- 1 Definition
- 2 Description
- 2.1 Example: Curriculum for Bachelor's degree of nuclear engineering
- 2.2 Competencies of graduates with a bachelor of nuclear engineering
- 2.3 Requirements for a graduate with a bachelor's degree in nuclear engineering
- 3 References
- 4 Related articles
An academic degree awarded to individuals who have undergone an undergraduate course or major that range from three to four years depending on the national educational system
Example: Curriculum for Bachelor's degree of nuclear engineering
See Table 1.
Competencies of graduates with a bachelor of nuclear engineering
It should be understood that having a good knowledge of basics in maths, physics, and chemistry is a prerequisite to perform well in a nuclear engineering education programme.
The graduate with the qualification (degree) of Bachelor of Nuclear Engineering for nuclear installations must have the competencies shown below. These are divided into two categories. General competencies describe those basic and fundamental areas in which all engineers should have capabilities. Specific competencies are more directed to the field of nuclear engineering.
The graduates must have the following abilities:
- BC-I Perform written and informal communications and reports in their national language and possibly English.
- BC-II Work effectively as part of a team, and to sustain creative collaboration with their colleagues.
- BC-III Work independently within the framework of their professional qualifications, and have a commitment to professional development throughout their career.
- BC-IV Understand the basic laws of natural sciences including classical physics, chemistry, atomic and nuclear physics.
- BC-V Understand the basic approaches for acquiring, storing and processing knowledge, information and data; be familiar with standard computer code packages, including computer-aided graphics and design.
- BC-VI Conduct mathematical analysis and numerical simulation, and theoretical and experimental investigations in nuclear engineering.
- BC-VII Conduct mathematical simulation of processes in components of nuclear power plants; apply standard methods and computer codes for design and analysis.
- BC-VIII Perform radiation protection and measurement experiments, and analyse resulting experimental data.
- BC-IX Have a commitment to safety and an understanding of safety culture (including for example, risk analysis and management, human factor engineering, and man-machine interface).
- BC-X Understand the regulatory process and the role of the regulator in power plant licensing and operation.
- BC-XI Participate in the design process of the principal system and components of nuclear power plants or other nuclear facilities, accounting for environmental and safety requirements, and incorporating new requirements and technologies.
Requirements for a graduate with a bachelor's degree in nuclear engineering
Upon completion of the degree of Bachelor of Nuclear Engineering for nuclear installations, the student must know the following (Knowledge), be able to demonstrate application of the knowledge (Demonstration), and know when to implement the knowledge (Implementation):
- B1.1 Basics of analytical geometry and linear algebra, differential and integral calculus, probability and statistics, vector analysis, basics of differential equations and partial differential equation systems.
- B1.2 Basics of mechanics, oscillations and waves, thermodynamics, electrical and magnetic phenomena, statistical physics, physics of the atomic nucleus, and optics.
- B1.3 Neutron transport theory, thermal hydraulics, applications of computer code systems for mathematical simulation of thermo-physical and neutronics analysis.
- B1.4 Basic laws of heat and mass exchange in power equipment units of nuclear power plants, requirements for heat transfer and heat removal systems, thermo-physical processes in heat exchangers.
- B1.5 Thermodynamic principles, types and operation of steam turbines, calculation of efficiency, reliability, operation and maintenance.
- B1.6 Materials properties, strength of materials, and materials requirements for nuclear power plants.
- B1.7 Numerical analysis of power reactors, reactor materials, the principal parameters associated with nuclear power plant operation, research and power reactors, and the basic dynamics of nuclear reactors.
- B1.8 The general role of control systems in nuclear reactors. Linear control systems. Operation of control rods, and burnable and soluble poisons.
- B1.9 The classifications of nuclear power plants, the main components including coolant loops, steam generators, steam turbines, the main reactor coolant circuitry and auxiliary systems.
- B1.10 Reliability and safety of nuclear power plant operation, understanding plants as a component of a regional or national electricity grid.
- B1.11 The main parts of the nuclear fuel cycle. The open and closed fuel cycles. Radioactive wastes, categories of waste, and treatment options, conditioning, reprocessing and final disposal.
- B1.12 Basic principles of radiation protection. Methods for detecting ionizing
radiation. Hazards of radioactive materials. Concepts and definitions of radiation and dose units. Short term and long term biological effects of ionizing radiation. ALARA principles.
- B1.13 The regulatory environment for the operation of nuclear power plants. The role of the regulator. Responsibilities of nuclear power plant staff for safety.
- B1.14 Risks from the diversion of nuclear materials, the basic principles of nuclear safeguards. The Nuclear Non-proliferation Treaty and international agreements. The role of the International Atomic Energy Agency and other international organizations.
- B2.1 Through examination, conduct analysis of technical and scientific problems, to reach relevant and accurate conclusions based on the analysis.
- B2.2 Solve problems for real processes and determine technical solutions using current computational resources.
- B2.3 Develop designs for new applications utilizing fundamental scientific, mathematical and engineering principles.
- B3.1 Analytical and numerical methodologies for analysis of reactor physics, thermal hydraulic and electric systems for analysing boundary-value problems.
- B3.2 Methodologies for planning and conducting experiments, and evaluating experimental errors.
- B3.3 Technical documents and publications, handbooks and other information resources.
- B3.4 Utilization of computing techniques to solve special problems.
- B3.5 Ability to design nuclear power plant systems including neutronics and core analysis, and heat transport electrical generation systems.
- B3.6 Methodologies for ensuring the environmental safety of nuclear facilities.