Higher Oxidation States of Americium - American Chemical Society

Jul 5, 2011 - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States ... common +III oxidation state, which is in close analog...
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Higher Oxidation States of Americium: Preparation, Characterization and Use for Separations Wolfgang H. Runde*,† and Bruce J. Mincher‡ †

G.T. Seaborg Institute for Transactinium Science, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545, United States ‡ Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States

CONTENTS 1. Introduction 2. Preparation of Higher Valence States 2.1. Americium(IV) 2.2. Americium(V) 2.3. Americium(VI) 3. Characterization 3.1. Absorption Spectroscopy 3.2. Vibrational Spectroscopy 3.3. X-ray Absorption Spectroscopy 4. Redox Potentials and Thermodynamic Properties 4.1. Am(IV)/(III) 4.2. Am(V)/Am(III) 4.3. Am(VI)/Am(III) 4.4. Am(VI)/(V) 4.5. Am(VII)/(VI) 4.6. Thermodynamic data for Am(IV), Am(V), and Am(VI) 5. Radiolysis Effects on Americium Speciation 6. Redox Reactions of Am(IV), (V), and (VI) 6.1. Reduction of Am(IV) 6.2. Reduction of Am(V) 6.3. Reduction of Am(VI) 6.4. Disproportionation of Am(IV) 6.5. Disproportionation of Am(V) 7. High-Valent Americium in Separations 7.1. Separation by Precipitation 7.2. Separation by Extraction 7.3. Ion Exchange Chromatography 8. Concluding Remarks Author Information Biographies References

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1. INTRODUCTION Today, there is a renewed worldwide interest in nuclear power, and this has initiated renewed research and development efforts for advanced nuclear fuel cycles. Responsible nuclear waste management and efficient use of uranium resources will almost certainly result in the recycling of used nuclear fuel. Current approaches r 2011 American Chemical Society

would partition americium to be transmuted to short-lived fission products in fast reactor fuel, rather than interring it in a high-level waste repository. Consequently, methods to separate americium from the lanthanides and higher actinides, a historically problematic separation, are being sought to be implemented on the process scale. There are two main approaches being investigated in those countries in Asia, Europe, and North America that are interested in reprocessing nuclear fuel. One approach is the use of soft-donor ligands that preferentially complex the actinides in favor of the lanthanides. The other approach is to utilize higher oxidation states of americium (i.e., IV, V, or VI) that exhibit solution chemistries quite different than that of the predominantly trivalent lanthanides and curium. Isotopes of americium, element number 95, are produced in nuclear power reactors as a byproduct of the irradiation of uranium with neutrons. The amount of americium generated in the fuel depends greatly on the reactor type, the nature of the fuel irradiated, and the irradiation parameters for burn-up, the amount of americium formed in neutron-irradiated UO2 fuel is generally small compared to the plutonium fraction. The main americium isotopes in used nuclear fuel are 241Am (t1/2 = 423.7 years), 242m Am (t1/2 = 141 years), and 243Am (t1/2 = 7380 years).1 Croff calculated about 0.06 wt % americium isotopes to be present at discharge in neutron-irradiated UO2 fuel.2 With time the activity of most of the americium isotopes declines, however, 241Am builds up because of the decay of 241Pu.2,3 As an example, after 10 years of decay, Binney and co-workers calculated that used, but nonreprocessed nuclear fuel from pressurized water reactors contains 594 g of americium per metric ton uranium (503 g of 241 Am/MTU, 0.66 g of 242 mAm/MTU, and 90.6 g of 243Am/ MTU).4 Americium isotopes are a part of the minor actinide fraction in used nuclear fuel that must be partitioned from the other actinides and fission products for transmutation or waste disposition. Americium is located near the middle of the 5f-series of the actinide elements, and its redox chemistry is far less rich than that of the preceding actinides neptunium and plutonium. In general, the aqueous solution chemistry of americium is determined by its common +III oxidation state, which is in close analogy to its chemical lanthanide congener europium. The trivalent valence is normally encountered unless special efforts are made to oxidize the element to its higher oxidation states Am(IV), Am(V) and Am(VI), which were discovered in the 19501960s. By the end of the 1960s the descriptive chemistry of oxidized americium had been characterized, and the ions were known to exist as Am4+, AmO2+, and AmO22+, analogous to the behavior of uranium, Received: June 10, 2010 Published: July 05, 2011 5723

dx.doi.org/10.1021/cr100181f | Chem. Rev. 2011, 111, 5723–5741

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Table 1. Most Common Routes to Synthesize Am(IV), (V), and (VI) oxidation state Am(IV)

conditions

starting material

ref

0.6 M NaOCl in 0.2 M NaOH

Am(OH)3

6

dissolution in 13 M NH4F

Am(OH)4

7

electrochemical (16 mA/2 V) in 1015 M H3PO4

Am(III)

8

0.01 M Ag3PO4/0.05 M (NH4)2S2O8 in 12 M H3PO4

Am(III)

9

0.1 M K2S2O8 and excess K10P2W17O61 at 98 °C

Am(III)

10

104 M AgNO3/0.03 M (NH4)2S2O8 and excess K10P2W17O61

Am(III)

11

0.5 M KBrO3 or 0.2 M K2Cr2O7 and excess K10P2W17O61 in