Nuclear Reactor Type Reference

PWR, BWR, CANDU, and other reactor types compared.

Reference table of major nuclear reactor types — PWR, BWR, PHWR/CANDU, RBMK, AGR, fast breeder, HTGR, SMR and MSR — comparing moderator, coolant, fuel and approximate global count. Filter by any field. It runs free in your browser on Gera Tools, with nothing uploaded.

Last updated Source: Gera Tools

What is the difference between a PWR and a BWR?

Both are light-water reactors. In a Pressurised Water Reactor the primary coolant stays liquid under high pressure and heats a separate steam generator, so the turbine sees clean steam. In a Boiling Water Reactor the water boils directly in the core and that steam drives the turbine, making it simpler but mildly radioactive on the turbine side.

Comparing the world’s reactor designs

This reference compares the major commercial and notable nuclear reactor types, from the dominant light-water PWR and BWR through heavy-water CANDU, graphite designs like the RBMK and AGR, fast breeders, high-temperature gas reactors, and the emerging small modular and molten-salt concepts. Each entry lists the moderator, coolant, fuel and an approximate count of operational units.

How it works

Every reactor is defined by three choices. The moderator slows the fast neutrons from fission so they can sustain a chain reaction — light water, heavy water and graphite are the usual options, while fast reactors use none. The coolant carries heat out of the core to make steam; it may be the same water, a gas like CO₂ or helium, or liquid sodium. The fuel is usually uranium dioxide, enriched to a few per cent U-235, though heavy-water designs run on natural uranium and breeders use plutonium-bearing mixed oxide.

These choices interact. Heavy water’s low neutron absorption lets CANDU skip enrichment. Graphite moderation enabled early gas-cooled and Soviet RBMK designs. Removing the moderator entirely gives a fast spectrum that can breed more fuel than it burns. The table makes these trade-offs visible side by side.

Key design families at a glance

Light-water reactors (PWR and BWR)

Pressurised Water Reactors (PWR) are the most common design worldwide. The primary coolant stays liquid under roughly 155 bar of pressure and transfers heat through a steam generator, so the turbine circuit is completely separate from the radioactive primary loop. This two-loop arrangement is a safety advantage: the turbine sees clean steam. Boiling Water Reactors (BWR) simplify the plumbing by letting the water boil directly in the core and sending that steam straight to the turbine, but the turbine becomes mildly radioactive during operation as a result.

Heavy-water designs (CANDU / PHWR)

Canada’s CANDU reactor uses deuterium oxide (heavy water) as both moderator and coolant. Heavy water absorbs so few neutrons that the chain reaction sustains itself on unenriched natural uranium, skipping the enrichment step entirely. This is a practical advantage for countries that lack enrichment infrastructure. On-load refuelling — adding and removing fuel bundles while the reactor runs — is another CANDU characteristic that maintains a high capacity factor.

Graphite-moderated designs

The Soviet RBMK used graphite moderation and ordinary water cooling. Its positive void coefficient — a tendency to run faster as cooling water turned to steam — contributed to the Chernobyl accident. The design is not built anywhere today. Britain’s AGR and the earlier Magnox reactors also used graphite with CO₂ gas cooling, generating electricity reliably for decades. Magnox is now fully retired.

Fast reactors and breeders

Fast breeder reactors use liquid sodium as coolant and need no moderator. Operating in a fast-neutron spectrum, they can convert non-fissile U-238 into fissile plutonium faster than they consume fuel — in principle extending uranium resources dramatically. No large commercial breeder fleet has been built, but several demonstration and prototype units have operated in Russia, France, Japan, and India.

Emerging designs — HTGR, SMR, and MSR

High-temperature gas-cooled reactors (HTGR) use helium and operate at temperatures that enable industrial process heat as well as electricity. Small modular reactors (SMR) are factory-built units under roughly 300 MWe, with designs ranging from scaled-down PWRs to entirely novel configurations. Molten-salt reactors (MSR) dissolve fuel directly in a liquid salt coolant, a concept from the 1950s that is being revisited for its passive-safety potential.

Notes and caveats

  • Light-water PWRs and BWRs make up the great majority of the global fleet.
  • The RBMK is the Chernobyl-type design; its positive void coefficient was a key factor in that accident and the design is being phased out.
  • Magnox reactors are fully retired and shown for historical context.
  • Molten-salt reactors remain at the research stage with no commercial units; counts are approximate and change over time.
  • Filter the table by moderator, coolant or fuel to focus on the design characteristic that interests you — typing “heavy water” or “sodium” quickly narrows the list to the relevant entries.