Concept of breed and burn reactor with spiral fuel shuffling

Kuwagaki, Kazuki; Nishiyama, Jun; Obara, Toru

doi:10.1016/j.anucene.2018.12.006

Cited by 14 publications

(2 citation statements)

References 14 publications

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“…Nitride fuel ( 15 N) as the fuel could increase the k‐eff and reduce the production of 14 C due to 14 N (n,p) 14 C reaction 9‐11 . The High‐Cr martensitic steel HT9 was employed as a cladding material because of its high resistance to neutron irradiation 12,13 …”

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%

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

et al. 2021

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“…[12]. The cladding material is High-Cr martensitic steel, HT9, then high-dose neutron exposure can be resisted [28,29]. As a coolant, we selected 208 Pb-bi eutectic to improve reactor performance [18,30].…”

Section: Reactor Materials and Designmentioning

confidence: 99%

Neutronic performance of ²⁰⁸Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched ¹⁵N)

Widiawati,

Suud

2024

J. Phys.: Conf. Ser.

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Fast reactors (FRs) require more uranium enrichment than LWRs and fuel reprocessing. The solution proposed to address these issues is to use the modified CANDLE burnup scheme on the reactor core. The use of uranium nitride (UN) as fuel was proposed because the UN fuel has several advantages, such as high melting point, high heavy metal density, and large thermal conductivity. However, using UN as a fuel can produce the radioactive isotope 14C via the reaction 14N (n, p)14C. Therefore, in this study, a neutronic analysis was performed in a modified CANDLE fast reactor employing UN and UN (enriched 15N) as fuel using SRAC. The modified CANDLE fast reactor fuelled with UN (99% 15N) has a higher keff than the UN-fuelled reactor with similar parameters. Similarly, the atomic density of fissile nuclides and power density are higher because the 15N isotope has a smaller neutron capture cross-section than the 14N isotope.

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Introduction to Breed and Burn Reactors

Qvist¹

2021

Encyclopedia of Nuclear Energy

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Concept of breed and burn reactor with spiral fuel shuffling

Cited by 14 publications

References 14 publications

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

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

Neutronic performance of ²⁰⁸Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched ¹⁵N)

Introduction to Breed and Burn Reactors

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Concept of breed and burn reactor with spiral fuel shuffling

Cited by 14 publications

References 14 publications

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

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

Neutronic performance of 208Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched 15N)

Introduction to Breed and Burn Reactors

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Neutronic performance of ²⁰⁸Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched ¹⁵N)