Nuclear Reactor Safety

Course Number: 
NE 267
Course Units: 
3
Course Instructor: 
Peterson

Catalog Description

  • Principles and methods used in the safety evaluation of nuclear power plants. Safety philosophies, design criteria and regulations. Deterministic and probabilistic models, reliability analysis, nuclear and thermal-hydraulic transients, radiological consequences, and risk assessment. Design-basis and severe accident analysis, role of engineered safety systems, siting, and licensing. Case studies of accidents. Offered even-numbered years.

Course Prerequisites

Course Objectives

  • To introduce students to the regulatory requirements and the safety issues related to the licensing of a complex engineered facility such as a nuclear (fission or fusion) power plant.
  • To give students some experience in preparing safety analyses and presenting their results for use in licensing.
  • To introduce students to some of the societal issues surrounding the design, construction and operation of such a plant.

Topics covered

  1. Introduction, deterministic vs. probabalistic methods
  2. Safety philosophy, safety goals and criteria
  3. The regulatory arena
  4. Risk assessment & risk management
  5. Fire and seismic safety
  6. Accident and consequence analysis
  7. Dynamics and stability of systems
  8. Case studies: Advanced reactors

Class schedule

  • Three hours of lecture per week

Assessment of student progress toward course objectives

  • The course will consist of lectures and a term project. The term project will focus on the safety analysis  required for siting a large complex engineered facility (e.g. fission  or fusion power plant, chemical process plant, etc.) at a   location in California. Grades will be based on the term projects and a final class presentation, in a hearing format.