Standard

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 изданияхстатьяРецензирование

Harvard

Herbst, RS, Law, JD, Todd, TA, Romanovskiy, VN, Smirnov, IV, Babain, VA, Esimantovskiy, VN & Zaitsev, BN 2003, 'Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes', Separation Science and Technology, Том. 38, № 12-13, стр. 2685-2708. https://doi.org/10.1081/SS-120022567

APA

Herbst, R. S., Law, J. D., Todd, T. A., Romanovskiy, V. N., Smirnov, I. V., Babain, V. A., Esimantovskiy, V. N., & Zaitsev, B. N. (2003). Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes. Separation Science and Technology, 38(12-13), 2685-2708. https://doi.org/10.1081/SS-120022567

Vancouver

Herbst RS, Law JD, Todd TA, Romanovskiy VN, Smirnov IV, Babain VA и пр. Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes. Separation Science and Technology. 2003 Янв. 1;38(12-13):2685-2708. https://doi.org/10.1081/SS-120022567

Author

Herbst, R. Scott ; Law, Jack D. ; Todd, Terry A. ; Romanovskiy, V. N. ; Smirnov, I. V. ; Babain, V. A. ; Esimantovskiy, V. N. ; Zaitsev, B. N. / Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes. в: Separation Science and Technology. 2003 ; Том 38, № 12-13. стр. 2685-2708.

BibTeX

@article{a73a57b5f73741e380a2ac437a467d73,
title = "Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes",
abstract = "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.",
keywords = "Actinide removal, Cesium removal, High-level radioactive waste, Solvent extraction, Strontium removal",
author = "Herbst, {R. Scott} and Law, {Jack D.} and Todd, {Terry A.} and Romanovskiy, {V. N.} and Smirnov, {I. V.} and Babain, {V. A.} and Esimantovskiy, {V. N.} and Zaitsev, {B. N.}",
year = "2003",
month = jan,
day = "1",
doi = "10.1081/SS-120022567",
language = "English",
volume = "38",
pages = "2685--2708",
journal = "Separation Science and Technology",
issn = "0149-6395",
publisher = "Taylor & Francis",
number = "12-13",

}

RIS

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