Development of continuous ingot casting process for uranium dendrites in pyroprocess

被引:14
作者
Jang, Jun-Hyuk [1 ]
Kang, Hee-Seok [1 ]
Lee, Yun-Sang [1 ]
Lee, Hansoo [1 ]
Kim, Jeong-Guk [1 ]
机构
[1] Korea Atom Energy Res Inst, Nucl Fuel Cycle Proc Technol Dev Div, Taejon 305353, South Korea
关键词
Uranium; Pyroprocess; Ingot casting; Engineering scale; Cathode process; DISTILLATION; RECOVERY; CADMIUM;
D O I
10.1007/s10967-012-2093-3
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
A continuous ingot casting process was developed to improve the productivity of ingot fabrication. A supplemental charge method in which uranium dendrites were additionally added into molten uranium was introduced for the first time, and a tilting system of a melting crucible to mold was developed. The feasibility of these processes was confirmed by a uranium melting test at the laboratory scale, successfully obtaining a uranium ingot in about 4.6 kg. Based on the results, we scaled up the ingot casting processes at the engineering scale. A rotating continuous feeder was installed for the ceaseless feeding of the dendrites into molten uranium. The tilting system and eight mold crucibles on a turn-table were adopted. The operability of the continuous ingot casting process at the engineering scale was successfully confirmed by a melting test of copper. We consider that the engineering scale equipment can cast above a 50 kg U/batch with the continuous casting processes.
引用
收藏
页码:1743 / 1751
页数:9
相关论文
共 11 条
  • [1] Brunsvold A. R., 2000, P 8 INT C NUCL ENG B
  • [2] The reactivity with uranium of coating layers by the thermal spraying method
    Cho, Choon-ho
    Lee, Yun-sang
    Kim, Eung-soo
    Kim, Jeong-guk
    Lee, Han-soo
    [J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2011, 287 (02) : 485 - 490
  • [3] Separation of adhered salt from uranium deposits generated in electro-refiner
    Kwon, S. W.
    Park, K. M.
    Ahn, H. G.
    Lee, H. S.
    Kim, J. G.
    [J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2011, 288 (03) : 789 - 793
  • [4] A study on the evaporation of cadmium for the recovery of actinides from a liquid cathode
    Kwon, S. W.
    Kim, J. Y.
    Ahn, D. H.
    Lee, H. S.
    Ahn, H. G.
    [J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2010, 284 (01) : 143 - 149
  • [5] LEE YOON SANG, 2010, [Journal of Nuclear Fuel Cycle and Waste Technology, 방사성폐기물학회지], V8, P85
  • [6] Lee YS, 2011, US patent, Patent No. [2011/0056647 A0056641, 20110056647]
  • [7] Park KM, 2012, J RADIOANAL NUCL CHE, DOI [10.1007/s10967-10012-11766-10962, DOI 10.1007/S10967-10012-11766-10962]
  • [8] Engineering-scale distillation of cadmium for actinide recovery
    Westphal, B. R.
    Price, J. C.
    Vaden, D.
    Benedict, R. W.
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 2007, 444 : 561 - 564
  • [9] On the development of a distillation process for the electrometallurgical treatment of irradiated spent nuclear fuel
    Westphav, Brian R.
    Marsden, Kenneth C.
    Price, John C.
    Laug, David V.
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2008, 40 (03) : 163 - 174
  • [10] Yoo J. H., 2008, J OF THE KOREAN RADI, V6, P233