Magy Mohamed Kandil

Professor and nuclear safety expert with extensive experience in nuclear reactor safety, advanced control systems, and AI applications. Proven track record in cybersecurity, thermal-hydraulic modelling, reactor simulation, and probabilistic safety assessment. Expertise in safety assessment, operational management, and providing technical support to regulatory authorities. Skilled in knowledge management for long-term operation and decommissioning of nuclear facilities.

• Magy M. Kandil, Fayza M. Ablemgeed. Software Testing as Applied to Computer Controlled Nuclear Reactor, Conference of Communication and Electronic Engineering, Cairo, 1989.
• Magy M. Kandil, Fayza M. Ablemgeed, Magda F. Fayek. Real-Time Pattern Recognition Using Adaptive Resonance Theory, Second International Conference for Information, Faculty of Computer, Cairo, 2004.
• Magy M. Kandil, Fayza M. Ablemgeed, Magda F. Fayek. A New Approach for Optimizing BackPropagation Training with Variable Gain Using PSO, ICGST International Conference on Graphics Vision and Image, Cairo, 2005.
• Magy M. Kandil, Samer Shein, Magda F. Fayek. Evolutionary Optimization of Neural Networks for Fire Recognition, ICCES06, Cairo, 2006.
• Magy M. Kandil, Samia Rashad, May Salama. Hybrid Algorithm for Fire Recognition Using Video Data in Real Time, IEEE Conference, Saint-Petersburg, Russia, May 2009.
• Magy M. Kandil, Samia Rashad, May Salama. Optimization of ART1 Neural Networks Using PSO for Fire Recognition, IPCV 2009, Las Vegas, Nevada, USA, July 2009.
• Magy M. Kandil, Samia Rashad, May Salama. Fire Detection Using a Dynamically Developed Neural Network, ELMAR-IEEE, Zadar, Croatia, September 2010.
• Magy M. Kandil, Samia Rashad, May Salama. Estimating the Number of Hidden Layers/Neurons in a Backpropagation Network, WORLDCOMP, Las Vegas, USA, July 2010.
• Magy M. Kandil, Samia Rashad, May Salama. A New Hybrid Algorithm for Fire Vision Recognition Inside the Closed Rooms in the Nuclear Reactor of Egypt, Engineering Research Journal, Faculty of Eng. Shoubra, April 2011.
• Samia Rashad, Mohamed El-Fawal, Magy M. Kandil. Evaluation of the Ventilation and Air Cleaning System Design Concepts for Safety Requirements During Fire Conditions in Nuclear Applications, XI Radiation Physics & Protection Conference, Cairo, Egypt, Nov 2012.
• Magy M. Kandil, Ahmed Gadallah, Faten Tawfik, Nema Kandil. Prediction of Maximum Ground Ozone Levels Using Neural Network, Int. J. Computing and Digital Systems, University of Bahrain, May 2014.
• Magy M. Kandil, Wessam Z. Awad. A New Real-Time Face Recognition Algorithm to Be Used in Nuclear Facilities, Int. J. Enhanced Research in Science Technology & Engineering, Vol. 3, Issue 8, August 2014, pp. 263–270.
• Magy M. Kandil. Real-Time Accidents Diagnosis for Research Reactors Using Adaptive Resonance Network, Int. J. Computing and Network Technology, 2014, 2(3).
• Magy M. Kandil, Wessam Z. Awad. Diversity Strategies in Computerized Safety Instrumentation and Control Systems, J. Energy and Environmental Science, Photon, Vol. 3, Issue 8, August 2014, pp. 569–575.
• Magy M. Kandil. Online Monitoring and Accidents Diagnosis System for Research Reactors, African J. Engineering Research, Vol. 3(1), Jan 2015, pp. 1–13.
• Magy M. Kandil. Safety Improvement of Nuclear Power Reactor Using Adaptive Resonance Network, Int. Conference on Operational Safety, Vienna, Austria, June 2015.
