APPLICATION OF VACUUM SALT DISTILLATION TECHNOLOGY FOR THE REMOVAL OF FLUORIDE

Electrodeposition Characteristics of Uranium in Molten LiCl-KCl Eutectic and its Salt Distillation Behavior

Journal of Nuclear Science and Technology ◽

10.1080/18811248.2006.9711088 ◽

2006 ◽

Vol 43 (3) ◽

pp. 263-269 ◽

Cited By ~ 22

Author(s):

Jong-Hyeon LEE ◽

Young-Ho KANG ◽

Sung-Chan HWANG ◽

Joon-Bo SHIM ◽

Byung-Gil AHN ◽

...

Keyword(s):

Salt Distillation

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Production of uranium metal via electrolytic reduction of uranium oxide in molten LiCl and salt distillation

Journal of Radioanalytical and Nuclear Chemistry ◽

10.1007/s10967-014-3842-2 ◽

2014 ◽

Vol 304 (2) ◽

pp. 535-546 ◽

Cited By ~ 10

Author(s):

Eun-Young Choi ◽

Chan Yeon Won ◽

Dae-Seung Kang ◽

Sung-Wook Kim ◽

Ju-Sun Cha ◽

...

Keyword(s):

Uranium Oxide ◽

Electrolytic Reduction ◽

Uranium Metal ◽

Salt Distillation

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Closed Chamber Salt Distillation System for an Enhanced Recovery of Evaporated Pure Salt

Journal of Nuclear Science and Technology ◽

10.1080/18811248.2010.9711661 ◽

2010 ◽

Vol 47 (11) ◽

pp. 973-976 ◽

Cited By ~ 1

Author(s):

Hee-Chul YANG ◽

Hee-Chul EUN ◽

Han-Soo LEE ◽

Yung-Jun CHO

Keyword(s):

Enhanced Recovery ◽

Closed Chamber ◽

Salt Distillation ◽

Distillation System ◽

Pure Salt

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Separation of Rare Earth Precipitates From LiCl-KCl Eutectic Salts by a Distillation at a Reduced Pressure

ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 1 ◽

10.1115/icem2009-16162 ◽

2009 ◽

Author(s):

Hee-Chul Eun ◽

Hee-Chul Yang ◽

Yung-Zun Cho ◽

Hwan-Seo Park ◽

Han-Soo Lee ◽

...

Keyword(s):

Rare Earth ◽

Vacuum Distillation ◽

Ambient Pressure ◽

Reduced Pressure ◽

Salt Distillation ◽

Almost All ◽

The Rare Earth

Distillation and condensation characteristics of LiCl-KCl eutectic salts containing rare earth precipitates were investigated to separate the rare earth precipitates from the salts effectively. The distillation flux of the salts was increased by about 1,000 times by reducing the ambient pressure from 760 Torr to 0.5 Torr. The salt vapors were almost changed into salt lumps during a salt distillation at the ambient pressure of 0.5 Torr and they were collected in the condensed salt storage. However, fine salt particles were formed when the salt distillation was processed at 10 Torr and it is difficult for them to be recovered. Therefore, it is thought that a salt vacuum distillation and condensation should be processed to recover almost all of the vaporized salts at a pressure below 0.5 Torr.

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Composition and Pressure Estimation on Salt Distillation Process after Electrorefining for Spent Nuclear Fuel

Advanced Materials Research ◽

10.4028/www.scientific.net/amr.807-809.1277 ◽

2013 ◽

Vol 807-809 ◽

pp. 1277-1280

Author(s):

Yeon Ki Hong ◽

Byung Heung Park

Keyword(s):

Nuclear Fuel ◽

Process Design ◽

Total Pressure ◽

Spent Nuclear Fuel ◽

High Vacuum ◽

Main Process ◽

Distillation Process ◽

Nuclear Fuels ◽

Vapor Composition ◽

Salt Distillation

A pyroprocessing technology has been developed to process spent nuclear fuels with decreased waste and increased proliferation resistance. A main process of the pyroprocessing is an electrorefining which requires a post-treatment for recovered uranium. A distillation approach is adopted to remove an electrolyte salt residue on the uranium. In this work, the vapor composition of the distillation process and the total pressure were estimated to obtain basic data for process design and integration. Six chlorides including KCl, LiCl, UCl3, PuCl3, CeCl3, and YCl3 were considered to understand the behavior of the representative components of actinides and lanthanides. It was found that small amount of the actinides and lanthanides would be accompanied by the electrolyte salts (KCl and LiCl) during the distillation under high vacuum.

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Stability of Tungsten Crucible against Uranium, Rare Earth, Cadmium, and Chlorides for Cathode Process in Pyroprocessing

Science and Technology of Nuclear Installations ◽

10.1155/2019/4121285 ◽

2019 ◽

Vol 2019 ◽

pp. 1-7

Author(s):

Junhyuk Jang ◽

Seungyoub Han ◽

Tack-Jin Kim ◽

Gha-Young Kim ◽

Chang Hwa Lee ◽

...

Keyword(s):

Rare Earth ◽

Induction Heating ◽

Induction Melting ◽

Potential Utility ◽

Crucible Material ◽

Heating Systems ◽

Salt Distillation ◽

Operation Conditions ◽

The Stability ◽

Re Elements

The stability of W against U, rare-earth (RE) elements, Cd, and various chlorides was evaluated by melting and distillation testing. Three runs were performed with a W crucible to examine its reactivity: (i) RE melting by induction heating, (ii) salt distillation test of U-dendrite and various chlorides, and (iii) Cd distillation test from U–Cd alloy. The W crucible remained stable after the RE melting test using induction melting, exhibiting its applicability for induction heating systems. The salt distillation test with the W crucible at 1050°C exhibited the stability of W against U and various chlorides, showing no interaction. The Cd distillation test with the W crucible at 500°C showed that the crucible was very stable against Cd, maintaining a shiny surface. These results reveal that the W crucible is stable under operation conditions for both salt and Cd distillation, suggesting the high potential utility of W as a crucible material for application in cathode processes in pyroprocessing.

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