Yasser Hamada | Nuclear Reactor Theory | Excellence in Research

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Assoc Prof Dr. Yasser Hamada | Nuclear Reactor Theory | Excellence in Research

šŸ‘Øā€šŸ«Profile Summary

Yasser Mohamed Hamada is an Assistant Professor of Applied Mathematics at Tanta University’s Faculty of Science. Born on August 30, 1973, in Egypt, he holds a Ph.D. in Applied Mathematics and specializes in Quantum Mechanics and the Theory of Nuclear Reactors. With an h-index of 10, he has authored numerous publications in prestigious journals, focusing on computational methods for neutron diffusion systems. Currently affiliated with Suez Canal University, Hamada is recognized for his expertise in numerical methods and stability analysis for reactor kinetics equations. He is also an experienced educator with over a decade of service at Suez Canal University and previous experience in Bahrain. Additionally, Hamada is an accomplished author of scientific books and an active YouTube channel creator.

 

šŸŒ Professional Profiles

 

 

šŸŽ“ Academic Journey

B.Sc in Major Mathematics (1995), M.Sc in Applied Mathematics (2003), PhD in Applied Mathematics (2009)

šŸ† Highest Attainment

  • Assistant Prof. in Applied Mathematics since 2018

šŸ” Specific Specialization

  • Applied Mathematics
  • Quantum Mechanics ā€“ Theory of Nuclear Reactors

 

 

šŸ“šTop Noted Publication

 

Power series solution (PWS) of nuclear reactor dynamics with Newtonian temperature feedback Paper Published in 2003 Cited by 74

PWS: an efficient code system for solving space-independent nuclear reactor dynamics Paper Published in 2002 Cited by 60

Generalized Rungeā€“Kutta method for two-and three-dimensional spaceā€“time diffusion equations with a variable time step Paper Published in 2008 Cited by 49

Computation accuracy and efficiency of a power series analytic method for two-and three-space-dependent transient problems Paper Published in 2009 Cited by 27

Modified fractional neutron point kinetics equations for finite and infinite medium of bar reactor core Paper Published in 2017 Cited by 27

Solution of a new model of fractional telegraph point reactor kinetics using differential transformation method Paper Published in 2020 Cited by 23

Confirmation of accuracy of generalized power series method for the solution of point kinetics equations with feedback Paper Published in 2013 Cited by 22

Nonstandard finite difference schemes for numerical solution of the fractional neutron point kinetics equations Paper Published in 2017 Cited by 16

Trigonometric Fourier-series solutions of the point reactor kinetics equations Paper Published in 2015 Cited by 21

Generalized power series method with step size control for neutron kinetics equations Paper Published in 2011 Cited by 15

Ayah Elshahat | Nuclear Engineering | Best Researcher Award

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Assoc Prof Dr. Ayah Elshahat | Nuclear Engineering | Best Researcher Award

Assoc Prof Dr. Ayah Elshahat,Ā  Alexandria University,Ā  Egypt

šŸ‘Øā€šŸ«Profile Summary

Ayah Elshahat possesses a strong academic background with a B.Sc. in Nuclear Engineering from the Faculty of Engineering at Alexandria University in 2001. He furthered his education with an MSc in “Thermal Performance of Nuclear Reactors” from the Nuclear and Radiation Engineering department at Alexandria University in 2005. His academic journey culminated in a Ph.D. titled “Enhancing Nuclear Energy Sustainability Using Advanced Nuclear Reactors” from the University of Manchester (UK) in 2015. specializes in various aspects of nuclear engineering, including thermal performance of nuclear reactors, nuclear reactor modeling, safety protocols, and advanced nuclear reactors. He has undergone specialized training courses in research-related skills, such as influencing in a research setting, radiation protection, effective presentation skills, and research team management. Dr. [Name] is not only well-versed in the technical aspects of nuclear engineering but also equipped with competencies in effective teaching, demonstrator preparation, and promoting ethical practices in education. His commitment to continuous learning is evident through additional training in examination systems, students’ evaluation, and communication skills. In 2019, he participated in Competencies Based Education (APITEL 2019), further enhancing his expertise in the field.

šŸŒ Professional Profiles

šŸŽ“Qualifications

B.Sc. in Nuclear Engineering, Faculty of Engineering, Alexandria University, 2001. M.Sc. in “Thermal Performance of Nuclear Reactors,” Nuclear and Radiation Engineering Department, Alexandria University, 2005. Ph.D. in “Enhancing Nuclear Energy Sustainability Using Advanced Nuclear Reactors,” University of Manchester (UK), 2015.

Fields of Expertise

Thermal Performance of Nuclear Reactors, Nuclear Reactor Modeling, Safety of Nuclear Reactors, Advanced Nuclear Reactors, Modeling and Simulation

Researcher Training Courses

šŸŒŸ Influencing in a Research SettingšŸ¤” Practical Thinking for Researchersā˜¢ļø Radiation ProtectionšŸ“š Examination Systems and Students’ EvaluationšŸŽ™ļø Effective Presentation SkillsšŸš€ Preparation of a Competitive Research ProjectšŸ¤ Research Team ManagementšŸ’¬ Communication SkillsšŸŽ“ Effective TeachingšŸ§‘ā€šŸ« Demonstrator PreparationšŸ“– Teaching Ethics

Competencies Based Education (APITEL 2019)

šŸ“ŠĀ Citation Metrics (Google Scholar):

Citations by: All ā€“ 89, Since 2019 ā€“ 42

h-index: All ā€“ 6, Since 2019 ā€“ 5

i10 index: All ā€“ 4, Since 2019 ā€“0

šŸ“šTop Noted Publication

Assessment of nuclear energy sustainability index using fuzzy logic Paper Published in 2010 Cited by 27

Assessment the safety performance of nuclear power plants using Global Safety Index (GSI)Paper Published in 2010 Cited by 15

Optimum selection of an energy resource using fuzzy logic Paper Published in 2009 Cited by 13

Simulation of the Westinghouse AP1000 response to SBLOCA using RELAP/SCDAPSIM Paper Published in 2014 Cited by 11

A methodology for CHF prediction in VVER rod bundles Paper Published in 2022 Cited by 6

Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3. 5 Paper Published in 2021 Cited by 6

Safety Analysis in VVER-1000 due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient using RELAP5/SCDAPSIM/MOD3. 5 Paper Published in 2022 Cited by 4

Analyzing population dynamics models via Sumudu transform Paper Published in 2021 Cited by 5

Study of Different Seed Fuels with Thorium in Accelerator-Driven Subcritical System Paper Published in 2021 Cited by 3

Investigation of VVER-1200 pressurizer dynamics by adopting modelica based modelingĀ  Paper Published in 2022 Cited by 2

Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code Paper Published in 2022 Cited by 1