• Proceedings of the Materials Research Society of Korea Conference
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• 2003.03a
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• pp.30-30
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• 2003

• Korean Journal of Materials Research
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• v.9 no.10
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• pp.985-991
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• 1999

Corrosion behaviors of Incoloy 800H, KSA(Kaeri Superalloy)-6, Inconel 600 and Hastelloy C-276 in molten salts were investigated in the temperature range of 650 ~ $850^{\circ}C$. Due to $\textrm{Li}_{2}\textrm{O}$-induced basic fluxing mechanism, the corrosion rates of the alloys in mixed molten salt of LiC1-$\textrm{Li}_{2}\textrm{O}$ were significantly higher than those in molten salt of LiCl. In the mixed molten salt, Fe-base alloys showed higher corrosion resistance than the Ni-base alloys. and Hastelloy C-276 with high Mo and W contents exhibited the highest corrosion rate among the examined alloys. The single layer of $\textrm{LiCrO}_{2}$ was formed in molten salt of LiCl and two phase structure of a scale consisted of oxides and Ni was formed in the mixed molten salt.

• Korean Journal of Materials Research
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• v.10 no.7
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• pp.471-477
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• 2000

Corrosion behavior of Fe-Ni-Cr alloy in molten salts of LiCl and LiCl-$Li_2O was investigated in the tempera-ture range of $650~850^{\circ}C$. In the molten salt of LiCl, and internal oxidation of Fe occurred in the KSA(Kaeri Superalloy)-1 alloy without containing Cr, while a dense protective oxide scale of $LiCrO_2$ was formed in the KSA-4, Incoloy 800H and KSA-5 alloys. In the mixed molten salt of LiCl-$Li_2O$, internal oxidation of Fe and Cr took place in the KSA-1 and KSA-4 alloys, respectively. Non-protective porous oxide scales consisting of $LiCrO_2$ and Ni were formed in the Incoloy 800H and KSA-5. The corrosion rate of the alloys increased with the increase in Cr content and the corrosion rate followed the parabolic law for the alloy containing Cr content less than 8%, and the linear law for the alloy containing Cr content more than 8%. Such a corrosion behavior of the alloy in the mixed molten salt of LiCl-$Li_2O$ was interpreted in terms of the basic fluxing mechanism of protective oxide scale of $Cr_2O_3$.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.346-346
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• 2009

산화물 형태 사용후핵연료의 효율적 처분 혹은 재활용을 위한 연구 가운데, 고온의 LiCl 용융염 중에서 전해환원하여 금속으로 환원시킨 후, 환원된 금속을 고온의 LiCl-KCl 용융염에서 전해정련하는 연구가 국내외적으로 활발하게 진행되고 있다. 전해환원을 위해 일정 농도 $Li_2O$가 LiCl 용융염에 첨가되며 $Li_2O$ 농도가 높으면 반응 재질의 부식성이 크게 증가하므로 일반적으로 우라늄 산화물은 1wt% 이하의 $Li_2O$ 농도에서 전해환원 된다. 우라늄 산화물의 전해환원 전위는 $Li_2O$의 전해환원 전위 보다 표준 상태를 기준으로 공정온도인 650 $^{\circ}C$ 에서 약 70 mV 정도 낮기 때문에 전해환원 과정에서 $Li_2O$ 의 환원으로 Li 금속이 생성될 가능성이 있으며 우라늄 산화물은 대부분 직접 전해환원 되지만 일부 Li에 의해 화학적으로 환원되기도 한다. 전해환원 공정에서 환원되지 않은 희토류 산화물은 전해정련 공정에서 $UCl_3$와 반응하여 $UO_2$를 생성시켜 공정 효율을 떨어뜨린다. 따라서 전해환원 공정에서 가능하연 최대한 희토류 산화물을 금속으로 환원시키는 조건을 찾아내는 것이 바람직하고 이를 위해서 우선 전해환원 공정에서 희토류 산화물의 화학적 거동의 이해가 요구된다. 본 연구에서 열역학적 검토를 통하여 희토류 산화물의 환원 조건을 조사한 결과 희토류 산화물은 매운 낮은 $Li_2O$ 농도에서 Li에 의해 환원되고, 1wt% 이하의 $Li_2O$ 농도에서는 Sc와 Lu의 산화물이 $Li_2O$와 복합산화물을 형성하고 이들 복합산화물은 Li에 의해 환원되지 않는 것으로 나타났다. 또한 희토류 원소 별로 희토류 원소 산화물의 Li에 의한 환원 조건으로서 평형상태에서의 $Li_2O$ 농도 즉 환원 임계 $Li_2O$ 농도를 실험적으로 측정하였으며 1wt% $Li_2O$ 농도 이하에서 열역학적 해석과 동일하게 Sc와 Lu만이 복합산화물을 형성하여 Li에 의해 직접환원 되지 않는 것으로 관찰되었다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.3
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• pp.211-217
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• 2004

A Li recovery technology has been developed and related experimental verification efforts were carried out to improve the economical viability and environmental friendliness of the 'Advanced Spent Fuel Conditioning Process' being developed at KAERI. This technology is characterized by the combination of 1) the electrolysis of $Li_2O$ in a molten salt by using a porous non-conducting magnesia container at the cathode, 2) the separation of the Li in the container from the molten salt by elevating the container above the level of a molten salt, 3) the transport of the Li in the container by using a vacuum siphon to a separated reservoir. Li was semi-continuously recovered from a LiCl-$Li_2O$ molten salt with a more than 95% yield by using the developed technology.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.374.2-374
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• 2001

• Journal of the Korean Electrochemical Society
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• v.18 no.4
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• pp.156-160
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• 2015

Experiments using a metal oxide of a non-nuclear material as a fuel are very useful to develop a new electrolytic reducer for pyroprocessing. In this study, the titanium oxides (TiO and $TiO_2$) were selected and investigated as the non-nuclear fuel for the electrolytic reduction. The immersion tests of TiO and $TiO_2$ in a molten 1.0 wt.% $Li_2O$-LiCl salt revealed that they have solubility of 156 and 2100 ppm, respectively. Then, the Ti metals were successfully produced after the separate electrolytic reduction of TiO and $TiO_2$ in a molten 1.0 wt.% $Li_2O$-LiCl salt. However, Ti was detected on the platinum anode used for the electrolytic reduction of $TiO_2$ unlike TiO due to the dissolution of $TiO_2$ into the salt.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.229-236
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• 2012

A molten salt technology using $Li_2O$-LiCl has been extensively investigated to recover uranium metal from spent fuels in the field of nuclear energy. In the reduction process, it is an important point to maintain the concentration of $Li_2O$. $ZrO_2$ is inevitably contained in the spent fuels because Zr is one of the main components of fuel rod hulls. Therefore, the fate of $ZrO_2$ in $Li_2O$-LiCl molten salt has been investigated. It was found that $Li_2ZrO_3$ and $Li_4ZrO_4$ were formed chemically and electrochemically and they were not reduced to Zr. The recycling of $Li_2O$ is the key mechanism ruling the total reaction in the electrolytic reduction process. However, $ZrO_2$ will have a role as a $Li_2O$ sink.

• Proceedings of the Materials Research Society of Korea Conference
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• 1999.11a
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• pp.38-38
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• 1999

• Proceedings of the Materials Research Society of Korea Conference
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• 2002.11a
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• pp.52-52
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• 2002