Low-power lead-cooled fast reactor loaded with MOX-fuel

Sitdikov, E R; Terekhova, Anna

doi:10.1088/1742-6596/781/1/012007

Cited by 1 publication

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“…The results show that the combination of MOX fuel and Pb-208 has better performance than that of MOX fuel and natural lead coolant. When MOX fuel is combined with Pb-208, the core has a larger initial keff so that the fuel loading can be reduced [15]. You-Peng Zhang et al studied the effect of axial swelling of fuel on core safety.…”

Section: Introductionmentioning

confidence: 99%

Study on Fuel Selection for a Long-Life Small Lead-Based Reactor

et al. 2022

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The choice of an appropriate fuel can effectively prolong the refueling cycle of a reactor core. The Th-U cycle and U-Pu cycle are commonly used fuel breeding cycles. Oxide fuels, nitride fuels, and metal fuels are the primary candidate fuels for lead-based reactors. For fuel selection, a core model of a 60 MWt reactor was established. The results show that the breeding performance of the breeding fuel Th-232 is better than that of U-238, and the driving performance of the driving fuel Pu-239 is better than that of U-235. Therefore, PuO2-ThO2, PuN-ThN, and Pu-Th-Zr fuels may have good performance. By comparing the reactivity loss of three types of fuel, it was found that the reactivity loss of PuN-ThN fuel is the smallest. Hence, using PuN-ThN fuel as a core fuel can result in a longer refueling cycle. On this basis, PuN-ThN fuel was used in the preliminary design of the 120 MWt core physical model. It can be seen that when PuN-ThN fuel is used as the core fuel, a smaller reactivity swing (1408 pcm), smaller power peak factor, and super long refueling cycle (more than 30 years) can be obtained.

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Section: Introductionmentioning

confidence: 99%