Partitioning of Radionuclides in Various Streams of the Mo-99 Purification Process

Technical Report · Mon May 01 04:00:00 EDT 2023

DOI:https://doi.org/10.2172/1984830· OSTI ID:1984830

Servis, Anna G. ^[1]; Kalensky, Michael ^[1]; Chemerisov, Sergey D. ^[1]; Gromov, Roman G. ^[1]; Alford, Kurt ^[1]; Wesolowski, Kenneth A. ^[1]; Bailey, James L. ^[1]; Patapenka, Andrei S. ^[1]; Hlavenka, Josh ^[1]; Jonah, Charles D. ^[1]; Mullins, David ^[1]; Tkac, Peter ^[1]

---

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

The Universal Neutron Irradiator (UNI) was designed to irradiate a small volume of uranium solution and to achieve high fission power without creating a large radionuclide (RN) inventory. The UNI system is equipped with a fully enclosed off-gas system with online hydrogen gas monitoring to prevent the production of an explosive atmosphere, as well as storage cylinders for capturing fission gases. It also includes a catalytic recombiner in the target capsule (to immediately recombine radiolytic hydrogen and oxygen gas in the system) and access ports for sampling the target solution and capsule headspace. In UNI Phase I experiments, 50 mL of uranyl sulfate solution was irradiated at 0.3–0.5 W/mL fission power using a tantalum target assembly to produce photoneutrons via irradiation with an electron beam. The purposes of the Phase I experiments were to test the efficacy of adding 200 ppm Fe²⁺ to the target solution to prevent uranyl peroxide precipitation under representative irradiation conditions, and to monitor iodine speciation in the irradiated uranyl sulfate solution. The focus of the UNI Phase II experiments was to use an irradiated uranyl sulfate solution containing a mixture of fission products and monitor their distribution in various streams during the primary recovery column (titania-based column) that separates Mo-99 from uranium. Irradiations were designed to create sufficient activity for tracking their distribution in various processing streams using a combination of gamma counting and inductively coupled plasma mass spectrometry (ICP-MS) analyses. Obtained data will be used to better understand the composition of waste streams, accumulation of RN on the titania column, and identify what RNs accumulate in the uranyl sulfate solution. Furthermore, this knowledge will allow us to determine waste classifications for various streams produced during the Mo-99 purification process and develop an appropriate waste clean-up strategy.

• Research Organization: Argonne National Laboratory (ANL)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1984830
• Report Number(s): ANL--23/30; 182753
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS