Fission
Uranium nuclei split and release energy.
Discover how a nuclear reactor works, how uranium atoms release energy through nuclear fission, and how this energy is used to generate electricity.
Select a component to learn what it does inside the reactor.
Control the chain reaction, coolant flow and electrical output while keeping the reactor within a safe operating temperature.
Discover what happens when a neutron strikes a uranium-235 nucleus and starts a nuclear chain reaction.
A neutron is absorbed by a uranium-235 nucleus, making it unstable.
In a nuclear reactor, the chain reaction is controlled so energy is released steadily as heat.
Follow heat from the reactor through the steam generator, turbine and electrical generator. This diagram responds to the reactor controls above.
Educational schematic. The primary coolant transfers heat through the steam generator without mixing with the secondary steam circuit. Values follow the simplified reactor model above.
Follow the energy released inside the reactor.
Uranium nuclei split and release energy.
Energy from fission heats the coolant.
Steam turns the turbine.
The generator produces electrical energy.
Discover how nuclear reactors have evolved, and how different designs use coolants, moderators and steam-generation systems.
Important milestones in the development of nuclear electricity generation.
EBR-I in the United States generates usable electricity using a fast reactor.
The Soviet Obninsk reactor begins supplying nuclear-generated electricity to the grid.
Britain's Calder Hall begins operation, marking the development of gas-cooled commercial nuclear power.
The Shippingport demonstration plant introduces PWR technology to civilian electricity generation in the US.
Dresden Unit 1 begins commercial operation, helping establish boiling water reactors.
Canada's NPD reactor supplies electricity, demonstrating technology that leads to CANDU reactors.
Leningrad Unit 1 connects to the grid, marking an early Soviet RBMK power reactor.
Britain's AGR fleet begins operating at stations including Hinkley Point B and Hunterston B.
Select a reactor type to learn how it works and what makes it different.
A PWR uses water under high pressure to remove heat from the reactor core without allowing the primary coolant to boil.
Hot primary coolant transfers heat through a steam generator to a separate water circuit. Steam from that second circuit drives the turbine.
Developed from early US naval reactor technology. Shippingport began operating in 1957 as a pioneering civilian demonstration PWR.
A BWR allows water to boil directly inside the reactor vessel.
Nuclear fission heats water into steam. After moisture separation, the steam travels directly to the turbine and is later condensed and returned to the reactor.
Developed through experimental boiling-water reactor programmes in the 1950s. Dresden Unit 1 began commercial operation in 1960.
A PHWR uses heavy water containing deuterium, rather than ordinary light water, as its moderator. Many designs also use it as coolant.
Heavy water slows neutrons while absorbing relatively few of them. CANDU designs can use natural uranium fuel and allow refuelling during reactor operation.
Developed prominently in Canada. The NPD prototype generated electricity in 1962 and helped establish CANDU technology.
An AGR uses carbon dioxide gas as coolant and graphite to slow down neutrons.
Hot carbon dioxide carries energy from the reactor core to steam generators. These produce steam to turn the turbine.
Developed in the United Kingdom as a successor to Magnox gas-cooled reactors. The commercial AGR fleet began operating in 1976.
An RBMK uses graphite to moderate neutrons and ordinary water to cool fuel inside pressure channels.
Water boils inside the fuel channels. Steam is separated from the water and directed to turbines to generate electricity.
Developed in the Soviet Union. Leningrad Unit 1 connected to the grid in 1973. An RBMK reactor was involved in the 1986 Chernobyl disaster, leading to major safety modifications to remaining units.
Fast reactors use high-energy neutrons without deliberately slowing them with a moderator.
Many fast reactors use liquid metal coolants such as sodium, allowing heat to be transferred without moderating neutrons. Some can be designed to breed additional fissile material.
EBR-I, an experimental liquid-metal fast reactor, produced the first usable nuclear-generated electricity in December 1951.
Compare the main technical characteristics of these reactor families.
| Type | Coolant | Moderator | Steam generation |
|---|---|---|---|
| PWR | Light water | Light water | Separate steam generator |
| BWR | Light water | Light water | Directly in reactor vessel |
| PHWR / CANDU | Heavy water | Heavy water | Separate steam generator |
| AGR | Carbon dioxide | Graphite | Separate steam generator |
| RBMK | Light water | Graphite | Steam separated after boiling in channels |
| Fast reactor | Often liquid sodium | None | Typically through heat exchangers |
These are representative reactor families. Actual designs vary. A Small Modular Reactor (SMR) is a size and construction approach, not a separate coolant or moderator category. The interactive reactor above is an educational model rather than an exact commercial design.