Reactor type 6 of 10

Sodium-cooled fast reactor

by Joe Miller

Sodium-cooled fast reactors use liquid sodium metal as the coolant and no moderator, so neutrons stay fast. Fast neutrons can burn the long-lived parts of spent fuel and can even breed more fuel than they use.

PhotoHow it circulatesComponentsKey detailsMaintenanceWhere it runs

Plain-English explainer by Joe Miller, a nuclear engineer. Not investment advice. Figures are the latest public numbers we could find and change fast; sources are at the bottom of each page.

What it looks like

Experimental Breeder Reactor II in Idaho, which ran from 1964 to 1994 and in 1986 shut itself down safely in tests with the pumps turned off.
Experimental Breeder Reactor II in Idaho, which ran from 1964 to 1994 and in 1986 shut itself down safely in tests with the pumps turned off. Photo: Argonne National Laboratory, public domain.

How the coolant circulates

Sodium-cooled fast reactor: pool of liquid sodium, plus an intermediate loopReactor pool (primary sodium)coreIHXheatexchangerprimary pumpSteam generatorintermediate sodiumTurbineGGeneratorto the gridCondensersteam back to watercooling water(river, lake or tower)steamfeedwater pumpNatrium adds hot molten-salt tanks to store heat and boost output.Primary sodium (in the pool)Intermediate sodium, hotIntermediate, returningSteamFeedwater
Arrows show the direction of flow in each loop.
  1. Primary pumps push sodium up through the core (about 500 to 550°C out).
  2. Hot sodium flows through the IHX inside the pool.
  3. The intermediate sodium loop carries heat out to the steam generator (or salt storage in Natrium).
  4. Steam drives the turbine; cooled intermediate sodium returns to the IHX.

The main components

ComponentWhat it does
Reactor poolA large tank of liquid sodium at near-atmospheric pressure holding the core, pumps and heat exchangers.
CoreMetal or oxide fuel pins, more highly enriched than water-reactor fuel (HALEU, up to about 20%), packed tightly with no moderator.
Primary pumpsCirculate sodium through the core inside the pool.
Intermediate heat exchanger (IHX)Transfers heat to a separate, non-radioactive sodium loop so radioactive sodium never reaches the steam generators.
Steam generatorIntermediate sodium boils water; it is designed carefully because sodium reacts violently with water.
Cover gasArgon blankets the sodium surface to keep air away.
Molten-salt heat storage (Natrium)Hot salt tanks store heat so the plant can boost output from 345 to 500 MW for several hours.

Key details

ItemDetail
CoolantLiquid sodium
ModeratorNone (fast spectrum)
FuelMetal or oxide, HALEU up to about 20%
PressureNear atmospheric
TemperatureAbout 500 to 550°C
EfficiencyAbout 40%
RefuelingEvery 1 to 2 years

How it is maintained

Where it runs

Russia's BN-600 and BN-800 at Beloyarsk (running); India's prototype fast breeder at Kalpakkam; China's CFR-600; TerraPower's Natrium at Kemmerer, Wyoming (NRC construction permit March 2026, aiming for about 2030; Meta has signed for up to eight units); Oklo's Aurora.

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Who's writing this? I'm Joe Miller, a nuclear engineer since 1974 and an ASME Fellow. I've run safety analyses for PWRs and BWRs, directed nuclear engineering at a working BWR, and reviewed new reactor designs for the NRC. This site explains every kind of reactor in plain English. My background and papers.