United States Patent N* **Si^Imblec0fy Lll] 3'891'741
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lll] 3 891 741 United States Patent n* **si^IMBLEC0Fy ' ' Carlin et al. [45] June 24, 1975 [54] RECOVERY OF FISSION PRODUCTS FROM Bray, Non-Ferrous Production Metallurgy, 2d Ed. ACIDIC WASTE SOLUTIONS THEREOF 1947, John Wiley & Sons, Inc. pp. 416-417, [TN/665/B75n], [75] Inventors: William W. Carlin, Portland; Bailar et al. Comprehensive Inorganic Chemistry, Per- William B. Darlington; Donald W. gamon Press, 1973, pp. 1 170-1173, [QD151.2/C6]. Dubois, both of Corpus Christi, all of Tex. Primary Examiner—Leland A. Sebastian [73] Assignee: PPG Industries, Inc., Pittsburgh, Pa. Attorney, Agent, or Firm—Irwin M. Stein [22] Filed: Nov. 24, 1972 [57] ABSTRACT [21] Appl. No.: 309,377 Fission products, e.g., palladium, ruthenium and tech- netium, are removed from aqueous, acidic waste solu- [52] U.S. CI 423/2; 23/300; 75/121; tions thereof. The acidic waste solution is electrolyzed 203/95; 204/109; 252/301.1 R; 423/49 in an electrolytic cell under controlled cathodic poten- [51 ] Int. CI COlg 55/00; COlg 57/00 tial conditions and technetium, ruthenium, palladium [58] Field of Search 252/301.1 R, 301.1 W; and rhodium deposited on the cathode. Metal deposit 423/2, 22, 49, 249; 204/105, 109 is removed from the cathode and dissolved in acid. Acid insoluble rhodium metal is recovered, dissolved [56] References Cited by alkali metal bisulfate fusion and purified by elec- UNITED STATES PATENTS trolysis. In one embodiment, the solution formed by acid dissolution of the cathode metal deposit is treated 2,895,889 7/1959 Schumpelt 204/47 3,309,292 3/1967 Andrews 204/39 with a strong oxidizing agent and distilled to separate 3,374,157 3/1968 Box 204/45 R technetium and ruthenium (as a distillate) from palla- 3,672,875 6/1972 MacCragh 252/301.1 RX dium. Technetium is separated from ruthenium by or- 3.708,508 1/1973 Schultz 423/22 X ganic solvent extraction and then recovered, e.g., as an ammonium salt. Ruthenium is disposed of as waste OTHER PUBLICATIONS by-product. Palladium is recovered by electrolysis of Lingane, Electroanlytical Chemistry, 2d Ed. 1958, In- an acid solution thereof under controlled cathodic po- terscience Publishers, Inc., pp. 416-420, [QD tential conditions. Further embodiments wherein al- 553/L5/C.2] ternate metal recovery sequences are used are de- Korkisch, Modern Methods for the Separation of scribed. Raier Metals Ions, 1969, Pergamon Press, pp. 512-513, 520, [QD 63/S4K6], 23 Claims, 3 Drawing Figures RHODIUM PALLADIUM PRODUCT PRODUCT RHODIUM PALLADIUM PRODUCT PRODUCT ACIDIC WASTE (PAW) Tc>Ru,Pd, Rh —O ELECTROLYTIC Fl LTER FIG.2 CELL 1 PO METALS ACID -4. AQUEOUS PYRIDINE REMOVAL —COJ Rh PHASE (Ru,Pd) RECYCLE CJl (SOLID) ALKALINE , REAGENT MIXING RHODIUM ORGANIC STEAM 1 T EXTRACTION SEPARATION Tc,Ru,Pd SETTLING PHASE (Tc,Pd) DISTILLATION •|fth(SOLlD) > KH S04 RHODIUM AQUEOUS PHASE(TCjPd) PYRIDINE 7 DI SSOLUTION ro MOTHER LIQUOR PRECIPITATION NH4OH RECYCLE •WATER ACID CRYSTALLIZATION ELECTROLYTIC ; NH4TGO4 ELECTROLYTIC J tPRODUCT CELL CELL DEPLETED 2 4 DEPLETED OJ CELL LIQUOR CELL LIQUOR (Tc) CO CD HCI RHODIUM PALLADIUM * REMOVAL REMOVAL PRECIPITATION ""f f 1 RHODIUM PALLADIUM T MOTHER PRODUCT PRODUCT Pd(NH3)2CI2 LIQUOR t=3 rv> —CD J cn oo CO CO "00 CO H PALLADIUM PRODUCT 3,906,2337 669 1 RECOVERY OF FISSION PRODUCTS FROM recovery of palladium, rhodium and technetium from ACIDIC WASTE SOLUTIONS THEREOF such aqueous alkaline waste solutions have been pro- posed. See, for example, U.S. application for Pat. Ser. DESCRIPTION OF THE INVENTION No. 309,015, filed Nov. 24, 1972, in the names of Wil- The present invention relates to the treatment of 5 liam W. Carlin and William Bruce Darlington and enti- aqueous solutions containing fission products, e.g., pal- tled RECOVERY OF FISSION PRODUCTS FROM ladium, rhodium, technetium and ruthenium, most no- WASTE SOLUTIONS THEREOF. tably, aqueous, acidic waste solutions containing fission With the increasing number of nuclear fuel reactors products obtained in processing neutron-irradiated nu- being built and proposed for electric power generation, clear fuel elements. In the conventional operation of 10 there is need for improved methods for processing radi- uranium-fuel nuclear reactors, it is necessary to process oactive liquid wastes. Announcements from the United the reactor fuel elements periodically to decontaminate States Atomic Energy Commission indicate that highly and purify them in order to sustain continued opera- radioactive liquid wastes will be required to be pro- tion. In the fission reaction, an atom of fissionable ura- cessed for disposal within five years of their formation. nium isotope, upon absorbing a neutron, splits, thereby 15 Although the aqueous waste stream produced by nu- forming at least two smaller atoms and emitting a plu- clear fuel processing contain palladium, rhodium and rality of neutrons. These neutrons pass through the fuel technetium at a parts per million