U, Np, and Pu L(II,III)-edge X-ray absorption fine structure (XAFS) spectra were collected for the UO(2)(2+), NpO(2)(+), Np(4+), and Pu(3+) ions as a function of chloride concentration in aqueous solution. At low chloride concentration, the hydration numbers and corresponding bond lengths for the different ions are as follows: UO(2)(2+), N= 5.3, R = 2.41 Å; NpO(2)(+), N = 5.0, R = 2.50 Å; Np(4+), N = 11.2, R = 2.40 Å; Pu(3+), N = 10.2, R = 2.51 Å. As the Cl(-) concentration increases, inner-sphere Cl(-) complexation occurs, resulting in a decrease in the hydration numbers and an expansion of the actinide-oxygen (water) bond lengths. The Pu(3+) ion shows only a decrease in hydration number (40%) and no inner-sphere Cl(-) complexation for [Cl(-)] < 14 M. For concentrations up to 10-14 M Cl(-), the average Cl(-) coordination numbers and bond lengths are as follows: UO(2)(2+), N = 2.6, R = 2.73 Å; NpO(2)(+), N = 1.0, R = 2.84 Å; Np(4+), N = 2.0, R = 2.61 Å. Structural changes are observed in the near-edge spectral region as shown by significant changes in the white line intensities upon Cl(-) complexation. For ions with similar structures, i.e. Pu(3+) and Np(4+) or the actinyl ions NpO(2)(+) and UO(2)(2+), positive energy shifts are observed with increasing oxidation state. The ability to use XAFS speciation results to calculate equilibrium constants and the relationship of these results to previous studies are discussed.

We have used EXAFS spectroscopy to investigate the inner sphere coordination of trivalent lanthanide (Ln) and actinide (An) ions in aqueous solutions as a function of increasing chloride concentration. At low chloride concentration, the hydration numbers and corresponding Ln,An-O bond lengths are as follows: La3+, N = 9.2, R = 2.54 A; Ce3+, N = 9.3, R = 2.52 A; Nd3+, N = 9.5, R = 2.49 A; Eu3+, N = 9.3, R = 2.43 A; Yb3+, N = 8.7, R = 2.32 A; Y3+, N = 9.7, R = 2.36 A; Am3+, N = 10.3, R = 2.48 A; Cm3+, N = 10.2, R = 2.45 A. In ca. 14 M LiCl, the early Ln3+ ions (La, Ce, Nd, and Eu) show inner sphere Cl- complexation along with a loss of H2O. The average chloride coordination numbers and Ln-Cl bond lengths are as follows: La3+, N = 2.1, R = 2.92 A; Ce3+, N = 1.8, R = 2.89 A; Nd3+, N = 1.9, R = 2.85 A; Eu3+, N = 1.1, R = 2.81 A. The extent of Cl- ion complexation decreases going across the Ln3+ series to the point where Yb3+ shows no Cl- complexation and no loss of coordinated water molecules. The actinide ions, Am3+ and Cm3+, show the same structural effects as the early Ln3+ ions, i.e., Cl- ion replacement of the H2O at high chloride thermodynamic activities. The Clion coordination numbers and An-Cl bond lengths are: Am3+, N = 1.8, R = 2.81 A; Cm3+, N = 2.4, R = 2.76 A. When combined with results reported previously for Pu3+ which showed no significant chloride complexation in 12 M LiCl, these results suggest that the extent of chloride complexation is increasing across the An3+ series. The origin of the differences in chloride complex formation between the Ln3+ and An3+ ions and the relevance to earlier work is discussed.