• El-Sayed M. El-Refaie, El-Gamel Amal A., A. H. Gepreel Mohamed, Magy M. Kandil, Hussein A. Z. Evaluation of Lead Nanoparticles Usability for Gamma Radiation Sensing, J. Materials Sciences and Applications, Vol. 1(5), 2015, pp. 262–265.
• El-Sayed M. El-Refaie, El-Gamel Amal A., A. H. Gepreel Mohamed, Magy M. Kandil, Hussein A. Z. Electrical Properties of Electrorefined Nanostructured Lead (Pb) for Enhancing Radiation Safety, Int. J. Materials Science and Applications, Vol. 4(5), 2015, pp. 283–287.
• Walaa El-Kattan, Magy M. Kandil, El-Sayed A. Said, Abd El-Razik Hussein. Evaluation of the Cable Types During Fire Conditions in Nuclear Power Plants, Int. J. Computing and Network Technology, Vol. 3(1), Jan 2015.
• Magy M. Kandil, May A. Salama. Determining the Optimum Number of Anchor Beacons While Localizing Wireless Sensor Network, Int. J. Wireless Communications, Networking and Mobile Computing, 2015; 2(4): 37–41.
• Magy M. Kandil, Mohamed Salama. A Hypothetical Accident Scenario for a Fire Accident with UF6 Packages Traversing Water Path Canal Close to a Highly Densely Populated City, Conference of Hardaka, Feb 2016.
• Magy M. Kandil. The Role of the Regulator in the Field of Safety Culture to Shun Nuclear Accidents, Int. Conference on Human and Safety Culture, Vienna, Austria, Feb 2016.
• Magy M. Kandil. Safety Culture for Regulator Competence Management in Embarking States, Third Int. Conference on Nuclear Knowledge Management, Vienna, Nov 2016.
• Magy M. Kandil. Cyber Security Accidents and I&C Systems in Nuclear Power Plants, Int. Conference on Physical Protection of Nuclear Material and Nuclear Facilities, Vienna, Austria, Nov 2017.
• Magy M. Kandil. The Role of Organizational Culture in Knowledge Management for Human Resource Development, Third Int. Conference on Human Resource Development for Nuclear Power Programmes, Gyeongju, Korea, May 2018.
• Magy M. Kandil. The Role of the Regulator in the Field of Safety Culture to Shun Nuclear Accident, J. Energy and Natural Resources, Vol. 7, Jan 2018.
• H. A. Refaey, M. A. Moawed, M. M. Kandil. Geometrical Study of Ventilation System Openings of Pump Room in Nuclear Power Plant, Alexandria Engineering Journal, Vol. 57, Issue 4, Dec 2018, pp. 3483–3491.
• Salwa Helmy, Magy M. Kandil, Ahmed Refaey. Dynamic Model for Predicting DNBR in PWR During Loss of Flow Accident, Int. J. Innovative Research in Science, Engineering and Technology, Vol. 8, Issue 2, Feb 2019.
• Magy M. Kandil, Azza A. Hassan, Afaf E. Ateya, Fatma A. Gaber. Simulation of the Intermediate Heat Exchanger (IHX) as Part of FBR Nuclear Power Plant, IJO, Vol. 2, No. 02, 2019.
• Magy M. Kandil, Azza A. Hassan, Fatma A. Gaber. Simulation of Turbine Generator, IJASRE, Mar 3, 2019.
• Salwa Helmy, Magy Kandil, Ahmed Refaey. Analysis of Thermal Hydraulic Behavior of KONVOI PWR During a Design Extension Condition, Nuclear Technology and Radiation Protection, Online March 2021.
• Salwa H. Abdel-Latif, Magy M. Kandil, Ahmed M. Refaey, Sayed A. Elnaggar. Simulation of Partial and Complete Loss of Flow Accidents for GPWR Using ATHLET Code, Int. J. Thermofluids, Vol. 11, May 2021, 100097.
