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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
G. W. Mason, D. F. Peppard
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 247-251
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28886
Articles are hosted by Taylor and Francis Online.
Certain applications of acidic organophosphorus extractants to transuranic separations devised in the authors' laboratory are described. In a system employing mono-2-ethyl hexyl phosphoric acid, (2-EtHexO)PO(OH)2, symbolized as H2MEHP, in toluene vs. a concentrated aqueous NH4CNS solution, the ratio KPm/KAm is approximately 50, while in the corresponding TBP system it is considerably less than unity. The H2MEHP (in toluene) vs. HCl system has been used in effecting mutual M(III), M(IV), and M(VI) separations. Throughout the 1–12 M HCl range the extractant dependency (0.05-0.3 F H2MEHP) approximates first power for lanthanides(III), Pu(III), Am (III), Np(IV) and U(VI). Comparable studies of other H2MGP and H2[GP] compounds, i.e., (GO)PO(OH)2 and GPO(OH)2, are reported. A system employing HDΦP, i.e. (C6H50)2PO(OH), in toluene vs. a concentrated aqueous chloride phase serves to effect the difficult Cf-Y separation, the ratio KCf/KY being approximately 400. Systems involving a mono acidic phosphate, HDGP, or phosphonate, HG[G'P], in a diluent vs. an aqueous mineral acid solution have proved valuable in effecting the Cf-Cm separation, Cf extracting the better. The fact that actinides(IV) are much more extractable than actinides(III) in HDGP vs. mineral acid systems is utilized in the purification of Bk(IV) by extraction from a nitrate solution into a n-heptane solution of di 2-ethyl hexyl phosphoric acid, HDEHP.