Mediaspace scheduled maintenance: Aug 25, 2026 07:00 - 12:00 AM. During this time, videos will be temporarily unavailable. Check status updates.

Lecture

Introduction to Nuclear Engineering

In course

ME-464: Introduction to nuclear engineering

This course is intended to understand the engineering design of nuclear power plants using the basic principles of reactor physics, fluid flow and heat transfer. This course includes the following: Reactor designs, Thermal analysis of nuclear fuel, Nuclear ...

Description

This lecture covers various topics in nuclear engineering, including reactor technology, nuclear physics, fuel cycle, reactor physics, reactor kinetics, thermal hydraulics, radiation protection, nuclear safety principles, design basis accidents, generation-IV reactors, and waste treatment. The instructor discusses the emergency core cooling system, large-break LOCA, hydroaccumulators, containment design, BWR heat removal systems, severe accidents, core flooding tank, and safety analysis assumptions. The lecture also delves into LB-LOCA sequences, containment isolation, core heatup phase, temperature escalation phase, core melt progression, and engineered safety features of a PWR. The Fukushima Daiichi nuclear accident is analyzed, highlighting the severe consequences and lessons learned.

This video is available exclusively on Mediaspace for a restricted audience. Please log in to MediaSpace to access it if you have the necessary permissions.

Instructors (3)

Official source

Ontological neighbourhood

Energy engineering

Nuclear power: Topics in nuclear power

Related concepts (32)

Nuclear reactor

A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nuclear fission is passed to a working fluid (water or gas), which in turn runs through steam turbines. These either drive a ship's propellers or turn electrical generators' shafts. Nuclear generated steam in principle can be used for industrial process heat or for district heating.

Nuclear reactor safety system

The three primary objectives of nuclear reactor safety systems as defined by the U.S. Nuclear Regulatory Commission are to shut down the reactor, maintain it in a shutdown condition and prevent the release of radioactive material. A reactor protection system is designed to immediately terminate the nuclear reaction. By breaking the nuclear chain reaction, the source of heat is eliminated. Other systems can then be used to remove decay heat from the core. All nuclear plants have some form of reactor protection system.

Boiling water reactor

A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), which is also a type of light water nuclear reactor. The main difference between a BWR and PWR is that in a BWR, the reactor core heats water, which turns to steam and then drives a steam turbine. In a PWR, the reactor core heats water, which does not boil.

Molten salt reactor

A molten salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt with a fissionable material. Two research MSRs operated in the United States in the mid-20th century. The 1950s Aircraft Reactor Experiment (ARE) was primarily motivated by the technology's compact size, while the 1960s Molten-Salt Reactor Experiment (MSRE) aimed to demonstrate a nuclear power plant using a thorium fuel cycle in a breeder reactor.

Light-water reactor

The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator; furthermore a solid form of fissile elements is used as fuel. Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of thermal-neutron reactor. There are three varieties of light-water reactors: the pressurized water reactor (PWR), the boiling water reactor (BWR), and (most designs of) the supercritical water reactor (SCWR).

Related lectures (41)

Nuclear Reactors: Concepts and Analysis

Explores nuclear reactor physics, covering basic principles, specific reactor types, accidents like Chernobyl, and advanced technologies.

Nuclear Reactor Safety and Sustainability

Explores new nuclear reactor concepts, safety goals, and challenges for future nuclear systems.

Physics of Nuclear Reactors: Gas-Cooled Reactors

Explores gas-cooled nuclear reactors, covering basic principles, reactor concepts, fuel types, and advanced technologies.

Reactor Technology: Reactivity Variations and Control

Explores reactivity variations, control mechanisms, and the impact of the Doppler effect on reactor temperature.

Gas Reactor: Transmutation with Fast Neutrons and High-Temperature Concepts