• Hasnain A. Refaey, Ahmed M. Refaey, Magy M. Kandil, Mohamed A. Moawed. Geometrical Study of Ventilation System Openings of Pump Room in Nuclear Power Plant, Alexandria Engineering Journal, Nov 2018.
• Ahmed M. Refaey, Hasnain A. Refaey, Magy M. Kandil, Mohamed A. Moawed. Effect of Varying the Height of Inlet and Outlet Vent on Fire Protection in NPPs, Arab J. Nuclear Sciences and Applications, Vol. 51, 1, Jan 2018.
• Amany F. Abd El-Aal, Adel Zaghloul, Magy M. Kandil. Simulation Emergency Fire Evacuation Model for Nuclear Power Plant, J. Power and Energy Engineering, April 2021.
• Magy M. Kandil. Prediction of the Performance of the IAEA 10 MW MTR Research Reactor at Transient Startup, Arab J. Nuclear Sciences and Applications, Vol. 54, 2, March 2021.
• Magy M. Kandil. Simulation of Pressurized Water Reactor under Specified Reactivity Accidents, J. Multidisciplinary Engineering Science Studies (JMESS), Vol. 7, Issue 3, March 2021.
• Magy M. Kandil. Simulation of Small Modular Reactor under Specified Transients, European Academic Research, Vol. VIII, Issue 12, March 2021.
• Magy Kandil, Salwa Helmy, Ahmed Refaey. Prediction of the SMR Critical Core Performance Under Zero Power, Int. J. Systems Engineering, Vol. 5, No. 1, 2021, pp. 18–24.
• Salwa Helmy, Magy Kandil. Dynamic Model for Predicting DNBR in PWR During Loss of Flow Accident, Int. J. Innovative Research in Science, Engineering and Technology, Vol. 8, Issue 2, Feb 2019.
• Amany Nagy Kamel, Magy M. Kandil. Prediction of Corrosion for Austenitic Stainless Steel Aged Using Artificial Neural Network, Int. J. Scientific & Engineering Research, Vol. 12, Issue 4, April 2021, pp. 1072.
• Amany Fouad, Abd El-Aal, Adel Zaghloul, Magy M. Kandil. Safest and Shortest Exit Algorithm for NPP Fire Evacuation, Applied Engineering, 2021; 5(1): 36–43.
• Afaf A.E. Ateya, Rehab M. Saeed, Magy M. Kandil. Design of a Robust Intelligent Power Controller for Pressurized Water Reactor Using Particle Swarm Optimization Algorithm, DOI: 10.1515/kern-2024-0041.
• Samaa Ahmed Wasfy, Magy M. Kandil, Ahmed Mahmoud Refaey, Salwa Helmy. Study of Thermal and Mechanical Effects on Materials During Heat Transfer in Supercritical Regime, Arab J. Nuclear Sciences and Applications, Vol. 58, Issue 1, Jan 2025, pp. 43–55.
• Ahmed E. Salman, Magy M. Kandil, Afaf A.E. Ateya, Magdy R. Roman. Control of the VVER-1000 Core Power Using Optimized T-S Fuzzy Controller Based on Nonlinear Point Kinetic Model, Progress in Nuclear Energy, Vol. 180, Feb 2025, 105560.
• Ayman A. Elbordany, Magy M. Kandil, Hassan Youness, Hammam Abdelaal. An Efficient AI Algorithm for Fault Diagnosis in Nuclear Power Plants Based on Deep Learning Techniques, Progress in Nuclear Energy, Vol. 180, Feb 2025, 105580.
• Ahmed E. Salman, Magy M. Kandil, Afaf A.E. Ateya, Magdy R. Roman. Enhancing Steam Generator Pressure Control in Nuclear Power Plants Through Optimal Control Strategies, Annals of Nuclear Energy, 226 (2026), DOI: 10.1016/j.anucene.2025.111799.