concentration, the element where they can be absorbed by another atom amount of the aforesaid metals present in such aqueous of fissionable uranium isotope thereby inducing its fis- wastes is significant because of the large volume of the sion and propagating the chain reaction. The smaller 20 aqueous waste produced. It has been estimated that by atoms resulting from the splitting action, together with 1980 more rhodium per year will be made by the nu- their radioactive decay products, are termed "fission clear industry than will be consumed in the United products". These fission products comprise isotopes States. Technetium is not found naturally in nature, but having atomic numbers ranging predominantly from 30 it is produced by the aforementioned fission process to 63 and largely remain intimately dispersed and en- 25 and has been produced by neutron irradiation of mo- trapped within the fuel element. Among such fission lybdenum. See, for example, U.S. Pat. No. 3,382,152. products are species that are highly neutron-absorptive Rhodium and palladium are both rare in nature. Thus, and thus deleteriously serve to intercept and drain the potential dollar value of the aforesaid metals in away neutrons produced during fission so as to attenu- such aqueous waste stream is high. ate the further propagation of the chain reaction. Ac- 30 In accordance with the present process, fission prod- cordingly, a fuel element, upon attaining enough rela- ucts, e.g., technetium, rhodium and palladium, are re- tive fission product concentration, is customarily dis- covered by treatment of an aqueous acidic waste charged from the reactor and processed to eliminate stream produced by nuclear fuel processors. More spe- fission product contamination and to isolate and re- cifically, the highly acidic aqueous waste stream cover the remaining bulk of the uranium. 35 (PAW), which generally has an acid concentration of One such recovery process is known as the Purex about 8 molar, is filtered to recover undissolved rho- process, which is fully described in U.S. Pat. No. dium and the filtrate treated with alkaline reagent until 2,990,240, issued June 27, 1961, in the names of its acid concentration is reduced to about one molar or Charles N. Ellison and Thomas C. Runion and entitled less, preferably about 0.25 molar. Alternatively, the PROCESS FOR SEGREGATING URANIUM FROM 40 waste stream can be partially neutralized first and then PLUTONIUM AND FISSION PRODUCT CONTAMI- filtered to recover the rhodium metal. The partially NATION. In the Purex process, fuel elements from nu- neutralized liquid (filtrate) is electrolyzed in a first clear reactors are dissolved in nitric acid. The pluto- electrolytic cell under controlled cathodic potential nium, uranium and neptunium therein are recovered by conditions and at a potential at which technetium is de- tri-n-butyl phosphate solvent extraction leaving the ma- posited upon the cathode. At such a potential, palla- jority of fission products, including palladium, rhodium dium and rhodium, as well as ruthenium, will also be and technetium, in the acidic aqueous wastes, which deposited on the cathode. Following electrolysis, the are termed Purex acid wastes (PAW). The process pro- electrolytic cell liquor, depleted of the aforementioned duces approximately 800 liters of liquid radioactive 5Q metals, is returned to the nuclear fuel processor. waste material per metric ton of uranium fuel pro- The metals deposited on the cathode are removed, cessed. Heretofore, the Purex acid wastes have been either mechanically or chemically, e.g., by dissolution neutralized with sodium carbonate and stored in large with acid. Rhodium, which is substantially insoluble in underground tanks designed to contain this self-boiling, acid, is removed as a solid from the resulting acid solu- highly radioactive solution. After four to five years of 55 tion by filtration and purified. Purification can be ac- storage, the radioactivity of the solution diminishes to complished by dissolving the rhodium by alkali metal, the point where the solution becomes non-boiling and e.g., sodium or potassium, bisulfate fusion techniques the majority of fission products settle to the bottom of and electrolysis of an acidic, aqueous solution prepared the tank in a layer of sludge. from the melt. The supernatant aqueous phase in the storage tank 6Q In one embodiment of the present process (FIG. 1), contains most of the cesium, strontium, rhodium, palla- the acid solution of metals removed from the cathode dium, ruthenium and technetium in solution. Most of of the first electrolytic eel) is treated with a strong oxi- the highly radioactive cesium and strontium are selec- dizing agent, such as perchloric acid, and distilled to tively removed from the supernatant leaving, in solu- thereby separate ruthenium and technetium as volatile tion, salts of rhodium, palladium, technetium, ruthe- 65 oxides from the palladium. The remaining aqueous, nium, sodium and low levels of other fission products.