Corrosion of 347 stainless steel in the presence of uranyl sulfate solution and radiation

Technical Report · Thu Jul 01 04:00:00 EDT 2021

DOI:https://doi.org/10.2172/1814820· OSTI ID:1814820

Gattu, Vineeth K. ^[1]; Obregon, Javier E. ^[1]; Quigley, Kevin J. ^[1]; Patapenka, Andrei ^[1]; Chemerisov, Sergey D. ^[1]; Byrnes, James P. ^[1]; McLain, Derek ^[1]; Indacochea, Ernesto J. ^[1]; Tkac, Peter ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

The U.S. molybdenum 99 (Mo-99) industry is pursuing production of fission-made Mo-99 using a uranium solution such as uranyl sulfate. In this process, uranyl sulfate solution containing low-enriched uranium will be bombarded by neutrons creating Mo-99 and other fission products. During the production, the uranyl sulfate solution will be irradiated until an acceptable activity level of Mo-99 is produced. The uranyl sulfate solution containing Mo-99 and other fission products will then undergo a series of separation steps. First, uranyl sulfate can be separated from Mo-99 using a primary titania column to recover Mo-99, with the uranyl sulfate solution to be used for another irradiation cycle. Then, raffinate from a primary titania column containing Mo-99 can be concentrated and purified using a LEU modified Cintichem process developed by Argonne National Laboratory. During irradiation, the temperature of the uranyl sulfate solution can reach near boiling (up to ~80° C assumed), causing radiolysis of water and the resultant formation of hydrogen peroxide. Because high-radiation fields will be present during each irradiation cycle, it is important to determine the corrosion rates of SS-347 under such conditions to estimate the life cycle of the target solution vessel. The buildup of corrosion products from the SS components in the uranyl sulfate solution also needs to be well understood because potential accumulation of iron, nickel, and other corrosion products may affect the Mo-99 recovery and purification process. To study the corrosion rates of SS-347 material under conditions relevant to future Mo-99 production facility, SS-347 coupons in uranyl sulfate solution at ~80° C were irradiated using Argonne’s Van de Graaff generator, which can generate high-radiation fields without fissioning of uranium or production of activation products.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation. Office of Material Management and Minimization (M3)
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1814820
• Report Number(s): ANL-21/30; 170296
• Country of Publication: United States
• Language: English

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