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The primary concern with this cycle, at least for water, is the material limits of the primary and support equipment. The materials in a boiler can be exposed to temperatures above their limit, within reason, so long as the rate of heat transfer to the coolant is sufficient to “cool” the material below its given limit. The same holds true for the turbine materials. With the advent of modern materials, i.e. super alloys and ceramics, not only are the physical limits of the materials being pushed to extremes, but the systems are functioning much closer to their limits. The current super alloys and coatings are allowing turbine inlet temperatures of up to 1290 oF (973 K) [3] and fourth generation super alloys with Ruthenium mono-crystal structures promise turbine inlet temperatures up to 2010 oF (1370 K) [4] in the future. Nuclear Light Water Power Application The Generation IV SuperCritical Water-cooled Reactor (SCWR) is a 1600 MWe nuclear power plant design based on the supercritical Rankine cycle. The system layout is identical to the supercritical system currently used in fossil fuels plants except the boiler is replaced with a nuclear reactor. The system diagram can be seen in Figure 7, page 5. Conventional nuclear plants operate on the simple Rankine cycle with superheating and exhibit thermal efficiencies on the order of 33%. The SCWR is capable of a thermal efficiency of 44.8% [5]. One of the attractive aspects of a supercritical cycle for a nuclear application is that it eliminates the need for pressurizers, primary to secondary heat exchangers, steam dryers, and steam generators. When one considers that the primary cost of electricity for a nuclear plant is the construction cost, elimination of support equipment is crucial, especially if it offsets the cost of heavier pressure vessels and support piping. The primary differences between the SCWR and conventional Boiling Water Reactors (BWR) & Pressurized Water Reactors (PWR) is the reactor outlet temperature is 930 oF (770 K) instead of 570 oF (570 K) and the SCWR operates at approximately 3625 psia [5] as compared to 915 psia and 2265 psia respectively [6]. This difference is graphically represented in Figure 8, page 5. In order to handle the higher pressures and temperatures, the reactor vessel must be designed to handle the extreme temperatures and pressures. The specifications required to meet this demand are listed in Table 1. More important than the pressure vessel however, are the fuel assemblies and control rod components. With a reactor inlet temperature of 535 oF (550 K), the reactor components are exposed to a temperature differential of 395 oF (220 K). Unlike the tubes in a boiler, a significant portion of the fuel assembly structure is not directly transferring heat to the fluid. This places much greater stress on those components and consequently, Phillip E. MacDonald performed a first order stress test on many of the common materials used for these assemblies. Of the austenetic (304L & 316L) and Nickle (Alloy 600, 625, 690, Table 1: SCWR Pressure Vessel Specifications [5] Parameter Value Material Design Pressure Operating Temperature Inside Shell Diameter Shell Thickness Head Thickness Vessel Weight SA-533 or SA-508 Grade 3, Class 1 27.5 MPa (3990 psig) 110% of nominal rating 535 oF (553 K) 5.322 m (209.5 in) 0.457 m (18 in) 0.305 m (12 in) 1.7 million lbs -4-PDF Image | Supercritical rankine cycle A synopsis of the cycle
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