M. Daniyal Nauman is a highly skilled nuclear engineer with a master’s degree in Nuclear Engineering from the Pakistan Institute of Engineering & Applied Sciences (PIEAS). With a background in Chemical Engineering, Daniyal has excelled in both academic and professional settings. His expertise lies in Computational Fluid Dynamics (CFD) and thermal hydraulics, where he has made significant contributions to innovative heat exchanger designs, safety analyses of research reactors, and proposals for passive containment cooling systems.
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Google Scholar Profile
Daniyal’s research output is notable, with publications in reputable journals such as the Journal of Power and Energy and the Annals of Nuclear Energy. His work has garnered attention within the academic community, evidenced by his publication record and citation metrics. Daniyal’s contributions to the field of nuclear engineering have established him as a respected author and researcher.
Education
Daniyal holds a master’s degree in Nuclear Engineering from PIEAS, where he achieved an impressive CGPA of 3.84. Prior to his master’s, he completed a bachelor’s degree in Chemical Engineering from the University of Engineering & Technology, Lahore, demonstrating his strong academic foundation in engineering disciplines.
Research Focus
Daniyal’s research primarily focuses on Computational Fluid Dynamics (CFD) and thermal hydraulics within the realm of nuclear engineering. He has conducted analyses on various aspects of heat exchanger designs, safety evaluations for research reactors, and proposals for passive containment cooling systems. His work contributes to the advancement of nuclear technology, with applications in reactor design, safety, and efficiency.
Professional Journey
Daniyal’s professional journey includes roles as a Senior Engineer at PINSTECH, PAEC, and as a Graduate Trainee Engineer at Engro Fertilizers, Dharki. At PINSTECH, he has been involved in cutting-edge research projects and has played a key role in the development of nuclear engineering solutions. His experience at Engro Fertilizers provided him with valuable industry exposure and practical engineering skills.
Honors & Awards
Throughout his academic and professional career, Daniyal has received numerous honors and awards. These include a gold medal in Chemical Engineering, achieving the second position in MS Nuclear Engineering from PIEAS, and receiving a fellowship from PAEC during his master’s program. His academic excellence and contributions to the field have been recognized both nationally and internationally.
Publications Noted & Contributions
Daniyal’s publications have made significant contributions to the field of nuclear engineering. Notable works include his research on the thermal-hydraulic investigation of passive containment cooling systems, experimental and CFD studies of innovative heat exchanger designs, and enhancement of heat duty for heat exchangers. His research outputs have advanced understanding in key areas of nuclear technology and reactor safety.
Experimental and Numerical Study of an Innovative Twined Tube HX Design
Authors: MA Khan, MD Khalid, M Ilyas, MD Nauman, M Asim, K Waheed, … Journal: Annals of Nuclear Energy Year: 2024 DOI: 10.1016/j.anucene.2024.110185
This publication presents an experimental and numerical investigation into an innovative twined tube heat exchanger (HX) design. Authored by a team including M. Daniyal Nauman, the study aims to enhance understanding of the thermal-hydraulic performance of the proposed design. By combining experimental testing with numerical simulations, the authors provide insights into the efficiency and effectiveness of the twined tube HX, contributing to advancements in nuclear engineering and heat transfer technology.
Thermal‐Hydraulic Investigation of a Proposed Concept for a Passive Containment Cooling System and Evaluation of Heat Exchanger Performance
Authors: M Ilyas, NH Hengra, MD Nauman, A Samee, MH Inayat Journal: Proceedings of the Institution of Mechanical Engineers, Part A: Journal of … Year: 2023
This publication focuses on the thermal-hydraulic investigation of a proposed concept for a passive containment cooling system, with a specific emphasis on evaluating the performance of the heat exchanger involved. Co-authored by M. Daniyal Nauman, the study delves into the intricacies of passive cooling systems, providing valuable insights into their feasibility and effectiveness in nuclear reactor safety. The research contributes to the ongoing efforts to enhance safety measures in nuclear power plants, with implications for reactor design and operation.
Research Timeline
Daniyal’s research timeline reflects a progression of projects and studies in nuclear engineering. Starting from his master’s program at PIEAS, he has been involved in various research endeavors, including analyses of heat exchangers, safety evaluations of research reactors, and ongoing studies on the effect of humidity on reactor safety margins. His research timeline demonstrates a commitment to advancing knowledge and innovation in nuclear engineering.
Collaborations and Projects
Throughout his career, Daniyal has collaborated on multidisciplinary projects and research initiatives. These collaborations have involved academic institutions, government agencies, and industry partners. His involvement in projects such as the development of passive containment cooling systems and enhancement of heat exchanger performance highlights his ability to work effectively in team environments and contribute to meaningful engineering solutions.
