Nuclear Reactor Safety
Course Number:
NE 267
Course Units:
3
Course Instructor:
Peterson Catalog Description
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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
- NE 150
- NE 161
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
- Introduction, deterministic vs. probabalistic methods
- Safety philosophy, safety goals and criteria
- The regulatory arena
- Risk assessment & risk management
- Fire and seismic safety
- Accident and consequence analysis
- Dynamics and stability of systems
- 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.

