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identified for ideal gas GFRs may not be as detrimental for S-CO2 systems. For example, the pumping power requirements are low for an S-CO2 system because the fluid density of the coolant at the compressor inlet conditions is very high (60-70% the density of water). The fluid is nearly incompressible and, therefore, the pumping power is low, even with the expected core pressure drop. Likewise, high-pressure, high-density fluids mean lower gas velocities, smaller containment, smaller turbomachinery, smaller heat exchangers, and smaller piping, provided the reactor concept remains roughly below the 300-500 MWth power size. Similarly, decay heat removal can be addressed by using natural circulation mechanisms, in the event that the turbomachinery is inoperable. Large flow rates due solely to natural circulation mechanisms have been observed in the research loops. Through appropriate design of the power conversion system, natural circulation mechanisms could be implemented to provide passive decay heat removal features. There also exists the ability to provide large tanks of liquid CO2 that can blow- down through the reactor to provide core cooling by venting through a break. These “blow- down” systems require no external pumps. Guard pressure vessels are often used in some GFR concepts to mitigate the effects of LOCA. CO2 expansion cooling has been found to be extremely effective and is used to cool down hardware in the research loops. As observed in the S-CO2 research loop, the venting and blow-down process through multiple 1⁄4 inch valves can take hours. Appropriate design of emergency cooling systems could allow for effective core cooling available for long periods of time. 2.1 Comparison of the GFR Concepts A comprehensive review of the GFR concepts is provided by van Rooijen (2009) covering the design concepts through 1980. More recently, the Department of Energy Office of Nuclear Energy (DOE-NE) Generation IV program has selected the GFR as one of its six preferred options. Research has identified literature describing four concepts from 2001 through 2009. One is by Idaho National Laboratory (INL) (Weaver and Khalil, 2002), another by the Tokyo Institute of Technology (TIT) (Kato, et al., 2004), a third by the Massachusetts Institute of Technology (MIT) (Pope, 2004; Handwerk, 2007; Pope, et al., 2009), and the last by the French Commissariat a l’Energy Atomique (CEA) (Dumas, et al., 2007). A fifth paper by British Nuclear Fuels (BNFL) (Newton and Smith, 2001) was reviewed that described a GFR based on the British Advanced Gas Fast Reactor. All of these systems provided basic design features for GFRs. Most used CO2 as the primary coolant, although the CEA design used helium or a helium-nitrogen mixture. A summary of the major design features is provided in Table 1. A review of this work confirms a number of design features. Most of the designs were developed for very large reactors, ~2400 MWth. The core sizes were large, 4-5 m in diameter, and most operated at power densities near 100 W/cc for the core. They all showed small reactivity consequences for a depressurization event (less than +$1.00 positive). Also, most of the concepts used active methods for decay heat removal. Several used guard vessels to mitigate the consequence of a LOCA to avoid full depressurization. Perhaps the most intriguing feature was that the concepts largely used non-conventional fuels. UC-SiC plates and UO2-BeO fuel were proposed, even though these fuel types have not been fully developed, characterized, or tested. Only the TIT design and the BNFL design concepts used conventional fuel: metal fuel for the TIT concept and oxide for the BNFL GFR concept. 12PDF Image | Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR)
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