In cooperation with the Iranian Nuclear Society

Document Type : Research Paper

Authors

Abstract

NaF disks are used for the adsorption of UF6 in low concentration. In this paper a wet chemical method is presented for recovery of uranium from NaF disks. In this method the adsorbed uranium on the disks is dissolved in sodium carbonate solution and converted to UO2(CO3)34- and this complex is adsorbed on the ionic exchange resin amberlit-110. By using sodium nitrate solution, UO2(CO3)34- is desorbed from resin. The uranium on the resulting solution can be used in production process of UF6. The proposed method introduced in this paper shown to have high efficiency and convenient operational procedure.

Highlights

  1. 1.    I. Amamoto, T. Terai, “Behavior of impurities in recycled uranium at uranium conversion process,” J. Nucl. Sci. Techno, Suppl. 3 (2002).

 

  1. 2.    Y. Yaita, I. Amamoto, “Wet process using hydrochloric acid for treatment of uranium waste,” Proceedings of 2003 Fall Meeting of the Atomic Energy Society of Japan, Shizuoka, Japan, Sep 24-26 (2003).

 

  1. 3.    M. Takai, I. Amamoto, “Study on fluorination processing method for spent uranium absorbent,” Proceedings of 2001 Fall Meeting of the Atomic Energy Society of Japan, Sapporo, Japan, Sep 9-21 (2001).

 

  1. 4.    R. Fujita, I. Amamoto, “Study on U recovery process for chemical trap materials by preprocess, Proceedings of 2000 Fall Meeting of the Atomic Energy Society of Japan,”  Aomori, Japan, Sep 15-17, 593 [in Japanese] (2001).

 

  1. 5.    R. Fujita, I. Amamoto, “Study on U recovery process for chemical trap materials by preprocess, Proceedings of 2000 Fall Meeting of the Atomic Energy Society of Japan,” Aomori, Japan, Sep 9-21, 774 [in Japanese] (2001).

 

  1. 6.    J.J. Katz, E. Rabin Witch, “The chemistry of uranium,” Dover, New York, 377-379 (1951).

 

  1. 7.    M.H. Rand, O. Kubaschewski, “The thermo chemical Properties of uranium compounds, oliver & boyd,” London, 13-15 (1963).

 

  1. 8.    C.J. Rodden, “Current procedures for analysis of UO2, U3O8, UF4 and UF6 TID-7003,” (1956).

 

  1. 9.    Radiochemistry Society, Lanthanides & Actinides: Uranium Chemistry (2003).

Keywords

  1. 1.    I. Amamoto, T. Terai, “Behavior of impurities in recycled uranium at uranium conversion process,” J. Nucl. Sci. Techno, Suppl. 3 (2002).

 

  1. 2.    Y. Yaita, I. Amamoto, “Wet process using hydrochloric acid for treatment of uranium waste,” Proceedings of 2003 Fall Meeting of the Atomic Energy Society of Japan, Shizuoka, Japan, Sep 24-26 (2003).

 

  1. 3.    M. Takai, I. Amamoto, “Study on fluorination processing method for spent uranium absorbent,” Proceedings of 2001 Fall Meeting of the Atomic Energy Society of Japan, Sapporo, Japan, Sep 9-21 (2001).

 

  1. 4.    R. Fujita, I. Amamoto, “Study on U recovery process for chemical trap materials by preprocess, Proceedings of 2000 Fall Meeting of the Atomic Energy Society of Japan,”  Aomori, Japan, Sep 15-17, 593 [in Japanese] (2001).

 

  1. 5.    R. Fujita, I. Amamoto, “Study on U recovery process for chemical trap materials by preprocess, Proceedings of 2000 Fall Meeting of the Atomic Energy Society of Japan,” Aomori, Japan, Sep 9-21, 774 [in Japanese] (2001).

 

  1. 6.    J.J. Katz, E. Rabin Witch, “The chemistry of uranium,” Dover, New York, 377-379 (1951).

 

  1. 7.    M.H. Rand, O. Kubaschewski, “The thermo chemical Properties of uranium compounds, oliver & boyd,” London, 13-15 (1963).

 

  1. 8.    C.J. Rodden, “Current procedures for analysis of UO2, U3O8, UF4 and UF6 TID-7003,” (1956).

 

  1. 9.    Radiochemistry Society, Lanthanides & Actinides: Uranium Chemistry (2003).