Dr. Muhammad Naweed | Solid Mechanics | Best Researcher Award
Pakistan Institute of Engineering & Applied Sciences (PIEAS) | Pakistan
Dr. Muhammad Naweed is a distinguished mechanical and nuclear engineer whose research bridges theoretical modeling with applied engineering solutions. He earned his doctorate from the Pakistan Institute of Engineering and Applied Sciences (PIEAS), where his work focused on fracture mechanics analysis and design optimization of Pressurized Water Reactor (PWR) pressure vessel components. His scholarly efforts revolve around enhancing the structural reliability and operational safety of nuclear systems using advanced computational techniques. Dr. Naweed has contributed to several international journals of high repute, including Nuclear Engineering and Design, Theoretical and Applied Fracture Mechanics, and Annals of Nuclear Energy, where his studies address challenges such as crack propagation, thermal shock resistance, and stress distribution in nuclear pressure vessels. His research demonstrates a consistent application of finite element analysis (FEA) and computational fluid dynamics (CFD) in assessing material performance under complex loading conditions. With 5 Scopus-indexed publications, over 18 citations, and an h-index of 3, he has established a credible academic presence in the domains of fracture mechanics and nuclear component analysis. Dr. Naweed’s ability to translate complex theoretical frameworks into practical engineering methodologies underscores his contribution to advancing nuclear safety and mechanical design optimization. His innovative work exemplifies excellence in engineering research and reflects a deep commitment to developing reliable, efficient, and safe mechanical systems, making him an exemplary candidate for the Best Researcher Award in Metallurgical Engineering.
Featured Publications
Naweed, M., Murtaza, U. T., & Siddique, W. (2021). Design optimization of a closure head for a PWR reactor pressure vessel. Nuclear Engineering and Design, 383, 111436. Cited by: 11
Naweed, M., Murtaza, U. T., & Siddique, W. (2023). Fracture mechanics analysis of a closure head of a PWR reactor pressure vessel: The effect of bolt pre-load and thermal stresses. Annals of Nuclear Energy, 189, 109843. Cited by: 8
Naweed, M., Murtaza, U. T., & Siddique, W. (2023). Fracture mechanics analysis of a closure head of a PWR reactor pressure vessel: LEFM-based SIF. International Journal of Pressure Vessels and Piping, 201, 104847. Cited by: 6
Naweed, M., Murtaza, U. T., & Siddique, W. (2023). Structural integrity assessment of a closure head of a PWR reactor pressure vessel under pressurized thermal shock. Nuclear Engineering and Design, 409, 112357. Cited by: 2
Naweed, M., Murtaza, U. T., & Siddique, W. (2023). Methodology for determination of critical crack depth in a class-I component. Theoretical and Applied Fracture Mechanics, 126, 103973. Cited by: 1