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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 1,866 - 1,870 (5page)
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초록· 키워드
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Residual salt separation is an essential step in pyroprocessing because its reaction products, as prepared by electrochemical unit processes, contain frozen residual electrolyte species, which are generally composed of alkali-metal chloride salts (e.g., LiCl, KCl). In this study, a simple technique that utilizes high-temperature gas flux as a driving force to melt and push out the residual salt in the reaction products was developed. This technique is simple as it only requires the use of a heating gun in combination with a gas injection system. Consequently, LiNO3–ZrO2 and LiCl–ZrO2 mixtures were successfully separated by the high-temperature gas injection (separation efficiency > 93%), thereby demonstrating the viability of this simple technique for residual salt separation.
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참고문헌 (16)
참고문헌 신청
HANSOO LEE / 2011 / PYROPROCESSING TECHNOLOGY DEVELOPMENT AT KAERI / Nuclear Engineering and Technology 43(4):317~328
TADASHI INOUE / 2008 / DEVELOPMENT OF PYROPROCESSING AND ITS FUTURE DIRECTION / Nuclear Engineering and Technology 40(3):183~190
E. -Y. Choi / 2015 / Electrochemical processing of spent nuclear fuels : an overview of oxide reduction in pyroprocessing technology / Pro. Nat. Sci. Mater 25:572~582
A. R. Brunsvold / 2000 / Design and development of a cathode processor for electrometallurgical treatment of spent nuclear fuel / Proceedings of ICONE 8: 8th International Conference on Nuclear Engineering
I. Kim / 2013 / Distillation of LiCl from the LiCl-Li2O molten salt of the electrolytic reduction process / J. Radioanal. Nucl. Chem 295:1413~1417
TADASHI INOUE / 2008 / DEVELOPMENT OF PYROPROCESSING AND ITS FUTURE DIRECTION / Nuclear Engineering and Technology 40(3):183~190
E. -Y. Choi / 2015 / Electrochemical processing of spent nuclear fuels : an overview of oxide reduction in pyroprocessing technology / Pro. Nat. Sci. Mater 25:572~582
A. R. Brunsvold / 2000 / Design and development of a cathode processor for electrometallurgical treatment of spent nuclear fuel / Proceedings of ICONE 8: 8th International Conference on Nuclear Engineering
I. Kim / 2013 / Distillation of LiCl from the LiCl-Li2O molten salt of the electrolytic reduction process / J. Radioanal. Nucl. Chem 295:1413~1417
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