Sterically pressured mid- to high-valent uranium complexes with an aryloxide substituted triazacyclononane ligand scaffold, [(((R)ArO)3tacn)(3-)], were studied for carbon dioxide activation and transformation chemistry. The high valent uranium(V) imido species [(((R)ArO)3tacn)U(NR)] (R = (t)Bu, R' = 2,4,6-trimethylphenyl (2-(t)Bu); R = Ad, R' = 2,4,6-trimethylphenyl (2-Ad); R = (t)Bu, R' = phenyl (3-(t)Bu)) were synthesized and spectroscopically characterized. X-ray crystallography of the tert-butyl mesityl imido derivative, 2-(t)Bu , reveals coordination of a bent imido fragment with a relatively long U-N bond distance of 2.05 A. The mesityl imido complexes reacted with carbon dioxide, readily extruding free isocyanate to produce uranium(V) terminal oxo species, [(((R)ArO)3tacn)U(O)] (R = (t)Bu (4-(t)Bu), Ad (4-Ad)), presumably through multiple bond metathesis via a uranium(V) carbimate intermediate. Using the smaller phenyl imido fragment in 3-(t) Bu slowed isocyanate loss, allowing the uranium(V) carbimate intermediate to undergo a second metathesis reaction, ultimately producing the diphenyl ureate derivative, [(((tBu)ArO)3tacn)U(NPh2)CO] (5-(t)Bu). Single crystal X-ray diffraction studies were carried out on both uranium(V) terminal oxo complexes and revealed short U-O bonds (1.85 A) indicative of a formal UO triple bond. The electronic structure of the oxo U(V) complexes was investigated by electronic absorption and EPR spectroscopies as well as SQUID magnetization and DFT studies, which indicated that their electronic properties are highly unusual. To obtain insight into the reactivity of CO2 with U-N bonds, the reaction of the uranium(IV) amide species, [(((R)ArO)3tacn)U(NHMes)] (R = (t)Bu (6-(t)Bu), Ad (6-Ad) with carbon dioxide was investigated. These reactions produced the uranium(IV) carbamate complexes, [(((R)ArO)3tacn)U(CO2NHMes)] (R = (t)Bu (7-(t)Bu), Ad (7-Ad)), resulting from insertion of carbon dioxide into U-N(amide) bonds. The molecular structures of the synthesized uranium carbamate complexes highlight the different reactivities due to the steric pressure introduced by the alkyl derivatized tris(aryloxide) triazacyclononane ligand. The sterically open tert-butyl derivative creates a monodentate eta(1)-O bound carbamate species, while the sterically more bulky adamantyl-substituted compound forces a bidentate kappa(2)-O,O coordination mode of the carbamate ligand.

Cementitious waste forms (CWFs) are an important component of the strategy to immobilize high-level nuclear waste resulting from plutonium production by the U.S. Department of Energy (DOE).Technetium ( 9 9 Tc) is an abundant fission product of particular concern in CWFs due to the high solubility and mobility of pertechnetate, TcO 4 -, the stable form of technetium in aerobic environments. CWFs can more effectively immobilize 9 9 Tc if they contain additives that reduce mobile TcO 4 -to immobile Tc(IV) species. Leaching of 9 9 Tc from reducing CWFs that contain Tc(IV) is much slower than for CWFs containing TcO 4 -. Previous X-ray absorption fine structure (XAFS) studies showed that he Tc(IV) species were oxidized to TcO 4 -in reducing grout samples prepared on a laboratory scale. Whether the oxidizer was atmospheric O 2 or NO 3 -in the waste simulant was not determined. In actual CWFs, rapid oxidation of Tc(IV) by NO 3 -would be a concern, whereas oxidation by atmospheric O 2 would be of less concern due to the slow diffusion and reaction of O 2 with the reducing CWF. To address this uncertainty, two series of reducing grouts were prepared using TcO 4 -containing waste simulants with and without NO 3 -. In the first series of samples, the TcO 4 -was completely reduced using Na 2 S, and the samples were placed in containers that permitted O 2 diffusion. In these samples, all of the technetium was initially present as a Tc(IV) sulfide compound, TcS x , which was characterized using extended X-ray absorption fine structure (EXAFS) 2 spectroscopy, and is likely Tc 2 S 7 . The TcS x initially present in the grout samples was steadily oxidized over 4 years. In the second series of samples, all of the TcO 4 -was not initially reduced, and the grout samples were placed in airtight containers. In these samples, the remaining TcO 4 -continued to be reduced as the samples aged, presumably due to the presence of reducing blast furnace slag. When samples in the second series were exposed to atmosphere, the lower-valent technetium species were rapidly oxidized to TcO 4 -.KEYWORDS technetium, cement, grout, nuclear waste BRIEFS The speciation of technetium in reducing grout samples was followed using X-ray absorption fine structure spectroscopy. The reduced technetium species were susceptible to oxidation by oxygen, but nitrate had no observable effect over the duration of the experiment. MANUSCRIPT TEXTIntroduction Immobilization of the high-level nuclear waste created during plutonium production by