Table of Contents
Lead-cooled fast reactor (LFR)
What's so interesting about them?
The Lead-cooled Fast Reactor (LFR) is a versatile fast neutron reactor that can utilise depleted uranium, thorium, or burn actinides from light water reactor (LWR) fuel. It employs liquid metal (Pb or Pb-Bi eutectic) cooling, operating at atmospheric pressure through natural convection. The envisioned unit sizes vary, from small factory-built “battery” units for small grids to larger modular 300-400 MWe units and 1400 MWe single plants. The operating temperature of 550°C is achievable, with advanced materials allowing for 800°C, enabling thermochemical hydrogen production.
Fuel
Fuel
Moderator
Moderator
Coolant
Coolant
Typical technical data:
| Neutron Spectrum | Outlet Temperature (Degrees Celsius) | Fuel Cycle | Net Electrical Energy Generation seen in Development (MW) |
|---|---|---|---|
|
Fast |
480-570 |
Closed |
20-1,000 |
What is happening with them today?
Initial LFR development focused on experimental designs like the US STAR and Japan’s LSPR, both using lead or lead-bismuth cooling. In 2014, key developments included Russia’s SVBR-100 and BREST-300, Europe’s ALFRED, and Belgium’s MYRRHA. Russia’s SVBR-100 has been cancelled, and Westinghouse proposed an LFR project to the DOE in 2015 for demonstration by 2035.
The SSTAR reactor, running at 564°C, features an integral steam generator and operates for 20 years before the entire unit is returned for fuel recycling. The ELFR project, led by Ansaldo Nuclear, was designed for 600 MWe but appears to be superseded by the ALFRED reactor, which runs on MOX fuel at 480°C.
Matt Moore
The Generation IV International Forum – Lead-Cooled Fast Reactor (LFR)
The Generation IV International Forum – Technology Systems
