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Featured researches published by Tae-Kyo Lee.


Journal of Nuclear Science and Technology | 2013

Study on the phosphate reaction characteristics of lanthanide chlorides in molten salt with operating conditions

Tae-Kyo Lee; Yung-Zun Cho; Hee-Chul Eun; Sung-Mo Son; Hwan-Seo Park; Geun-Il Park; Taek-Sung Hwang

A minimization of waste salt is one of the most important issues for the optimization of pyroprocessing. The separation of fission products in waste salts and the reuse of purified waste salt are promising strategies for minimizing the waste salt amounts. The phosphate precipitation of lanthanide is currently being considered for eutectic (LiCl–KCl) waste salt purification. In this research, the effects of molten salt temperature (400–550 °C) and reaction time (max. 180 min) upon conversion into the phosphate of lanthanides was investigated using 1 and 3 kg of eutectic salt. The conversion efficiency of lanthanides to molten salt-insoluble precipitates and phosphates was increased with an increase in molten salt temperature and operating time until it attained a specific temperature and time. K3PO4 as a precipitant was more favorable than Li3PO4 in terms of reactivity. To obtain over a 99% overall conversion efficiency, about 30 min was required in the case of using K3PO4 at 450 °C, but about 120 min in the case of using Li3PO4 at 550 °C. The lanthanide precipitates formed by a reaction with phosphate were a mixture of monoclinic structures, usually representing a polyhedron structure, and a tetragonal structure, representing a platelet structure.


Nuclear Engineering and Technology | 2013

EUTECTIC(LiCl-KCl) WASTE SALT TREATMENT BY SEQUENCIAL SEPARATION PROCESS

Yung-Zun Cho; Tae-Kyo Lee; Jung-Hun Choi; Hee-Chul Eun; Hwan-Seo Park; Geun-Il Park

The sequential separation process, composed of an oxygen sparging process for separating lanthanides and a zone freezing process for separating Group I and II fission products, was evaluated and tested with a surrogate eutectic waste salt generated from pyroprocessing of used metal nuclear fuel. During the oxygen sparging process, the used lanthanide chlorides (Y, Ce, Pr and Nd) were converted into their sat-insoluble precipitates, over 99.5% at 800 °C; however, Group I (Cs) and II (Sr) chlorides were not converted but remained within the eutectic salt bed. In the next process, zone freezing, both precipitation of lanthanide precipitates and concentration of Group I/II elements were preformed. The separation efficiency of Cs and Sr increased with a decrease in the crucible moving speed, and there was little effect of crucible moving speed on the separation efficiency of Cs and Sr in the range of a 3.7 – 4.8 mm/hr. When assuming a 60% eutectic salt reuse rate, over 90% separation efficiency of Cs and Sr is possible, but when increasing the eutectic salt reuse rate to 80%, a separation efficiency of about 82 – 86 % for Cs and Sr was estimated.


Journal of Nuclear Materials | 2012

Recycling of LiCl–KCl eutectic based salt wastes containing radioactive rare earth oxychlorides or oxides

Hee-Chul Eun; Yung-Zun Cho; S.M. Son; Tae-Kyo Lee; Hee-Chul Yang; In-Tae Kim; Han-Soo Lee


Journal of Nuclear Materials | 2013

Purification of used eutectic (LiCl–KCl) salt electrolyte from pyroprocessing

Yung-Zun Cho; Tae-Kyo Lee; Hee-Chul Eun; Jung-Hoon Choi; In-Tae Kim; Geun-Il Park


Journal of Nuclear Materials | 2013

An optimal method for phosphorylation of rare earth chlorides in LiCl–KCl eutectic based waste salt

Hee-Chul Eun; J. H. Kim; Yung-Zun Cho; Jung-Hoon Choi; Tae-Kyo Lee; Hyun-Soo Park; Geun-Il Park


Journal of Non-crystalline Solids | 2016

Fabrication of rare earth calcium phosphate glass waste forms for the immobilization of rare earth phosphates generated from pyrochemical process

Jung-Hoon Choi; Hee-Chul Eun; Ki-Rak Lee; In-Hak Cho; Tae-Kyo Lee; Hwan-Seo Park; Do-Hee Ahn


Journal of Crystal Growth | 2013

Inclusion behavior of Cs, Sr, and Ba impurities in LiCl crystal formed by layer-melt crystallization: Combined first-principles calculation and experimental study

Jung-Hoon Choi; Yung-Zun Cho; Tae-Kyo Lee; Hee-Chul Eun; Jun-Hong Kim; In-Tae Kim; Geun-Il Park; Jeung-Ku Kang


Journal of Nuclear Materials | 2016

A reactive distillation process for the treatment of LiCl-KCl eutectic waste salt containing rare earth chlorides

Hee-Chul Eun; Jung-Hoon Choi; N.Y. Kim; Tae-Kyo Lee; Seung-Youb Han; Ki-Rak Lee; Hyun-Soo Park; Do-Hee Ahn


Journal of Nuclear Materials | 2011

Study on a recovery of rare earth oxides from a LiCl–KCl–RECl3 system

Hee-Chul Eun; Yung-Zun Cho; Hyun-Soo Park; Tae-Kyo Lee; In-Tae Kim; K.I. Park; Han-Soo Lee


Journal of the Nuclear Fuel Cycle and Waste Technology | 2015

Separation Characteristics of NdCl3 from LiCl-KCl Eutectic Salt in a Reactive Distillation Process using Li2CO3 or K2CO3

Hee-Chul Eun; Jung-Hoon Choi; Tae-Kyo Lee; In-Hak Cho; Na-Young Kim; Jae-Uk Yu; Hwan-Seo Park; Do-Hee Ahn

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Hee-Chul Eun

University of Science and Technology

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Yung-Zun Cho

University of Science and Technology

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Hyun-Soo Park

Korea Electric Power Corporation

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Yung-Zun Cho

University of Science and Technology

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