·Magy M. Kandil and Afaf A.E. Atey, Dynamic Modeling for Efficient load Regulation in Two-Fluid Molten Salt Breeder  Reactors, Arab Journal of Nuclear Sciences and Applications, ajnsa.journals.ekb.eg, Arab J. Nucl. Sci. Appl., Vol. 59, 2, 61-73 (2026),

· Ayman A. Elbordany, Magy M. Kandil, Hassan A. Youness, Hammam M. Abdelaal, AI-Enhanced Emergency Response System for Nuclear Power Plants: Integrating Machine Learning with Symptom-Oriented Procedural Guidance.DOI 10.32918/nrs.2026.1(109).07 , Видання, 2026, Ядерна та радіаційна безпека, № 1(109), с. 77-96.ency Response System for Nuclear Power Plants: Integrating Machine Learning with Symptom-Oriented Procedural Guidance.DOI 10.32918/nrs.2026.1(109).07 , Видання, 2026, Ядерна та радіаційна безпека, № 1(109), с. 77-96.

• Nuclear Power Safety – ENNRA, Cairo, Egypt, May 2005
• Nuclear Power Safety – ENNRA, Cairo, Egypt, 20 March – 4 May 2008
• Capacity Building Program: Nuclear Safety for Egyptian Nuclear Regulators – ENNRA, Cairo, Egypt, 11–28 March 2012; organized by Korea International Cooperation and Korea Institute of Nuclear Safety
• Nuclear Safeguards & Security Workshop – IAEA & ENNRA, Cairo, Egypt, 14–16 May 2012
• Safety Assessment and Review of NPP – IAEA & ENNRA, Cairo, Egypt, 17–21 June 2012
• Self-Assessment Workshop for Nuclear Infrastructure Using SAG-16 – IAEA, Tunis, 14–17 July 2012
• Regulatory and Self-Assessment – IAEA & ENNRA, Cairo, Egypt, 25–29 November 2012
• Finite Elements Modeling Using COMSOL Multiphysics – Cairo, Egypt, February 2013
• Self-Assessment Workshop Using the IAEA Methodology and SARIS Software – IAEA & ENNRA, Cairo, Egypt, 16–18 June 2013
• Operating Experience Evaluation – ENSTTI, France, 9–13 September 2013
• National Workshop in Drafting Nuclear Security Regulations – IAEA & ENNRA, Cairo, Egypt, 11–13 March 2014
• Assistance of ENNRA for Human Resources Development Plan Preparation – IAEA & ENNRA, Cairo, Egypt, 22–26 June 2014
• Leadership, Management and Safety Culture for the Regulatory Body – IAEA & ENNRA, Cairo, Egypt, 30 November – 4 December 2014
• Quality Assurance – ENNRA, Cairo, Egypt, 22–25 March 2015
• Workshop on Training in Licensing – IAEA & ENNRA, Cairo, Egypt, 4–7 May 2015
• Workshop on Human Performance and Root Cause Analysis in Licensing – IAEA & ENNRA, Cairo, Egypt, 7–17 December 2015
• International Conference on Human and Organizational Aspects of Assuring Nuclear Safety – Exploring 30 Years of Safety Culture – IAEA, Vienna, Austria, 22–26 February 2016
• Workshop on Training in Methodology of Review of Safety Analysis Report (SAR) – IAEA & ENNRA, Cairo, Egypt, 6–9 February 2017
• First RCM and CS on Organizational Cultural Basis for Successful Performance in Nuclear Facilities – IAEA, Vienna, Austria, 4–6 July 2017
• First Research Coordination Meeting on Passive Engineered Safety Features in Advanced SMRs (CRP I3 2010) – IAEA, Vienna, Austria, 30 October – 2 November 2017
• Second Research Coordination Meeting on Passive Engineered Safety Features in Advanced SMRs (CRP I3 2010) – IAEA, Vienna, Austria, 4–7 May 2018
• International Conference on Challenges Faced by Technical and Scientific Support Organizations (TSOs) in Enhancing Nuclear Safety and Security – IAEA, Brussels, Belgium, 15–18 October 2018
• Technical Meeting on Safety and Security Interface Approaches and National Experiences – IAEA, Vienna, Austria, 29 October – 1 November 2018
• Third International Conference on Human Resource Development for Nuclear Power Programmes – Gyeongju, Korea, 28–31 May 2018
• Third Research Coordination Meeting on Passive Engineered Safety Features in Advanced SMRs (CRP I3 2010) – Daejeon, Korea, 3–6 September 2019
