P2-38 Studies of dissolution solutions of ruthenium metal, oxide and mixed compounds in nitric acid F. Mousset 1, C. Eysseric1, F. Bedioui2 1CEA DEN/SE2A, Valrhô-Marcoule, BP 17171, 30207 Bagnols-sur-Cèze Cedex, France 2Laboratoire de Pharmacologie Chimique et Génétique, FRE CNRS-ENSCP n°2463, École Nationale Supérieure de Chimie de Paris, 11 rue Pierre et Marie Curie, 75231 Paris Cedex 05, France Abstract – Ruthenium is one of the fission products generated by irradiated nuclear fuel. It is present throughout all the steps of nuclear fuel reprocessing —particularly during extraction—and requires special attention due to its complex chemistry and high bg activity. An innovative electrovolatilization process is now being developed to take advantage of the volatility of RuO4 in order to eliminate it at the head end of the PUREX process and thus reduce the number of extraction cycles. Although the process operates successfully with synthetic nitrato-RuNO3+ solutions, difficulties have been encountered in extrapolating it to real-like dissolution solutions. In order to better approximate the chemical forms of ruthenium found in fuel dissolution solutions, kinetic and speciation studies on dissolved species were undertaken with RuO2,xH2O and Ru° in nitric acid media. INTRODUCTION on two reactions. It consists in oxidizing a synthetic nitrato-nitrosyl-ruthenium complex (RuNO3+) in nitric Ruthenium is one of the chemical elements present acid, using Ag(II) electrochemically generated at a in solutions treated in nuclear fuel reprocessing based on platinum anode [4-7] as a strong oxidant. The volatile the PUREX process. It exhibits specific behavior during RuO4 formed is then desorbed from the electrolytic the process because of its relative abundance (6% of solution by flowing nitrogen and trapped in a suitable fission products), high activity (due to isotopes 103Ru liquid phase. and 106Ru) and complex chemistry (more than 25 species Although the feasibility of a process of this type is at several oxidation states). Multiple oxidation and well established for the simple synthetic nitrato-nitrosyl- coordination states of ruthenium are present in the nitric ruthenium RuNO3+ solution, further investigation is acid media and encountered in reprocessing, including necessary to better understand the differences observed nitrato complexes of nitrosyl ruthenium, colloids with during extrapolation to nuclear fuel dissolution. For this organophosphates in liquid phases, and ruthenium purpose, RuO2,xH2O and Ru° were dissolved in nitric tetroxide (RuO4) in the off-gas. In an advanced acid for electrovolatilization studies [8]. This paper reprocessing concept it would be an improvment to discusses the speciation and kinetic studies for these separate the ruthenium from the concentrated flows simulated dissolution tests. during the early process steps. Methods for removing ruthenium within the EXPERIMENTAL PUREX process have thus been developed for synthetic or high-level waste solutions. Their principle consists in Chemicals first oxidizing ruthenium species to the volatile RuO4 form, followed by selective separation. Oxidation can be Nitric acid solutions (3N, 6N, 10N) were prepared performed either by adding a strong oxidant [1] from concentrated HNO3 (Merck, rectapur grade, 65%). (KMnO4, K2Cr2O7 or ozone) or electrochemically [2,3]. RuO2,xH2O powder (x = 4.3, Aldrich; mean particle The resulting RuO4 is then removed by precipitation as diameter 11 µm) and Ru° metal powder (Aldrich, insoluble RuO2 through electrochemical reduction or micrometric) were used. A solution of nitrato-nitrosyl- using chemical reducing agents such as hydrazine. This ruthenium complex, with the general formula 3-x-y approach involving the use of additional reactants is RuNO(NO3)x(NO2)y(H2O)z (x+y+z = 5), designated unsuitable because of the increased quantities of high- RuNO3+ in the remainder of this document, was level waste requiring subsequent treatment. A simpler prepared using a commercial powder RuNO(NO3)3 and more elegant way is to take advantage of the (Aldrich, 31.3% ruthenium) which is easily dissolved at volatility of RuO4 to ensure its desorption. room temperature in nitric acid. A Ru(IV) standard In a context of sustainable development, electro- solution was obtained using H2O2 to reduce RuO4 chemistry is well suited for oxidation of the ruthenium freshly prepared by dissolution of 5 mM of KRuO4 species and could be easily coupled with RuO4 powder (Aldrich) in concentrated nitric acid. According desorption by simple gas flow. An overall conceptual to Anderson and McConnell [9], the properties of the ruthenium separation process has been developed based resulting solution are consistent with the hypothesis that ATALANTE 2004 Nîmes (France) June 21-25, 2004 1 P2-38 35 it contains a series of hydroxo aquo ruthenium T = 100°C FM56ICP 30 complexes of tetravalent ruthenium that could be FM54ICP 4+ FM57ICP formulated as Ru (OH) and is designated here as 10N 4 12 25 Ru(IV). The sodium nitrite solution (7 mol·L-1) is 20 obtained by dissolution of NaNO2 powder (Aldrich) in mg/L H2O (MilliQ). 