These courses are provided by distance education at NPI partner universities – Texas A&M University, Texas A&M University-Corpus Christi, Texas A&M University-Kingsville, Prairie View A&M University and Tarleton State University. This certificate is designed for engineers in disciplines other than Nuclear Engineering and will prepare students for careers in the nuclear industry. Successful completion of these courses will result in receiving the Nuclear Power certificate from NPI.
- ENGR 489 – Nuclear Power Plant Fundamentals
- ENGR 489 – Nuclear Power Plant Systems
- ENGR 489 – Nuclear Power Plant Operation
- ENGR-489 – Human Performance For Nuclear Power Plant Engineers
ENGR 489 – Nuclear Power Plant Fundamentals
3 credit hours
COURSE DESCRIPTION
This course is offered to students pursuing non-nuclear majors as a part of the Nuclear Power Engineering Technology Certificate program. The course is divided into six sections (modules):
The Water Chemistry for Nuclear Power Plants section of the course introduces students to the basic chemistry terms, units, definitions, limits, and basic concepts associated with chemistry control for nuclear power plant systems. Topics discussed in this section include
- fundamentals of chemistry,
- principles of secondary water chemistry control as applied to PWR,
- chemical and bio-fouling controls for auxiliary systems (PWR, BWR), and
- principles of reactor coolant system chemistry control for PWR and BWR (control and removal of impurities, radiochemistry).
The Material Science section of the course explains the terms, definitions, and basic concepts associated with reactor plant materials and how to recognize conditions detrimental to plant materials. Topics discussed in this section include classification of crystalline materials; imperfections in materials; material behavior and metallurgical definitions; mechanisms of deformation and fracture; effects of radiation on materials; alloys and their power plant applications; nuclear fuel; stress developed in the reactor vessel wall; erosion/corrosion effects; and nondestructive test methods.
The Electrical Science section of the course starts with a review of basic electrical theory followed by an introduction to basic alternating current (AC) and direct current (DC) theory. Topics covered in this section include AC and DC circuits, motors and generators, batteries, voltage regulators, transformers, electrical distribution systems.
The Mechanical Science section of the course covers mechanical engineering principals for all engineers at a nuclear power plant. Topics discussed in this section include statics and dynamics, lubrication, bolting fundamentals, piping, valve fundamentals and components, pumps, turbines, vibration, and rotating equipment safety.
The Civil Engineering for Nuclear Power Plant Engineers section of the course starts with a review of statics followed by a discussion of structural materials used at nuclear power plants. The section is concluded with an introduction of civil design considerations.
The Digital Process Control Systems section of the course covers the following topics: temperature measurement, pressure measurement, level measurement, flow measurement, control systems, and logic diagrams (digital control).
ENGR 489 – Nuclear Power Plant Systems
3 credit hours
COURSE DESCRIPTION
This course is offered to students pursuing non-nuclear majors as a part of the Nuclear Power Engineering Technology Certificate program. The course introduces students to the
- boiling water reactor (BWR) systems: the systems unique to the BWR for control of the fission process and the associated systems and strategy for reactor safety.
- pressurized water reactor (PWR) core systems: the systems unique to the PWR for control of the fission process and the associated systems and strategy for reactor safety.
- power plant generation: the balance of plant equipment used in the steam cycle.
The following subjects are covered:
- Reactor physics. Introduction to nuclear power
- Systems overview
- Reactor heat generation
- Thermodynamic aspects of nuclear power
- Reactor coolant systems: Primary loop. Secondary loop.
- PWR Coolant systems
- BWR Coolant systems
- Other reactor components
- Introduction to safety analysis
- Fuel systems
- Support systems
- Electrical distribution
ENGR 489 – Nuclear Power Plant Operation
4 credit hours
COURSE DESCRIPTION
This course is offered to non-nuclear majors interested in careers in the nuclear-electric-generating utilities. The course is divided in four sections (modules): reactor theory, heat transfer and fluid flow, radiological safety, and core protection. A fifth section will involve conducting reactor experiments and operations at the one megawatt research reactor on the Texas A&M University campus.
The Reactor Theory section of the course reviews the fundamental concepts of nuclear physics and nuclear engineering that pertain to a nuclear power reactor. Students will learn the sub-atomic interactions involved in nuclear fission and how the energy released from fission is safely controlled and channeled in a nuclear power plant to generate electricity.
The Heat Transfer and Fluid Flow section starts with a review of thermodynamics and basic properties of fluids. Then students will be introduced to the mechanisms of heat transfer in heat exchangers (conduction, convection, and radiation), followed by an analysis of heat transfer in a nuclear reactor. The concepts of flow rates and energy conversions in steady flow frictionless systems will be introduced. Students will learn mathematical equations used to evaluate properties of the fluid at different points in the system and how to predict the behavior of fluid flow in piping systems with friction losses present. The section is concluded by a discussion of how changes in system configuration and components, as well as changes in pump configuration and operation, effect a change in the amount of flow through the system.
The Radiological Safety section of this course starts with a review of nuclear and atomic physics. A study of the physics that describes the interaction of nuclear radiations with matter and biological systems follows. The latter includes a review of the state-of-the-knowledge in radiation biology, health, and risk. Principles of radiation transport and the practice of radiation dosimetry techniques are discussed. This section includes external dosimetry and internal dose assessment, as well as long-term risk analysis and an overview of radiation health-based regulations.”
The Core Protection part of the course introduces students to the core protection concepts (terms, units, definitions) and describes the consequences of damaged nuclear fuel, as well as the design and the operating policies to prevent it.
ENGR-489 – Human Performance For Nuclear Power Plant Engineers
2 credit hours
COURSE DESCRIPTION
This course is offered to students pursuing non-nuclear majors as a part of the Nuclear Power Engineering Technology Certificate program. The course is divided into four modules: human performance fundamentals, error reduction techniques, root cause analysis, and case study on TMI, Chernobyl, and Davis-Besse.
Human Performance Fundamentals.
Using principles developed by INPO, the fundamentals of human performance theory will allow students to understand the interrelationship between worker, culture, and organizations. The student will be introduced to the safety culture, questioning attitude and other approaches to improving human performance.
Error Reduction Techniques.
This topic is a continuation of human performance fundamentals. The student is challenged to identify the effectiveness of the various techniques to reduce errors and will choose the best technique given a set of circumstances. These include peer-checking, three-communication, and other techniques.
Root Cause Analysis.
With a background in human performance, the student will learn root cause analysis techniques.
Case Studies of Chernobyl, TMI, and Davis-Besse.
The student will analyze the lessons learned in the three most important events in commercial nuclear power. Other events will be discus