Computational validation of a supercritical-water reactor in a thorium-uranium fuel cycle

A series of computational studies on the idea of a supercritical water (P = 25 MPa, T = 420 °C) cooled lightwater reactor operating in a thorium-uranium fuel cycle was conducted at the Physics and Power-Engineering Institute (FEI) in 2003–2010. These studies focused on the SKBR-T fast reactor. An integral breeding ratio 1.012, taking account of breeding in thorium screens, was obtained by optimizing the design parameters of the reactor. In this case, the reactor operates in a self-fueling regime and the neutron-physical characteristics satisfy the self-regulation and safety requirements. The principal characteristics of the fuel cycle were calculated. The design proposed for the reactor makes it possible to reach the indicated breeding ratio with current VVER fuel burnup and specific power. The economic performance is expected to be much improved over ordinary VVER power-generating units because of the single-loop thermal scheme and high efficiency.