Heavy Water Reactors (HWRs) utilize heavy water (deuterium oxide) as both a moderator and a coolant. This allows them to operate with natural uranium fuel, making them more efficient and cost-effective.

Control rods are inserted or withdrawn from the reactor core to control the rate of nuclear reactions by absorbing neutrons. This allows operators to adjust the power output of the reactor.

Gas-Cooled Reactors (GCRs) employ graphite as a moderator to slow down neutrons and sustain the nuclear chain reaction.

Pressurized Water Reactors (PWRs) utilize ordinary water (light water) as the primary coolant, which is pressurized to prevent boiling and maintain high efficiency.

Boiling Water Reactors (BWRs) are widely used in commercial power plants for electricity generation. They directly convert the heat from nuclear reactions into steam, which drives a turbine to generate electricity.

The primary function of a moderator in a nuclear reactor is to slow down neutrons produced by nuclear reactions, allowing them to be more easily captured by fissile atoms and sustain the nuclear chain reaction.

Sodium-cooled Fast Reactors (SFRs) employ liquid sodium as a coolant due to its excellent heat transfer properties and ability to operate at high temperatures.

Most commercial nuclear reactors primarily use Uranium-235 as fuel due to its high fissile properties and availability.

Fast Breeder Reactors (FBRs) are designed to produce more fissile material (such as Plutonium-239) than they consume, potentially extending the availability of nuclear fuel.

The primary purpose of a containment structure in a nuclear power plant is to prevent the release of radioactive materials into the environment in the event of an accident.

Pressurized Heavy Water Reactors (PHWRs) utilize heavy water as a moderator and ordinary water as a coolant, providing efficient neutron moderation and heat transfer.

The primary purpose of a nuclear reactor's control system is to maintain a stable and safe operating condition by regulating various parameters such as power output, temperature, and neutron flux.

Research Reactors are specifically designed for research purposes, including isotope production, material testing, and neutron scattering experiments.

CANDU reactors primarily use Uranium-235 as fuel, which is blended with natural uranium to form fuel bundles.

Molten Salt Reactors (MSRs) employ molten salt as a coolant and fuel carrier, offering potential advantages in terms of safety, efficiency, and waste management.