Recently, a group of countries has initiated an international collaboration, the Generation IV International Forum (GIF), to develop the next-generation nuclear reactors. The GIF program has narrowed the design options of nuclear reactors to the following six concepts:

1) SuperCritical-Water-cooled Reactor (SCWR);

2) Sodium-cooled Fast Reactor (SFR);

3) Lead-cooled Fast Reactor (LFR);

4) Molten Salt Reactor (MSR);

5) Gas-cooled Fast Reactor (GFR); and

6) Very-High-Temperature Reactor (VHTR);

The purpose of this paper is to compare main thermophysical, corrosion, and neutronic properties of the Generation-IV reactors’ coolants within the proposed range of operation.

Volume Subject Area:
Thermal Hydraulics
Topics:
Coolants, Nuclear reactors, Fast neutron reactors, Molten salt reactors, Sodium fast reactors, Very high temperature reactors, Collaboration, Corrosion, Design, Generation IV reactors, Supercritical water reactors, Water
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