An Electrochemical Reduction of Uranium Oxide in the Advanced Spent-Fuel Conditioning Process

Jeong, Sang Mun; Hur, Jin‐Mok; Hong, Sun; Kang, Dae Seung; Choung, Myoung Soo; Seo, Sang‐Woo; Yoon, Ji Sup; Park, Seong-Won

doi:10.13182/nt162-184

Cited by 31 publications

(11 citation statements)

References 12 publications

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“…To supply metal fuel materials to FBRs, the oxide fuels of current light water reactors (LWRs) must be reduced to metals, and an electrolytic reduction technique has recently been developed for this purpose [4][5][6][7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Effect of alkali and alkaline-earth chloride addition on electrolytic reduction of UO2 in LiCl salt bath

Sakamura

2011

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Effect of alkali and alkaline-earth chloride addition on electrolytic reduction of UO2 in LiCl salt bath

Sakamura

2011

Journal of Nuclear Materials

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“…The loaded oxide fuel can have various physical forms, for example, rods, crushed particles, powder, and porous granules 19‐23 . In addition, various states of oxidized uranium are used, that is, both UO 2 and U 3 O 8 24,25 .…”

Section: Process Of Electrolytic Recovery Of Snfmentioning

confidence: 99%

“…The loaded oxide fuel can have various physical forms, for example, rods, crushed particles, powder, and porous granules. [19][20][21][22][23] In addition, various states of oxidized uranium are used, that is, both UO 2 and U 3 O 8 . 24,25 On the basis of X-ray structural analysis, it was shown that intermediate compounds such as LiUO 3 , U 4 O 9 , and UO 2 can be formed in the initial stage of processing.…”

Section: Electrochemical Processing Of Snfsmentioning

confidence: 99%

Recoveryof actinidesand fission products from spent nuclear fuel via electrolytic reduction: Thematic overview

Галашев

2021

Intl J of Energy Research

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Summary Spent nuclear fuel (SNF) from modern light water or thermal reactors containing uranium oxide with small concentrations of plutonium and other actinide oxides is converted into metal by the electrolytic reduction. The obtained metal must be subjected to further processing (electrorefining). This review reflects the achievements in development SNF electrolytic processing, concepts of the technological operations, and a model describing the electrochemical process. The technological scheme for the electrochemical reduction of SNF and MOX fuel is considered. The complexity of a carbon anode application in the process of UO2 electrolytic reduction is reflected. The reduction processes of alkali, alkaline earth (AE), and rare earth metal oxides as well as oxide compounds of zirconium are demonstrated. The reduction of lanthanum oxide and oxy‐chloride to the metallic form by adding metallic nickel to the molten salt is discussed. The solubility of Li2O in molten salts is interpreted depending on the amount of dissolved alkali and AE metal chlorides. The considered pyroprocessing technology enables a much greater release of the energy accumulated in uranium ore, and recycling all actinides allows reducing significantly the amount of nuclear waste and the time it must be isolated.

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“…Uranium oxides of shapes, such as powder and crushed pellets, were tested for the oxide reduction process [4][5][6]. Although U3O8 powder has advantages in terms of current efficiency, it is difficult to handle and requires a well designed cathode basket [4,5]. The current efficiency of crushed pellets was lower than that of U3O8 powder [6].…”

Section: Oxide Feed Fabrication Processmentioning

confidence: 99%

Pyroprocessing Technology Development at Kaeri

Lee¹,

Park²,

Kang³

et al. 2011

Nuclear Engineering and Technology

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234

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An Electrochemical Reduction of Uranium Oxide in the Advanced Spent-Fuel Conditioning Process

Cited by 31 publications

References 12 publications

Effect of alkali and alkaline-earth chloride addition on electrolytic reduction of UO2 in LiCl salt bath

Effect of alkali and alkaline-earth chloride addition on electrolytic reduction of UO2 in LiCl salt bath

Recoveryof actinidesand fission products from spent nuclear fuel via electrolytic reduction: Thematic overview

Pyroprocessing Technology Development at Kaeri

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