Electrodeposition characteristics of uranium by using a graphite cathode

Kang, Young Hwan; Lee, Sang-Kwon; Hwang, Sung Chan; Shim, Joon-Bo; Kim, E.H.; Park, S.W.

doi:10.1016/j.carbon.2006.05.026

Cited by 19 publications

(6 citation statements)

References 9 publications

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“…Electrorefining experiments of uranium were successfully carried out in the LiCl-KCl eutectic molten salt at 500 • C with a graphite cathode. The formation of U-graphite intercalation compound (GIC) helped the self-scraping mechanism of uranium dendrite [111]. Also uranium deposits were prepared by the electrolysis in a fused chloride melt (NaCl-KCl) at 670-710 • C [112].…”

Section: Groupmentioning

confidence: 99%

Electrodeposition of metals from non-aqueous solutions

Simka

Puszczyk

Nawrat

2009

Electrochimica Acta

271

154

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Section: Groupmentioning

confidence: 99%

Electrodeposition of metals from non-aqueous solutions

Simka

Puszczyk

Nawrat

2009

Electrochimica Acta

271

154

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“…In order to increase a throughput of electrorefiner, KAERI has developed the advanced high-throughput electrorefiner by employing a graphite cathode. The self-scraping mechanism of graphite cathode increases the efficiency of the electrorefiner due to an elimination of the stripping step [3]. In addition, continuous operation of the advanced electrorefiner can be realized by adding a bucket-type deposit transfer system.…”

Section: Electrorefinermentioning

confidence: 99%

“…SAP wasteform ZIT wasteform Radionuclide leach rate, g/m 2 day 10 −4 ∼10 −3 for Cs/Sr <10 −5 for rare earth Wasteform leach rate, g/m 2 day 10 −2 10 −3 Density, g/cm 3 2.35∼2.40 3.7∼4.2 Thermal conductivity, W/mK 1.1∼1.4 1.7 Thermal capacity, J/gK 0.96∼1.07 0.65 Glass transition temperature, K 753∼800 -Thermal expansion coefficient, K −1 3.0 × 10 −6 Microhardness, GPa 4.76 ± 0.15 5.5 been tested successfully. PRIDE facility has been constructed at KAERI and advanced technologies in engineering-scale are planned to be demonstrated in PRIDE.…”

Section: Propertymentioning

confidence: 99%

Current Status of Pyroprocessing Development at KAERI

Lee

Park

Lee

et al. 2013

Science and Technology of Nuclear Installations

104

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Pyroprocessing technology has been actively developed at Korea Atomic Energy Research Institute (KAERI) to meet the necessity of addressing spent fuel management issue. This technology has advantages over aqueous process such as less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, and compact equipments. This paper describes the pyroprocessing technology development at KAERI from head-end process to waste treatment. The unit process with various scales has been tested to produce the design data associated with scale-up. Pyroprocess integrated inactive demonstration facility (PRIDE) was constructed at KAERI and it began test operation in 2012. The purpose of PRIDE is to test the process regarding unit process performance, remote operation of equipments, integration of unit processes, scale-up of process, process monitoring, argon environment system operation, and safeguards-related activities. The test of PRIDE will be promising for further pyroprocessing technology development.

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“…A prototype Gen IV sodium‐cooled fast reactor (PGSFR) is being developed in combination with the pyro‐electrochemical processing of spent fuel at KAERI . It can resolve the issue of the accumulation of PWR (pressurized water reactor) spent fuels and can increase the utilization of uranium resources while maintaining higher proliferation resistance . U‐Zr and U‐TRU‐RE‐Zr metal fuels have been considered as the driver fuels for SFR in Korea .…”

Section: Introductionmentioning

confidence: 99%

Ceramic plasma‐spray‐coated graphite crucible for injection casting of fast reactor fuel slugs

Kim

Hong

Kim

et al. 2018

Int J Applied Ceramic Tech

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Ceramic plasma-spray coatings with single and multiple layers have been applied to melting crucible material substrates for the development of a reusable crucible for the fabrication of metal fuel slugs for a sodium-cooled fast reactor (SFR). Various combinations of vacuum plasma-spray (VPS) coated specimens have been applied to investigate the bonding effect on the crucible substrate and the interaction between the metal fuel and the VPS-coated crucible substrate. All VPS-coated methods maintained a sound coating state after a dipping test with U-10 wt%Zr melt. A single coating of a Y 2 O 3 (150) layer and a double coating layer of TaC(50)-Y 2 O 3 (100) showed some degradation or penetration, respectively, after 2 cycles of dipping test with an aggressive U-10 wt%Zr-5 wt%RE melt. Injection castings of U-10 wt%Zr and U-10 wt%Zr-5 wt%RE fuel slugs were also conducted to investigate the feasibility of a reusable melting crucible of metal fuel slugs. The U-10 wt% Zr fuel slugs were soundly fabricated without significant interactions of the graphite crucibles; however, the U-10 wt%Zr-5 wt%RE fuel slugs had some degradation or penetration, respectively, after injection casting. K E Y W O R D Sinjection casting, interaction, melting crucible, metal fuel, vacuum plasma-spray

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Electrodeposition characteristics of uranium by using a graphite cathode

Cited by 19 publications

References 9 publications

Electrodeposition of metals from non-aqueous solutions

Electrodeposition of metals from non-aqueous solutions

Current Status of Pyroprocessing Development at KAERI

Ceramic plasma‐spray‐coated graphite crucible for injection casting of fast reactor fuel slugs

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