Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
The universal solvent extraction (unex) process. II. flowsheet development and demonstration of the unex process for theseparation kof cesium strontium and actinides from actual acidic radioactive waste. / Law, Jack D.; Herbst, R. Scott; Todd, Terry A.; Romanovskiy, Valeriy N.; Babain, Vasily A.; Esimantovskiy, Vyatcheslav M.; Smirnov, Igor V.; Zaitsev, Boris N.
в: Solvent Extraction and Ion Exchange, Том 19, № 1, 07.04.2001, стр. 23-36.Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
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TY - JOUR
T1 - The universal solvent extraction (unex) process. II. flowsheet development and demonstration of the unex process for theseparation kof cesium strontium and actinides from actual acidic radioactive waste
AU - Law, Jack D.
AU - Herbst, R. Scott
AU - Todd, Terry A.
AU - Romanovskiy, Valeriy N.
AU - Babain, Vasily A.
AU - Esimantovskiy, Vyatcheslav M.
AU - Smirnov, Igor V.
AU - Zaitsev, Boris N.
PY - 2001/4/7
Y1 - 2001/4/7
N2 - A novel solvent extraction process, the Universal Extraction (UNEX) process, has been developed for the simultaneous separation of cesium, strontium, and the actinides from acidic waste solutions. The UNEX process solvent consists of chlorinated cobalt dicarbollide for the extraction of 137Cs, polyethylene glycol for the extraction of 90Sr, and diphenyl-N,N-dibutylcarbamoyl phosphine oxide for the extraction of the actinides and lanthanides. A nonnitroaromatic polar diluent consisting of phenyltrifluoromethyl sulfone has been developed for this process. A UNEX flowsheet consisting of a single solvent extraction cycle has been developed as a part of a collaborative effort between the Khlopin Radium Institute (KRI) and the Idaho National Engineering and Environmental Laboratory (INEEL). This flowsheet has been demonstrated with actual acidic radioactive tank waste at the INEEL using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded cell facility. The activities of 137Cs, 90Sr, and the actinides were reduced to levels at which a grout waste form would meet NRC Class A LLW requirements. The extraction of 99Tc and several nonradioactive metals by the UNEX solvent has also been evaluated.
AB - A novel solvent extraction process, the Universal Extraction (UNEX) process, has been developed for the simultaneous separation of cesium, strontium, and the actinides from acidic waste solutions. The UNEX process solvent consists of chlorinated cobalt dicarbollide for the extraction of 137Cs, polyethylene glycol for the extraction of 90Sr, and diphenyl-N,N-dibutylcarbamoyl phosphine oxide for the extraction of the actinides and lanthanides. A nonnitroaromatic polar diluent consisting of phenyltrifluoromethyl sulfone has been developed for this process. A UNEX flowsheet consisting of a single solvent extraction cycle has been developed as a part of a collaborative effort between the Khlopin Radium Institute (KRI) and the Idaho National Engineering and Environmental Laboratory (INEEL). This flowsheet has been demonstrated with actual acidic radioactive tank waste at the INEEL using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded cell facility. The activities of 137Cs, 90Sr, and the actinides were reduced to levels at which a grout waste form would meet NRC Class A LLW requirements. The extraction of 99Tc and several nonradioactive metals by the UNEX solvent has also been evaluated.
UR - http://www.scopus.com/inward/record.url?scp=0035077533&partnerID=8YFLogxK
U2 - 10.1081/SEI-100001371
DO - 10.1081/SEI-100001371
M3 - Article
AN - SCOPUS:0035077533
VL - 19
SP - 23
EP - 36
JO - Solvent Extraction and Ion Exchange
JF - Solvent Extraction and Ion Exchange
SN - 0736-6299
IS - 1
ER -
ID: 53581988