Результаты исследований: Публикации в книгах, отчётах, сборниках, трудах конференций › статья в сборнике материалов конференции › научная › Рецензирование
Diamide derivatives of dipicolinic acid as actinide and lanthanide extractants in a variation of the UNEX process. / Peterman, D. R.; Herbst, R. S.; Law, J. D.; Tillotson, R. D.; Garn, T. G.; Todd, T. A.; Romanovskiy, V. N.; Babain, V. A.; Alyapyshev, M. Yu; Smirnov, I. V.
GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems. 2007. стр. 1106-1110 (GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems).Результаты исследований: Публикации в книгах, отчётах, сборниках, трудах конференций › статья в сборнике материалов конференции › научная › Рецензирование
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TY - GEN
T1 - Diamide derivatives of dipicolinic acid as actinide and lanthanide extractants in a variation of the UNEX process
AU - Peterman, D. R.
AU - Herbst, R. S.
AU - Law, J. D.
AU - Tillotson, R. D.
AU - Garn, T. G.
AU - Todd, T. A.
AU - Romanovskiy, V. N.
AU - Babain, V. A.
AU - Alyapyshev, M. Yu
AU - Smirnov, I. V.
PY - 2007/12/1
Y1 - 2007/12/1
N2 - The Universal Extraction (UNEX) process has been developed for simultaneous extraction of cesium, strontium, and actinides from acidic solutions. This process utilizes an extradant consisting of 0.08 M chlorinated cobalt dicarbollide (HCCD), 0.007-0.02 M polyethylene glycol (PEG-400), and 0.02 M diphenyl-N,N-di-n-butylcarbamoylmethylphosphine oxide (PhiCMPO) in the diluent trifluoromethylphenyl sulfone (CF3C6H5SO 2, designated FS-13) and provides simultaneous extraction of Cs, Sr, actinides, and lanthanides from HNO3 solutions. The UNEXprocess is of limited utility for processing acidic solutions containing large quantities of lanthanides and/or actinides, such as dissolved spent nuclear fuel solutions. These constraints are primarily attributed to the limited concentrations of CMPO (a maximum of ∼0.02 M) in the organic phase and limited solubility of the CMPO-metal complexes. As a result, alternative actinide and lanthanide extradants are being investigated for use with HCCD as an improvement for waste processing and for applications where higher concentrations of the metals are present. Our preliminary results indicate that diamide derivatives of dipicolinic acid may function as efficient actinide and lanthanide extradants. The results to be presented indicate that, of the numerous diamides studied to date, the tetrabutyldiamide of dipicolinic acid, TBDPA, shows the most promise as an alternative adinide/lanthanide extradant in the UNEX process.
AB - The Universal Extraction (UNEX) process has been developed for simultaneous extraction of cesium, strontium, and actinides from acidic solutions. This process utilizes an extradant consisting of 0.08 M chlorinated cobalt dicarbollide (HCCD), 0.007-0.02 M polyethylene glycol (PEG-400), and 0.02 M diphenyl-N,N-di-n-butylcarbamoylmethylphosphine oxide (PhiCMPO) in the diluent trifluoromethylphenyl sulfone (CF3C6H5SO 2, designated FS-13) and provides simultaneous extraction of Cs, Sr, actinides, and lanthanides from HNO3 solutions. The UNEXprocess is of limited utility for processing acidic solutions containing large quantities of lanthanides and/or actinides, such as dissolved spent nuclear fuel solutions. These constraints are primarily attributed to the limited concentrations of CMPO (a maximum of ∼0.02 M) in the organic phase and limited solubility of the CMPO-metal complexes. As a result, alternative actinide and lanthanide extradants are being investigated for use with HCCD as an improvement for waste processing and for applications where higher concentrations of the metals are present. Our preliminary results indicate that diamide derivatives of dipicolinic acid may function as efficient actinide and lanthanide extradants. The results to be presented indicate that, of the numerous diamides studied to date, the tetrabutyldiamide of dipicolinic acid, TBDPA, shows the most promise as an alternative adinide/lanthanide extradant in the UNEX process.
UR - http://www.scopus.com/inward/record.url?scp=45149116041&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:45149116041
SN - 0894480553
SN - 9780894480553
T3 - GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
SP - 1106
EP - 1110
BT - GLOBAL 2007
T2 - GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Y2 - 9 September 2007 through 13 September 2007
ER -
ID: 42868506