Plutonium isotopic composition of high burnup spent fuel discharged from light water reactors

Nakano, Yoshikatsu; Ōkubo, Tsutomu

doi:10.1016/j.anucene.2011.08.009

Cited by 13 publications

(1 citation statement)

References 2 publications

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“…However, the plutonium from natural uranium burnup is not available at this time. Therefore, the plutonium originates from APWR used fuel with 49 GWd/t of burnup and 5 years of cooling time 22 . Table 2 shows the Pu isotope vector.…”

Section: Methodsmentioning

confidence: 99%

Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling

et al. 2021

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Summary Natural uranium is utilized in a small percentage by the Light Water Reactor (LWR) and also by the once‐through Fast Breeder Reactor. One of the reactor designs that can increase the natural uranium utilization is the MCANDLE (Modified Constant Axial shape of Neutron flux, nuclides densities, and power shape During Life of Energy production) reactor. The scheme divides the core into several discrete regions. The modified CANDLE reactor will only need natural uranium as fuel input after reaching quasi‐equilibrium conditions. In this study, We used a core with certain Plutonium (Pu) composition in each region as a startup core. Initially, the Pu content in each region imitates that of the reactor core at the quasi‐equilibrium state. We calculated the neutronics of the initial core by the SRAC that stands for Standard Reactor Analysis Code System and used JENDL 4.0 as a nuclear data library. Plutonium (Pu) from LWR spent fuel was utilized as the initial reactor fuel. However, excess reactivity is more than 10%. It is because there are no other fission products. Therefore, we replace other fission products with a reduction in the volume of fuel cells. The volume reduction was adjusted to the level of burnup in each region at the quasi‐equilibrium condition. Hence, there are differences in the volume reduction ratio for each fuel cell. The method can reduce excess reactivity to 5%. The reduction of the volume of fuel cells can also reduce the amount of plutonium as the initial fuel for the reactor core. Also, the spent fuel burnup is 48% FIMA. The design could increase the utilization of natural uranium without an enrichment process.

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Section: Methodsmentioning

confidence: 99%