation review of the 250Cf neutron cross section
  35. Harmonizing nuclear and renewable energy: Case studies
  36. Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method
  37. Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
  38. New monitoring procedure of axial xenon oscillation in large pressurized water reactors
  39. Effect of Thermal Energy Storage Integration on Overall Nuclear Power Plant Efficiency
  40. Homogenization of TRISO Fuel Using Reactivity Equivalent Physical Transformation Method