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2.4.2 Supercritical CO2 cycle at the Tokyo Institute of Technology Another institute that is currently investigating the supercritical CO2 cycle is the Tokyo Institute of Technology in Japan [Kato et al., 2001]. The work here at first focused on partial condensation cycles, but given the difficulties with the supply of the cold cooling water the current reference design is a partial cooling cycle. A thermal efficiency of 50% at 12 MPa was achieved with the partial cooling cycle operating at a reactor outlet temperature of 800oC. Recently, a corrosion loop was built at the Tokyo Institute of Technology and corrosion studies of candidate materials for use in the supercritical CO2 cycle are in progress. One part of the corrosion loop is a HEATRIC design printed circuit heat exchanger. This type of heat exchanger is vital for the future successful implementation of the cycle and its testing is of prime interest. 2.4.3 Supercritical CO2 cycle at other institutes In the United States the investigation of the recompression supercritical CO2 cycle was resumed in the year 2000 at MIT under collaboration with INEEL. An indirect supercritical CO2 recompression cycle was designed for a lead-bismuth eutectic cooled reactor [Dostal et al., 2001]. A net efficiency of 41% was calculated for a compressor outlet pressure of 20 MPa and LBE reactor outlet temperature of 555oC. Currently, both direct and indirect versions for fast gas cooled reactors are being pursued. At Argonne National Laboratory the recompression cycle is being evaluated for the STAR-LM reactor [Moisseytsev et al., 2003], and at INEEL the CO2 Brayton cycle with multiple inter-coolers operating at temperatures above 900oC is being investigated for thermal spectrum gas cooled reactors [Oh, 2002]; both are NERI projects. 2.5 Summary This chapter described the benefits of compression near the critical point, the causes of the pinch-point problem and the past investigations of supercritical CO2 cycles. The 36PDF Image | Advanced Nuclear Power Technology Program A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
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