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chemical reaction with water or air in the event of coolant leakage. In the indirect cycle,10 the intermediate Na loop can be eliminated because the Na-CO2 reaction is anticipated to be much milder than the Na-water (H2O) reaction; furthermore, no extra gas (hydrogen in the Na-H2O reaction) or corrosive reaction product (sodium hydroxide in the Na-H2O reaction) is produced. The core volume is about 1/5 that of the direct cycle because Na provides more efficient heat transfer performance and a tighter fuel pin lattice than CO2. The Na-core-cooled indirect cycle inherits extensive research and development results on designs, mockup tests for thermal-hydraulics and safety, material tests, operation, and maintenance obtained for and from Joyo and Monju. This indirect cycle eliminates safety problems that are peculiar to the Na-H2O reaction, thereby simplifying the heat transport system, reducing the turbine size, and simplifying plant maintenance. is transmuted to 239Pu after two neutron-capture reactions 237 (*) (*) PUMP HX Overpressure Relief Valves Isolation V alves Generator RV #1 RD #2 RD a) Direct Cycle System Therefore, 237Np functions mainly as a neutron absorber in the early stage and as a fissile material in the latter stage. Because of this burnable poison effect of 237Np, the burnup reactivity loss is reduced. In the direct cycle core, the burnup reactivity loss is almost zero, 0.02% ∆k/k, during ten years when 237Np is added by 6.5 weight percent to the fuel, whereas the maximum reactivity swing is 0.14% ∆k/k. After ten-year burning, all core fuel and the blanket fuel are discharged and fresh fuel is loaded. The burnup reactivity loss in the Na- cooled core is 2.02% ∆k/k when 237Np is added by 10 weight percent into the fuel and three-batch refueling with a one-year cycle length is applied. Zero burnup reactivity loss can be attained if 237Np is added by more than 20 weight percent. However, because it is desirable for void reactivity in a Na-cooled core that it be less than 5 $ from the perspective of accident management control, the 237Np content in the Na-cooled core was limited to 10% and the effective core height was shortened to 0.8 m. The 237Np burning rate is about 69 kg·yr-1 in the S- CO2 cooled core and about 74 kg·yr-1 in the Na-cooled core. The total amounts of MAs discharged from one LWR of 1000 MWe are about 24 and 34 kg, respectively, when the spent fuel is reprocessed after cooling of 3 years and 10 years. Because 237Np comprises about 60% and 40% of the MAs, after cooling of 3 years and 10 years, respectively, it is a principal long-life radioactive waste in MA. The 237Np burn rates in the core are equivalent to the quantity produced from about 20 LWRs of the same electrical output. The low burnup reactivity greatly reduces control rod worth requirements for primary rods. Seven primary control rods offer a sufficient shutdown margin under a one-rod-stuck condition for the S-CO2 and the Na-cooled cores, although three backup control rods also provide a sufficient shutdown margin. As a case in contrast, Monju, with electrical output of 280 MWe, has 13 primary rods and 6 backup rods. The control rods are reduced to half those used for Monju. Rod withdrawal operations with burnup time to compensate the reactivity loss are almost unnecessary in the S-CO2-cooled core. Moreover, the excess reactivity is minimized so that the core can be kept near critical under consideration of the reactivity uncertainty. Primary rods are withdrawn from the core during the operation and reactivity insertion imparted by rod withdrawal is very small. The lower excess reactivity the Na-cooled core relative to the Monju core reduces b) Indirect Cycle System Fig. 7 Flow diagrams of direct and indirect cycle III.C. Core Performance In the S-CO2 FR direct cycle and indirect cycle cores, Np is added to reduce the burnup reactivity loss, which 4 via 238Pu as follows: 11 237Np Absorber (n, γ) 238Pu β , 2.1 d α , 87 y 234U Fertile (n, γ) (n, γ) 239Pu 235U FissilePDF Image | ADVANCED ENERGY SYSTEM WITH NUCLEAR REACTORS
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