ElectraTherm Green Machine Generates Power Biomass in Italy

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ElectraTherm Green Machine Generates Power Biomass in Italy ( electratherm-green-machine-generates-power-biomass-italy )

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Fig. 2. Schematic of GFR Vessel with Core (from [20]) Table 4. Key Dimensions of Primary Loop Component name Length (m) Flow Area (m2) Hydraulic diameter (m) Inlet duct Downcomer Inlet plenum Distribution Plate Bottom reflector Core Top reflector Outlet plenum Outlet duct 3.0 3.8 1.0 0.3 1.0 1.95 1.0 3.5 3.0 3.90 5.50 12.57 3.0 1.41 1.41 1.41 12.57 0.50 1.3650 0.6000 4.0000 0.7000 0.0127 0.0127 0.0127 4.0000 0.8000 3.2 GFR Methology for Selection of Optimum Parameters IHX dimensions depend on core flow rate and inlet and outlet temperatures, hence they need to be reoptimized during calculations. A HEATRICTM type IHX was used with straight channels and semi-circular channel diameter of 2mm (channel pitch and plate thickness were determined from 1D stress analysis). The IHX inlet and outlet temperatures on the CO2 side were used from the optimized cycle designs in Table 2. Note that for the selected turbine inlet tempera- tures of 550 and 650°C the IHX inlet temperatures are determined by the SCO2 cycle thermodynamics. In the search process for the optimum reactor inlet and outlet temperatures a wide range of possible IHX temperatures was considered. For every set of inlet and outlet temperatures the IHX was sized and the pressure drops on both helium and CO2 sides were calculated. Using the calculated IHX CO2 pressure drop, p IHX, the new cycle efficiency was calculated from the relation = 0-0.002 p IHX (see Section 2.1). Next, the required pumping power was determined based on the calculated pressure drop around the primary loop. Note that the circulator pumping power is converted ultimately to heat added to the primary system, hence the reactor thermal power, which enters efficiency calculations, will be reduced for fixed total power. The indirect cycle efficiency is calculated by dividing net electric power by reactor thermal power, where the net electric power is the cycle electric power minus the electric pumping power). This efficiency is then used for the specific cost calculations. The cost of the IHX is calculated based on its weight using cost of 30 $/kg for stainless steel HEATRICTM heat exchangers [17]. The cost of the circulator is scaled based on the pumping power requirements and the IHX vessel cost is scaled based on the IHX volume. The baseline cost data for these components ($17,421,051 for circulator and $11,224,237 for IHX vessel in 1992$) were taken from General Atomics cost estimates for 450MWth Modular High-Temperature Gas-cooled reactors [18]. These costs were scaled with respect to differences in power rating and volume and adjusted for inflation. The reference direct cycle plant cost was assumed to be 1000$/kWe – a target for new nuclear power plants in deregulated electricity market. More details of the economic assessment are given in Ref. 13. Sizing of the IHX was based on detailed heat transfer calculations using 30 axial nodes. In addition, a simplified 1-D stress analysis was also performed to determine the plate thickness and channel pitch necessary to withstand the pressure difference between the SCO2 side (20MPa) and the helium side (7MPa). At elevated temperatures, creep becomes the primary mechanism of concern for stress analysis, because it limits IHX lifetime. The prime currently available structural material for high temperature reactors, alloy 800, was used for the basic design. It is noted that the longest time to creep-driven rupture available for this material is 105 hours, which constitutes an IHX lifetime of about 12 years. This is a relatively short lifetime so a better material with higher stress rupture strength will have to be developed if a 30 year lifetime is specified, to reduce the number of replacements during a 60-year plant life. For the advanced SCO2 design, it becomes very difficult to design the IHX even with a lifetime of 10 years because of the low allowable stress rupture strength of Alloy 800 at higher temperatures (IHX helium inlet temperatures of 800°C would be needed). Therefore, the calculations HEJZLARetal., AssessmentofGasCooledFastReactorwithIndirectSupercriticalCO2Cycle NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.38 NO.2 SPECIAL ISSUE ON ICAPP ‘05 113

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