• Third International Regulators Conference on Nuclear Security – IAEA & Marrakech, Morocco, 1–4 October 2019
• Consultancy Meeting on Implementation of IAEA Safety Culture Self-Assessment Methodology – IAEA, Vienna, Austria, 13–19 October 2019
• Leadership Development Course – Criminal Research Institute, 23–26 February 2020
• International Conference on Computer Security in the Nuclear World: Security for Safety – IAEA, Vienna, Austria, 19–23 June 2023
• CRP Meeting: Advancing Thermal-Hydraulic Models and Predictive Tools for Design and Operation of SCWR Prototypes ([I31034) – IAEA, Vienna, Austria, 4–9 September 2023
• CRP Meeting: Advancing Thermal-Hydraulic Models and Predictive Tools for Design and Operation of SCWR Prototypes ([I31034) – IAEA, Vienna, Austria, 2–7 September 2024
• International Conference on Small Modular Reactors and Their Applications – IAEA, Vienna, Austria, 21–25 October 2024
• International Conference on Enhancing Nuclear Safety and Security Through TSOs – IAEA, Vienna, Austria, 2–6 December 2024
• Train the Trainers Course on the IAEA School on Nuclear and Radiological Leadership for Safety – IAEA, Cairo, Egypt, 13–15 May 2025
• 28 September – 2 October 2025
• Organized by the Arab Atomic Energy Authority in collaboration with the Egyptian Atomic Energy Authority, Cairo, Egypt.
• Supervised and guided participants throughout the training program
• Provided mentorship and practical insights on cybersecurity applications in nuclear facilities
• Organized by the Arab Atomic Energy Authority in cooperation with the Egyptian Atomic Energy Authority, Cairo, Egypt.

• Lead safety assessments for research reactors and NPPs (Deterministic & Probabilistic Safety Analysis).
• Develop, review, and validate reactor I&C systems for compliance with national and international safety standards.
• Design and implement reactor simulators and dynamic modeling platforms for operator training and accident scenario evaluation.
• Perform fault detection, diagnosis, and prognostics using AI-assisted techniques.
• Conduct software verification and validation (V&V) for safety-critical software.
• Implement wireless sensor and smart monitoring systems for nuclear facilities.
• Conduct fire safety and protection system assessments, hazard analysis, and emergency preparedness.
• Establish knowledge management systems for operational experience, regulatory knowledge, and long-term operation.
• Serve as a member of national technical committees for reactor safety, licensing, inspection, and regulation.
• Contributed to drafting national regulations for Instrumentation & Control, Mining, Fire Protection, and NPP Design (2014–2020).
• Promote nuclear safety culture, quality assurance, and human factors integration in nuclear operations.

• Member of national technical committees for reactor safety assessment, licensing, regulatory inspection.
• Contributed to drafting and updating national regulations:
• Instrumentation and Control Systems (2014)
• Mining & Nuclear-Related Industrial Safety Regulations (2015)
• Fire Protection & Fire Safety Engineering Regulations (2015)
• Nuclear Power Plant Design & Safety Regulations (2020)

• Electrical Engineering and Nuclear Technology Applications
• Advanced Control Systems for Nuclear Reactors
• Deterministic and Probabilistic Risk and Safety Analysis (DSA & PSA)
• Reactor Operations, Transient Analysis, and Accident Management
• Thermal-Hydraulic Modeling and Safety Analysis of Small Modular Reactors (SMRs)
• Modeling, Simulation, and Digital Twin Development for NPPs
• Cybersecurity for Digital I&C and Industrial Control Systems