TY - GEN
T1 - Use of cyanex-301 for separation of Am/Cm from lanthanides in an advanced nuclear fuel cycle
AU - Peterman, Dean
AU - Law, Jack D.
AU - Todd, Terry
AU - Tillotson, Richard D.
PY - 2006
Y1 - 2006
N2 - As part of the Advanced Fuel Cycle Initiative (AFCI), technologies for advanced aqueous processing of spent LWR fuel are being developed. Included in this program is the separation of Am and Cm from the lanthanides. This separation would allow the Am/Cm to be fabricated into a target and recycled to a reactor and the lanthanides to be disposed of with the raffinates from the process. A Laboratory Directed Research and Development (LDRD) Project at the INEEL is investigating the use of the active extradant in the Cyanex-301 reagent, bis(2,4,4-trimethylpentyl)dithiophosphinic acid, as a potential method to accomplish this separation. Specifically, the extractant is being developed based on an ammonium acetate/acetic acid buffered feed to the process which can be used to strip the actinides and lanthanides from a preceding transuranic separation process. The extraction and scrub distribution coefficients of Am and Eu with this extractant, as a function of total acetate concentration and pH, have been measured. Additionally, the extraction behavior of several additional lanthanides are compared. The potential for developing a Cyanex-301 process for the separation of Am/Cm from lanthanides to support an advanced nuclear fuel cycle is discussed.
AB - As part of the Advanced Fuel Cycle Initiative (AFCI), technologies for advanced aqueous processing of spent LWR fuel are being developed. Included in this program is the separation of Am and Cm from the lanthanides. This separation would allow the Am/Cm to be fabricated into a target and recycled to a reactor and the lanthanides to be disposed of with the raffinates from the process. A Laboratory Directed Research and Development (LDRD) Project at the INEEL is investigating the use of the active extradant in the Cyanex-301 reagent, bis(2,4,4-trimethylpentyl)dithiophosphinic acid, as a potential method to accomplish this separation. Specifically, the extractant is being developed based on an ammonium acetate/acetic acid buffered feed to the process which can be used to strip the actinides and lanthanides from a preceding transuranic separation process. The extraction and scrub distribution coefficients of Am and Eu with this extractant, as a function of total acetate concentration and pH, have been measured. Additionally, the extraction behavior of several additional lanthanides are compared. The potential for developing a Cyanex-301 process for the separation of Am/Cm from lanthanides to support an advanced nuclear fuel cycle is discussed.
UR - https://www.scopus.com/pages/publications/37449013326
U2 - 10.1021/bk-2006-0933.ch016
DO - 10.1021/bk-2006-0933.ch016
M3 - Conference contribution
AN - SCOPUS:37449013326
SN - 0841239312
SN - 9780841239319
T3 - ACS Symposium Series
SP - 251
EP - 259
BT - Separations for the Nuclear Fuel Cycle in the 21st Century
PB - American Chemical Society
ER -