15 6N Analysis of ruthenium solutions 10 3N The amount of ruthenium in the dissolution solution 5 was determined by ICP/AES analysis (Jobin Yvon). 0 0 20 40 60 80 100 120 140 160 180 UV-visible spectrophotometry measurements used to Time (min) characterize various ruthenium forms as RuNO3+ or Figure 2. Effect of HNO concentration on the Ru(IV) were performed with a Cary spectrometer (1A 3 dissolution kinetics of RuO2,xH2O at 100°C model). -1 -1 Table I. RuO2,xH2O dissolution rate (µg·L min ) Dissolution Reactor versus nitric acid concentration and temperature The dissolutions were carried out in two [HNO3] experimental setups (Figure 1). The first series used a Temperature four-necked 1 L flask and cooler with a Lauda 3°C 3 N 6 N 10 N cryostat. A Bioblock modular heater was used to 85°C 3 regulate the dissolution temperature via a temperature 100°C 31 90 175 sensor immersed in solution. A sampling valve was 107°C 334 fitted on one of the necks. The second series of dissolutions was performed with the same setup coupled periodic solution samples. The [Ru] = f(t) curves to a nitrogen oxide (NOx) generator consisting of a 1 L showed a linear variation during the first 200 minutes, flask containing 10 N nitric acid heated to 50°C. A -1 from which an initial dissolution rate r0 was determined 1 mm dia. PTFE connection supplied a 7 mol·L sodium (Figures 1, 2, 3). nitrite solution from a peristaltic pump to the 10 N nitric Figure 2 shows the ruthenium concentration in acid in the generator to produce nitrogen oxides. They solution versus time at three acidities (3 N, 6 N and were desorbed by sparging nitrogen at 1.5 L·min-1 in the 10 N) during dissolution of RuO2,xH2O. The higher the NOx generator, which was connected via a hermetic line nitric acid concentration, the faster the dissolution to the dissolution reactor. The vector gas thus carried the kinetics. The dissolution rates are indicated in Table I. nitrogen oxides into the nitric acid dissolution solution, The results indicated an apparent reaction order of generating nitrous acid in situ. approximately 2 with respect to HNO3: NOx generator Ruthenium dissolver 2 r0 a [HNO3] (1) To NOx trapping Figure 3 illustrates the effect of temperature on the Condenser dissolution kinetics at 85°C, 100°C and 107°C (boiling) Vector gas supply column in 6 N HNO3. The apparent activation energy calculated NOx flux 70 Temperature FM53ICP probe FM54ICP 60 Sampling FM55ICP device 107°C 50 40 Sodium nitrite Nitric acid acidification Regulated heater mg/L solution supply 30 Figure 1. Diagram of the experimental devices 20 100°C 10 85°C RESULTS AND DISCUSSION 0 0 20 40 60 80 100 120 140 160 180 200 Kinetic studies Time (min) The dissolution kinetics was established by Figure 3. Effect of temperature on the dissolution kinetics of RuO2,xH2O, [HNO3] = 6 N ICP-AES determination of the dissolved ruthenium in ATALANTE 2004 Nîmes (France) June 21-25, 2004 2 P2-38 from these dissolution rates is: Moreover, different chemical forms of the initial solid ruthenium can be postulated. It is often assumed E¢ = 246 kJ/mol (2) a [10] that a large fraction of ruthenium in the spent fuel is Experiments with NOx sparging revealed the major found as polymetallic compounds alloyed with influence of this parameter. Figure 4 shows the varia- molybdenum, palladium, rhodium and technetium. tion of the dissolved ruthenium for three different These alloys (e phase) are known as “white inclusions”. nitrous acid concentrations obtained by increasing NOx Initially, dissolution tests were undertaken with gas generation parameters. The increasing HNO2 micrometer size Ru° metal powder in addition to concentration in solution resulted in increased dissolu- RuO2,xH2O dissolutions. As shown in Table III, only tion kinetics as indicated in Table II. The apparent order high acidity and high temperatures in the presence of of the nitrous acid concentration was 0.5: nitrous acid are capable of obtaining kinetics that can be 0.5 quantified by ICP-AES, but remain very slow. r0 a [HNO2] (3) Table III. Dissolution rate r0 of Ru metal powder Table II. RuO2,xH2O dissolution rate versus nitrous for various temperatures, nitric acidities acid concentration (T = 100°C, [HNO3] = 6 N) and nitrous acid concentrations 3 -1 [HNO2] (×10 mol·L ) T [HNO3] [HNO2] r0 (°C) (N) ×103 (mol·L-1) (µg·L-1·min-1) 1.5 4.5 24.5 107 3 - < 0.5 Dissolution rate 69 86 268 (µg·L-1min-1) 117 10 - < 0.5 117 10 24.5 4.5 60 - 2 - 1 Dissolution tests with polymetallic Ru-Mo and Ru- [HNO 2] = 2.45 × 10 mol·L 50 Mo-Pd alloys are now in progress to identify possible synergistic effects during the dissolution of alloyed 40 - 3 - 1 elements and to assess the increased representativeness [HNO 2] = 4.5 × 10 mol·L of these alloys compared with spent fuel.