B4992 - "Nuclear Power Plants for Sustainaibility T"

Learning outcomes

The course aims to provide students with a general understanding of electronuclear power plant for the power generation on an industrial scale, and in particular of boiling water reactors (BWR) and pressurized water reactors (PWR) power plants of the different generations. Upon completion of the course, the student acquires the basic knowledge regarding the operation of nuclear power plants, with special reference to their thermo-hydraulics, safety and risk analysis, and environmental impact.

Course contents

The course aims to frame the development of new nuclear plants within the context of the energy transition, highlighting the key role that nuclear energy can play in promoting sustainable development.

The fundamental concepts of integral sustainability and the process of decarbonizing the global energy system are explored in depth, with a particular focus on the renewed interest in nuclear energy in Europe.

The course analyzes the main existing and emerging nuclear technologies, including SMRs and AMRs.

Specific attention will be given to nuclear safety issues, both from a deterministic and probabilistic perspective, as well as to the environmental impacts of nuclear facilities.

By the end of the course, students will have acquired:

• Skills in applying sustainability concepts to the energy and nuclear sectors;

• Technical knowledge of nuclear plant systems and emerging technologies;

• Risk analysis capabilities, particularly regarding nuclear safety and the assessment of environmental impacts.

Content

• What are sustainable development and integral sustainability

• From “The Limits to Growth” to sustainable development; integral sustainability; the changing stance of Europe, Italy, and the Emilia-Romagna region regarding the use of nuclear energy

• The energy transition: the dynamics of energy source substitution; decarbonization of the energy system

• Architecture of third-generation nuclear plants

• Architecture of SMRs and AMRs

• Thermofluid dynamics of the reactor core and residual heat removal

• Risk analysis, safety, and safety culture; major nuclear incidents

• Probabilistic vs deterministic approaches; elements of probability theory

• Risk analysis tools (Block diagrams; Graph analysis; Fault Trees and Event Trees; …)

• Environmental impact of a nuclear reactor

Readings/Bibliography

Instructor’s Notes

J.R. LaMarsh, A.J. Baratta, Introduction to Nuclear Engineering, Prentice (2001)

J.C. Lee, N.J. McCormick, Risk and Safety Analysis of Nuclear Systems, Wiley (2011)

In-depth articles and technical reports

Teaching methods

Lectures and Practical Exercises

Expert Seminars

Visit to a Nuclear Facility (if possible)

Assessment methods

In-class exercises developed by students (not contributing to the final grade)

Midterm assessment

Final written exam

Additional oral exam upon request

Teaching tools

To be evaluated based on specific needs

Office hours

See the website of Paolo Vestrucci