Teaching

MEMS 1220 / ME 2220: Reliability & Risk Analysis for Engineering Systems

Term: Spring 2027 (New course)

This course will study the theoretical and methodological foundations of risk and reliability analysis for complex engineering systems, with emphasis on rare events (annual likelihood < 1E-4) that can cause significant consequences for system safety and performance once they occur.

About one-fourth of the course covers the fundamentals of probability and statistics needed for risk and reliability analysis, and the remainder is split evenly between component reliability modeling and data analysis as well as systematic risk assessment methods. This course gives students a systematic perspective that connects their fundamental engineering knowledge to a structured understanding of system safety and to engineering decision-making. This course will focus on current practice in industries such as nuclear power and aerospace, where risk and reliability analysis is commonly used to inform critical decisions related to design, licensing, operations, and maintenance.

At the conclusion of this course, you will be able to: 

  1. explain the fundamentals of probability and statistics used to characterize uncertainty in low-likelihood but high-consequence events;
  2. construct and analyze component reliability models using hardware reliability data;
  3. construct and quantify fault trees and event trees to systematically assess risk in complex engineering systems;
  4. conduct human reliability analysis to assess the contribution of human error to system risk;
  5. evaluate risk and reliability analysis results to inform engineering decisions such as design, operations, and maintenance

 

ENGR 1700: Introduction to Nuclear Engineering

Term: Offered every Fall

This course provides an introduction to nuclear science and technology, covering both foundational concepts and practical applications. Topics include the history of nuclear development, reactor types, elementary nuclear and reactor physics, radiation and safety principles, radioactive waste management and disposal, the nuclear fuel cycle, and historical accidents and lessons learned.

The course serves as an initial stepping stone for students interested in pursuing careers or advanced studies in nuclear-related fields, including the nuclear industry, academia, national laboratories, government agencies, and international organizations. Emphasis is placed on developing a strong conceptual understanding that prepares students for deeper engagement with the field.

Topics presented in the class include the following:

  • Historical context of nuclear energy
  • Review of fundamentals of nuclear physics
  • Nuclear reactions and cross-sections
  • Reactor physics
  • Reactor kinetics, reactor control, and feedback
  • Radiation physics and safety principles
  • Introduction to light-water reactors
  • Fuel depletion and related effects
  • Nuclear fuel cycle and waste management
  • Reactor safety

rare lab class picture teaching in progress

NUCE 2104: Nuclear Operations and Safety

Term: Offered every Spring

A nuclear power plant differs from conventional power plants in using nuclear fission to provide the heat used to generate steam that drives an electric turbine generator. This abundant, renewable, and unique power source has many benefits, as well as unique characteristics that necessitate special attention to safety in design, licensing, and operation.  

Our first responsibility is to understand the fundamental physics governing the plant processes – nuclear fission and core kinetics, criticality, radiation physics, feedback mechanisms, and accident progression that are not seen in a fossil, solar, wind, or other power system.

In this course, we will become familiar with these processes, methods for calculating some of their key features, and the relationship of those features to normal and off-normal plant operations, up to and including severe accidents. 

Two approaches to nuclear safety evaluation will be discussed:

  1. Deterministic calculation, in which a phenomenon is analyzed according to fixed assumptions, using mathematical techniques focused on that purpose, and
  2. Probabilistic Risk Assessment (PRA) that considers the spectrum of possible accident scenarios and plant responses using systems modeling and statistical methods. 

The main course topics include: 

  • Key Principles and Evolution of Nuclear Safety
  • Review of Nuclear Physics and Neutron Reactions
  • Nuclear Fission Systems and Criticality Safety
  • Reactor Reactivity Control
  • Reactor Accident Phenomenology
  • Radiation Protection
  • Offsite Accident Impacts
  • Probabilistic Risk Assessment (PRA)
  • Operations and Safety of Advanced Reactors