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6. Neutronic Analysis Neutronic analyses were performed using the Monte Carlo N-Particle code Version 5 (MCNP, 2003) and the ENDF/B-VI cross sections included in the distribution. K effective (keff), burnup, and void reactivity worth calculations were performed using the three-dimensional model of the core shown in Figure 3 and the baseline parameters in Tables 3 and 4. The calculations were performed with the fuel cross sections at 1200 K. Scoping keff and burnup analyses were iterated with the flow analysis to determine the appropriate fuel-pin size, coolant fraction, enrichment, reactor size, and reflector thickness. The goal was to determine if a reasonably-sized reactor could be configured that would have only a small change in reactivity over the desired 20-year operating life as the U-235 is consumed and the fissile Pu-239 is produced from the neutron absorption of U-238. 6.1 Burnup Analyses Burnup analyses were performed using the burnup code BURNCAL (Parma, 2002). BURNCAL uses MCNP to perform the neutronic analysis and calculates the fuel inventory, including the fission product, activation product, and transuranic inventory, using the MCNP tally results. Calculations are performed for a time-at-power history defined in an input file. It is important to note that the results presented represent scoping calculations performed using a single reactor zone. Thus the inventory calculated over the time history represents the core average values and not the true three-dimensional representation. Future calculations will include zoned core configurations to more accurately represent the core inventory. In order to determine the appropriate enrichment range for a long-life reactor core, initial burnup calculations were performed for an infinite reactor system. To perform this analysis, a fuel pin was modeled with coolant in a hexagonal geometry. Specular reflector boundary conditions were identified in the MCNP model that allow for the simulation of an infinite reactor. UO2 fuel was used with stainless-steel cladding. CO2 coolant at a pressure of 20 MPa and 0.2 cf was modeled. The results are shown in Figure 17 for an operating history of seventeen years and a power density of 50 MWth/MTU. Calculations were performed for enrichments of 5%, 10%, 12.5%, and 20%. The results show that a long-term burnup is achievable for an infinite reactor with an enrichment of greater than 5%. An infinite reactor with an enrichment of 5% cannot be made critical. At an enrichment of 12.5%, the infinite reactor value of the multiplication constant stays almost constant over the entire seventeen years of burnup. The initial value of k- infinity is about 1.25, which allows for some leakage margin in a finite reactor configuration. The question is whether a finite reactor can be configured with a reasonable size and for ~12.5% enriched fuel. A core could be configured with a higher enrichment value, up to 20%. However, many dollars of negative reactivity would be required in the form of burnable poisons, control rods, or other removable poisons to maintain a critical condition over the operating history. Figure 18 shows the burnup results for a 200 MWth, 12.5% enriched UO2 fuel pin, 0.75 cm in diameter, 0.2 cf, core radius of 0.75 m, active fuel height of 1.4 m, and a Ni reflector 25 cm in thickness. The core was sized to have an initial keff value of greater than one. 250,000 particle histories were run for each time point resulting in a statistical uncertainty in keff of ~0.001 (~$0.12 of reactivity). The error bars are included within each data point. 34PDF Image | Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR)
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