Abstract
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.
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