Application of melt and refining procedures in the CANDLE reactor concept

Karim, Julia Abdul; Nishiyama, Jun; Obara, Toru

doi:10.1016/j.anucene.2015.12.001

Cited by 14 publications

(3 citation statements)

References 13 publications

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“…Once applying the control assemblies for the reactor, it would have an effect on the criticality of the cores with a rotationalfuel-shuffling scheme. However, it was mentioned in the previous studies [19][20][21] that the excess reactivity would be increased by applying the melt-refining process because of FP removal during the reprocessing. Therefore, it was expected that criticality would be ensured throughout the cycle for the melt-refining core designed with the control systems.…”

Section: Ivc Characteristics Of the Equilibrium Cyclementioning

confidence: 99%

“…To reduce the maximum dpa value, the fuel cycle length of operation should be decreased or fuel reprocessing, such as the melt-refining process, should be applied. [19][20][21] These changes would result in an altered equilibrium state. Therefore, further analyses and optimizations for a practical reactor design must be performed in a future work.…”

Section: Ivc Characteristics Of the Equilibrium Cyclementioning

confidence: 99%

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Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

Hoang

Sambuu

Nishiyama

et al. 2021

Nuclear Science and Engineering

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The objective of the present study is to show that it is feasible to establish the breed-and-burn (B&B) mode of operation with rotational fuel shuffling in the S-PRISM core based on neutronic and thermal-hydraulic analyses. The results quantified the impact of major core design choices on the criticality of a core that uses sodium as a coolant material and HT9 steel as structural material. The design variables examined include the binary metallic fuel U-Zr with different weight percentages of zirconium as well as different core heights and fuel rod pitchto-diameter ratios (P/Ds) in the fuel assembly. We found that a core using the binary metallic fuel U-Zr with 2 wt% zirconium, with a core height of 200 cm, a P/D of 1.086, and a core power of 400 MW(thermal), could overcome some major design constraints.It was also found that with shuffling intervals of 1125 to 1250 days, the core with rotational fuel shuffling was critical in the equilibrium state, and the possible average discharged burnup was from 274.8 to 305.3 GWd/ton HM. Reactor characteristics such as neutron flux and power profile were almost stable during the equilibrium cycle. A steady-state thermal-hydraulic analysis was performed for the hottest channel in the core. It revealed that both the fuel and cladding maximum temperatures were less than the melting point of the fuel and the chemical interaction temperature of the HT-9, respectively. The mixed coolant outlet temperature was somewhat below the temperature usually observed in sodium-cooled fast reactors. Thus, it appears that the S-PRISM can be principally designed to have a B&B core.

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Section: Ivc Characteristics Of the Equilibrium Cyclementioning

confidence: 99%

Section: Ivc Characteristics Of the Equilibrium Cyclementioning

confidence: 99%

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

Hoang

Sambuu

Nishiyama

et al. 2021

Nuclear Science and Engineering

Self Cite

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show abstract

“…The main features of this concept are: Sub‐cycle length: It is not mentioned in the consulted references, but assuming the refueling strategy, the sub‐cycle length would be the same as the time between refueling. Full core life: It would depend on the number of refueling, but because structural material and other components would have to remain in the core for the whole cycle life, the life length would be restricted by their integrity and not by neutronics. Power of the proposed reference core: The proposed core mentioned here is a medium‐sized core of 1540 MWt; nevertheless, other references consider a big‐sized 3000 MW t core and even a small 30 MW t size core Fuel and coolant: Various types of fuels have been proposed such as metallic, nitride, and even TRISO.…”

Section: Types Of Breed/burn Reactor Coresmentioning

confidence: 99%

The breed and burn nuclear reactor: A chronological, conceptual, and technological review

Lopez-Solis

François

2017

Int J Energy Res

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Summary Currently about 11% of the world's energy is produced in nuclear power plants; this implies the processing of uranium in order to enrich it to be suitable for “burning” in a nuclear reactor. Besides other environmental and monetary costs involved in the whole nuclear fuel cycle, the enrichment process has the disadvantage of producing depleted uranium as a sub‐product that has no wide use and is essentially stockpiled. One strategy to deal with this issue is to design a nuclear reactor that can run mostly on depleted uranium by breeding its own fissile fuel from it. Even though this concept could sound innovative or new, the truth is that it has been in the thought of the nuclear engineers since the 50s. In the present paper, the breed & burn (B&B) reactor concept is reviewed, as well as its origins, evolution up to present, and its main technical features. The objectives of this review are as follows: (1) to summarize the history of the development of B&B reactors, (2) to compare different B&B concepts based on a systematic approach under selected technical features, and (3) to bring out current trends and future directions on this technology. It is expected that this review will help the nuclear engineering community in general, and newcomer researchers in the field, to get an overview about the B&B reactors and how to direct a research in this direction.

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CANDLE Reactor Concept

Sekimoto

2021

Encyclopedia of Nuclear Energy

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Application of melt and refining procedures in the CANDLE reactor concept

Cited by 14 publications

References 13 publications

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

The breed and burn nuclear reactor: A chronological, conceptual, and technological review

CANDLE Reactor Concept

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