Design study of 208Pb-Bi eutectic-cooled reactor with natural uranium as fuel cycle input with radial fuel shuffling

Widiawati, Nina; Su’ud, Zaki; Irwanto, Dwi; Permana, Sidik; Takaki, Naoyuki; Sekimoto, Hiroshi

doi:10.1016/j.anucene.2022.109003

Cited by 4 publications

(3 citation statements)

References 25 publications

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“…Table 1 presents the reactor design parameters. The pancake-type core was selected to minimize the axial load from severe heat flow [15], [16]. Figure 2 shows the reactor core design (c) and the fuel cell design (d).…”

Section: Reactor Descriptionmentioning

confidence: 99%

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

Ndayiragije,

Su’ud,

Waris

2024

J. Phys.: Conf. Ser.

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The Modified CANDLE (MCANDLE) burnup scheme divides the reactor core into several regions in an axial or radial direction with equal volume. It works like the CANDLE burnup scheme except that, in the CANDLE burnup scheme, the reactor core is divided into three main regions in the axial direction. Namely, spent fuel, burning region and fresh fuel region. In this study, the design of a modular modified CANDLE fast reactor using helium gas as a coolant has been performed. One of the important roles of a modified CANDLE fast reactor is that it can utilize natural uranium as fuel without the need for enrichment or reprocessing. This type of reactor can be used, including in developing countries, without the nuclear proliferation problem. Using helium gas as a coolant gives hope for a fast reactor due to its properties, such as its less neutron absorption, less radioactive, and as helium is an inert gas, prevents chemical reactions with other materials. The study was performed on a rector with a thermal power of 450MWth. The active core was divided into ten regions with equal volume in radial directions. The refueling scheme has been optimized every ten years of burnup to obtain a good reactor design. In the beginning, the fuel was put in the first region after ten years of burnup was moved to the second region, after another ten years of burnup was moved to the third region and so on until the tenth region where the fuel gets out. The neutronic calculation has been performed using the SRAC (Standard Reactor Analysis Code system). The collision probability method (PIJ) was employed for cell burnup calculation, and CITATION was used for the reactor core design with JENDL 4.0 as the nuclear data library.

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Section: Reactor Descriptionmentioning

confidence: 99%

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

Ndayiragije,

Su’ud,

Waris

2024

J. Phys.: Conf. Ser.

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“…Furthermore, it can also harden the neutron spectrum [18,23,31]. Another advantage of this coolant material is that it has a higher level of safety than natural lead, especially since the margin between melting and boiling points is larger [13]. Other parameters are from the results of previous optimal calculations.…”

Section: Reactor Materials and Designmentioning

confidence: 99%

“…As a result, natural uranium is located next to the fuel with a high burnup level. The goal is to compensate for the reduction in reactivity during the operation time [13,32].…”

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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Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material

Widiawati,

Trianti,

Luthfi

et al. 2025

Annals of Nuclear Energy

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Design study of 208Pb-Bi eutectic-cooled reactor with natural uranium as fuel cycle input with radial fuel shuffling

Cited by 4 publications

References 25 publications

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

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

Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material

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Design study of 208Pb-Bi eutectic-cooled reactor with natural uranium as fuel cycle input with radial fuel shuffling

Cited by 4 publications

References 25 publications

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

Design study of a 450MW thermal Modified CANDLE fast reactor using helium gas as a coolant

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

Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material

Contact Info

Product

Resources

About

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