Website belongs to an official educational in the Kingdom of Saudi Arabia always ends with .edu.sa
Secure websites in the Kingdom of Saudi Arabia use the HTTPS protocol for encryption.
Registered with the Digital Government Authority under number:
20260412890The Master of Science in Nuclear Engineering is a graduate program designed to prepare highly qualified specialists in nuclear engineering, radiation science, and nuclear technology applications. The program provides advanced knowledge in reactor physics, reactor engineering, radiation transport, operational radiation safety, engineering mathematics, and research methodology. The curriculum combines compulsory courses with specialized electives, including nuclear radiation detection and instrumentation, radiation protection, the nuclear fuel cycle, radiochemistry, computational radiation dosimetry, radiation effects on materials, and special topics in nuclear reactor engineering. The program culminates in a master’s thesis, through which students conduct independent research and apply theoretical, computational, and analytical methods to address advanced problems in nuclear engineering.
To be a leading reference in graduate studies in nuclear engineering, contributing to scientific advancement, promoting the safe applications of nuclear technology, and supporting sustainable national development.
To provide advanced education and research training that equips students with the scientific and practical knowledge and skills in nuclear engineering, radiation safety, and nuclear technology applications, qualifying them to conduct independent research, solve complex engineering problems, and contribute effectively to the energy, industrial, medical, regulatory, and research sectors in support of national development and societal needs.
Last Modified Date: 21/07/2026 - 9:29 PM Saudi Arabia Time
| Course Code | Course | Credits | Prerequisites |
|---|---|---|---|
| NE 611 | Nuclear Reactor Physics | 3 | – |
| Description | This course provides an introduction to reactor physics at the graduate level. Emphasis will be given to the energy distribution of neutrons in an infinite, homogeneous, and critical reactor; diffusion theory; energy group constants in the presence of resonance absorbers; and reactor kinetics. Numerical projects using MATLAB will be given to students | ||
| NE 621 | Reactor Engineering | 3 | – |
| Description | This course covers the thermal hydraulics of different types of reactor cores, including heat generation and removal, heat sources, steady and unsteady one-dimensional and two-dimensional heat conduction in fuel elements, convection with and without phase change and thermal core design. Numerical projects will be assigned to students to model specific thermal hydraulics phenomena. | ||
| NE 656 | Operational Radiation Safety | 3 | – |
| Description | Radiobiology and radiation protection. Optimization and safety procedures and equipment involving ionizing radiation. Use of personal dosimeters and area monitors for various types of ionizing radiation. Roles of the various regulatory bodies. International and national legal frameworks for nuclear industry. Role of the Nuclear Decommissioning Authority. | ||
| NE 635 | Radiation Transport | 3 | – |
| Description | Neutron transport equation, methods of solving neutron transport equation, point kernel technique, build-up factors, Monte Carlo simulation, pseudo-random numbers generation, probability density functions, sampling, particle tracking, geometry specifications, variance reduction techniques, numerical simulations | ||
| MATH 639 | Advanced Engineering Mathematics | 3 | – |
| Description | This course provides students with advanced mathematical methods commonly used in engineering applications. It covers infinite series, matrices, special functions, Laplace transforms, Fourier series and integrals, partial differential equations, and nonlinear differential equations. The course emphasizes the application of mathematical tools to solve linear systems, ordinary and partial differential equations, and to analyze statistical data relevant to engineering problems. | ||
| IE 694 | Engineering Research Skills | 3 | – |
| Description | Introduction to engineering research. Research design. Quantitative and qualitative research. Data collection procedures. Literature search and review. Survey research methods. Statistical analysis. Research presentation. | ||
| NE 681 | Seminar | 2 | – |
| Description | Students select a subject of interest and make a research about it. Then he will organize a presentation for faculty members and students. The topics may be any aspect of the nuclear engineering and must be approved by the academic advisor. | ||
| NE 699 | Master Thesis | 8 | – |
| Description | This course focuses on the preparation, development, and defense of a master’s thesis in the student’s research field. It enables students to identify a research problem, review and analyze relevant scientific literature, organize and evaluate data, apply appropriate theoretical, practical, and computational methods, and present research findings in a clear and scientific manner. The course also emphasizes drawing conclusions, making recommendations, using updated references, and defending the thesis before a scientific committee. | ||
| NE 630 | Radiation Effects on Materials | 3 | – |
| Description | Properties and selection of materials for nuclear steam supply systems and the effects of radiation on materials. The implications of radiation damage to reactor materials and the material problems in nuclear engineering are discussed. An overview of nuclear steam supply systems, crystal structure and defects, dislocation theory, mechanical properties, radiation damage, hardening and embrittlement due to radiation exposure and problems concerned with fission and fusion materials. | ||
| NE 640 | Nuclear Radiation Detection and Instrumentation | 3 | – |
| Description | Basic nuclear physics and radiation decay, interaction of radiation with matter, counting statistics and error propagation, properties of radiation detectors and pulse processing, radiation spectroscopy, detection efficiency, dead time, gas filled detectors, scintillation detectors, solid-state detectors, neutron detectors, state of the art radiation detectors, analog and digital pulse processing. | ||
| NE 651 | Current Methods in Radiation Protection | 3 | – |
| Description | Radiation protection guides such as ICRP, NCRP, etc. Radiation safety criteria, Allowable Limit on Intake (ALI), Derived Air Concentration (DAC), Maximum Permissible Concentration (MPC). Basic principles for external and internal radiation protection and radioactive waste management. Compartmental bio-kinetics models and important intake characteristics, uptake, concept of critical organ, and SEE (Specific Effective Energy) concept and dose calculations. | ||
| NE 653 | Nuclear Fuel Cycle | 3 | – |
| Description | Sources of nuclear fuel, mining, milling, and purification, principles of isotope enrichment, fuel fabrication, transport and reprocessing of spent fuel. In-core fuel management, linear reactivity, batch, nodal and pin cell methods, power shape and control management, partial core reloading, fuel depletion, poison management and hauling strategy, breeding and fast reactors, economics of the fuel cycle, computation of fuel cycle costs, waste disposal. | ||
| NE 667 | Radiochemistry and Analysis | 3 | – |
| Description | The course introduces chemical properties in radiation and radiochemistry. Use of stability constants and relationship between speciation, kinetics and thermodynamics. Influence of radiolysis on chemistry of radioisotopes. Radioisotope production and use. Radiochemical separations. The course also reviews current advances in radiochemistry, hot atom chemistry, radiation chemistry, and nuclear spectrometry. | ||
| NE 673 | Computational Methods in Radiation Dosimetry | 3 | – |
| Description | Intake and deposition ICRP models, MIRD method. Use of software packages for internal dose assessment. Physics and chemistry of radiation effect. Micro-dosimetry in the determination of absorbed dose distribution within tissue. MCNP dose calculation. Statistical fluctuations of absorbed dose at the cellular and subcellular level. Radiation emergency response. | ||
| NE 691 | Special Topics in Nuclear Reactors Engineering | 3 | – |
| Description | Nuclear reactor technologies and its applications, reactor research and fuel material manufacturing, applications of artificial intelligence and modern technologies in the field of nuclear power generation. | ||
| NE 692 | Special Topics in Nuclear Reactors Engineering 2 | 3 | – |
| Description | Nuclear reactor technologies and its applications, reactor research and fuel material manufacturing, applications of artificial intelligence and modern technologies in the field of nuclear power generation. | ||
