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Other burnup analyses were performed using the same basic reactor geometry but with a pin diameter of 1.20 cm and a 0.3 cf. This configuration has approximately the same fuel density as for the 0.75 cm pin diameter and 0.2 cf. The results are not included in this report but are found to be very similar to those presented in Figures 19 to 21. The results of the burnup analyses show that a long-life core can be made feasible with an initial core loading of 12% enriched UO2. The reactivity change over the lifetime can be maintained within ~$1.00 of reactivity. Further analyses are required to more accurately maintain the three- dimensional inventory by zone loading the core. 6.2 Delayed Neutron Fraction and Void Worth The burnup calculations were performed with the reactor temperature at conditions representing full power operation. Additional MCNP calculations were performed at cold, room temperature conditions to determine the startup reactivity requirements. The cold reactor keff was found to be larger than the hot condition by k/k = 0.00956 ± 0.0015, or about +$1.20 of reactivity. Further, the neutron lifetime of the reactor was found to be 41.4 s. Future work will include an in-depth analysis to determine the temperature coefficient of reactivity for the fuel and coolant. MCNP calculations were also performed to determine the delayed neutron fraction () and the void reactivity worth of the core over the core lifetime. The results are shown in Table 5. The values for are based on the U-235, U-238, and Pu-238 values given in Lewins (1978) for fast fission. The results were determined by multiplying each fissile constituent by the normalized fraction of fissions for that constituent. The results do not include the effectiveness factor, which would increase the values somewhat, due to the importance of the delayed neutrons at the center region of the core. Future work will include a determination of the effectiveness factor for the core. A beginning of life (BOL) value for of 0.008 is calculated. This value is greater than the U-235 value due to a relatively large number of U-238 fissions that occur in a fast reactor. This value decreases over the lifetime of the core due to the increased inventory of Pu-239. The end of life (EOL) value for of 0.0062 for 200 MWth and 0.0052 for 400 MWth is calculated. These values are significantly smaller than for the BOL value. Void reactivity worth was calculated by changing the density of the CO2 coolant in the reactor from a value at 20 MPa (3000 psia) to a value at 0.1 MPa (14.7 psia), a factor of 200. The results are shown in Table 5 for the 0.75 cm pin 0.2 cf case, and for the 1.20 cm pin 0.3 cf case. Calculations were performed for BOL and EOL for 200 MWth and 400 MWth. Although there is significant uncertainty in the results (±~$0.25), they indicate that the voiding is positive but small – less than +$1.00. Since the only way that voiding could occur in the reactor core is by a depressurization of the system, this reactivity effect is considered to be manageable by inserting the control and safety rods. It would be expected to take several minutes to depressurize the core in the event of a small pipe break. Smaller reactor configurations have been shown to have negative void reactivity worth, due to the higher neutron leakage from the core. Future work will include more accurate analysis of the void worth. Further accident analysis will provide more information on the effects of having a positive void worth on the safety of the system. 38PDF Image | Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR)
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