Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes. / Herbst, R. Scott; Law, Jack D.; Todd, Terry A.; Romanovskiy, V. N.; Smirnov, I. V.; Babain, V. A.; Esimantovskiy, V. N.; Zaitsev, B. N.
в: Separation Science and Technology, Том 38, № 12-13, 01.01.2003, стр. 2685-2708.Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
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TY - JOUR
T1 - Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes
AU - Herbst, R. Scott
AU - Law, Jack D.
AU - Todd, Terry A.
AU - Romanovskiy, V. N.
AU - Smirnov, I. V.
AU - Babain, V. A.
AU - Esimantovskiy, V. N.
AU - Zaitsev, B. N.
PY - 2003/1/1
Y1 - 2003/1/1
N2 - A synergistic extraction mixture containing chlorinated cobalt dicarbollide (CCD), polyethylene glycol (PEG), and diphenyl-N,N-dibutylcarbamoyl phosphine oxide (CMPO) in a suitable polar diluent is being developed for the simultaneous recovery of Cs, Sr, and the actinides from highly acidic radioactive wastes. Development of this UNEX process was by a successful collaboration between scientists from the Idaho National Engineering and Environmental Laboratory (INEEL) and the Khlopin Radium Institute (KRI) in St. Petersburg, Russia. Development efforts focused on the treatment of radioactive waste currently stored at the INEEL. The development of the UNEX process has and continues to be an evolutionary process. Numerous countercurrent flowsheet demonstrations have been conducted to date, including two tests with several liters of actual radioactive tank waste, one test with dissolved radioactive calcine, and several tests with surrogate INEEL tank and dissolved calcine wastes. All countercurrent flowsheet tests have been performed in banks of centrifugal contactors. Removal efficiencies of 99.95% for 137Cs, 99.995% for 90Sr, and 99.96% for total α (predominately 241Am, 238Pu, and 239Pu) were observed in countercurrent tests with samples of actual INEEL tank waste. The evolutionary concepts included in the development of the UNEX process are discussed, including development of the current diluent, phenyltrifluoromethyl sulfone, to replace nitroaromatic diluents used in earlier studies. Results from the most recent countercurrent flowsheet testing with 1.2 L of actual dissolved INEEL calcine are also presented, which represents the current state of UNEX development. Finally, future research directions in the development and understanding of the UNEX process are discussed.
AB - A synergistic extraction mixture containing chlorinated cobalt dicarbollide (CCD), polyethylene glycol (PEG), and diphenyl-N,N-dibutylcarbamoyl phosphine oxide (CMPO) in a suitable polar diluent is being developed for the simultaneous recovery of Cs, Sr, and the actinides from highly acidic radioactive wastes. Development of this UNEX process was by a successful collaboration between scientists from the Idaho National Engineering and Environmental Laboratory (INEEL) and the Khlopin Radium Institute (KRI) in St. Petersburg, Russia. Development efforts focused on the treatment of radioactive waste currently stored at the INEEL. The development of the UNEX process has and continues to be an evolutionary process. Numerous countercurrent flowsheet demonstrations have been conducted to date, including two tests with several liters of actual radioactive tank waste, one test with dissolved radioactive calcine, and several tests with surrogate INEEL tank and dissolved calcine wastes. All countercurrent flowsheet tests have been performed in banks of centrifugal contactors. Removal efficiencies of 99.95% for 137Cs, 99.995% for 90Sr, and 99.96% for total α (predominately 241Am, 238Pu, and 239Pu) were observed in countercurrent tests with samples of actual INEEL tank waste. The evolutionary concepts included in the development of the UNEX process are discussed, including development of the current diluent, phenyltrifluoromethyl sulfone, to replace nitroaromatic diluents used in earlier studies. Results from the most recent countercurrent flowsheet testing with 1.2 L of actual dissolved INEEL calcine are also presented, which represents the current state of UNEX development. Finally, future research directions in the development and understanding of the UNEX process are discussed.
KW - Actinide removal
KW - Cesium removal
KW - High-level radioactive waste
KW - Solvent extraction
KW - Strontium removal
UR - http://www.scopus.com/inward/record.url?scp=0042026795&partnerID=8YFLogxK
U2 - 10.1081/SS-120022567
DO - 10.1081/SS-120022567
M3 - Article
AN - SCOPUS:0042026795
VL - 38
SP - 2685
EP - 2708
JO - Separation Science and Technology
JF - Separation Science and Technology
SN - 0149-6395
IS - 12-13
ER -
ID: 53581094