Development of hybrid reprocessing technology based on solvent extraction and pyro-chemical electrolysis

Ohmura, Hideki; Mizuguchi, Koji; Kanamura, Shohei; Ohsato, Tetsuo; Fujita, Reiko; Omori, Takashi; Utsunomiya, Kazuhiro

doi:10.1016/j.pnucene.2011.05.033

Cited by 3 publications

(1 citation statement)

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“…Namely, the technology of the Pyro-SFR nuclear fuel cycle is one of the alternatives that can fundamentally solve the problem of spent fuel management and is known to be an advanced technology with high proliferation resistance [2].…”

Section: Introductionmentioning

confidence: 99%

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

Kim

Lee

2013

Science and Technology of Nuclear Installations

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This paper evaluates whether SFR metallic nuclear fuel can be economical. To make this determination, the cost of SFCF (SFR fuel cycle facilities) was estimated, and the break-even point of the manufacturing cost of SFR metallic nuclear fuel for direct disposal option was then calculated. As a result of the cost estimation, the levelized unit cost (LUC) for SFCF was calculated to be 5,311 $/kgHM, and the break-even point was calculated to be $5,267/kgHM. Therefore, the cost difference between LUC and the break-even point is not only small but is also within the relevant range of the uncertainty level of Class 3 in accordance with a generic cost estimate classification matrix of AACE (the Association for the Advancement of Cost Engineering). This means it is very difficult to judge the economical feasibility of SFR metallic nuclear fuel because as of today there are no commercial facilities in Korea or the world. The economic feasibility of SFR metallic nuclear fuel, however, will be enhanced if the mass production of SFCF becomes possible in the future.

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Section: Introductionmentioning

confidence: 99%

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

Kim

Lee

2013

Science and Technology of Nuclear Installations

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The coprecipitation and conversion of mixed actinide oxalates for aqueous-based reprocessing of spent nuclear fuels

Sarsfield¹

2015

Reprocessing and Recycling of Spent Nuclear Fuel

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The Electrolytic Reduction of Gd₂O₃ in LiCl-KCl-Li₂O Molten Salt

Zhu

Peng

et al. 2021

J. Electrochem. Soc.

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In the common spent fuels, actinides and fission products are generally in the form of oxide, so direct dealing with oxide will be the most convenient way for spent fuel reprocessing. In this work, the electrolytic reduction of Gd2O3 has been studied in LiCl-KCl-Li2O (1 wt%) melts at different conditions, and the effect of sintering temperature on the porosity of Gd2O3 powder and the electrochemical behavior of Li2O in LiCl-KCl molten salt were investigated, too. The diffusion coefficient of O2− was calculated to be 2.0 × 10−5 cm2·s−1 in LiCl-KCl melts on the Mo electrode at 923 K by cyclic voltammetry (CV). The electrode process of Gd2O3 powder was also analyzed in LiCl-KCl-Li2O (1 wt%) melts, and the formation process of composite oxide LiGdO2 was determined. By the analysis of XRD and oxygen content characterization, it was suggested that after 74 h electrolysis (923 K, 3.40 V), the oxygen content of Gd2O3 cathode decreased from 12.25 wt% to 1.41 wt%, indicating 88.5% Gd2O3 was reduced to metal.

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Development of hybrid reprocessing technology based on solvent extraction and pyro-chemical electrolysis

Cited by 3 publications

References 6 publications

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

The coprecipitation and conversion of mixed actinide oxalates for aqueous-based reprocessing of spent nuclear fuels

The Electrolytic Reduction of Gd₂O₃ in LiCl-KCl-Li₂O Molten Salt

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Development of hybrid reprocessing technology based on solvent extraction and pyro-chemical electrolysis

Cited by 3 publications

References 6 publications

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

The coprecipitation and conversion of mixed actinide oxalates for aqueous-based reprocessing of spent nuclear fuels

The Electrolytic Reduction of Gd2O3 in LiCl-KCl-Li2O Molten Salt

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The Electrolytic Reduction of Gd₂O₃ in LiCl-KCl-Li₂O Molten Salt