Nuclear Technology Posters

An Advanced Recycle Treatment Facility Based on Pyrochemical Separations Techniques

Arthur A. Frigo, Dale R. Wahlquist, and John L. Krazinskic

The Advanced Fuel Cycle Initiative focuses on recycle of spent fuel to optimize the utilization of the first geological repository. New recycle technologies are required that are more proliferation-resistant and cost-competitive than existing alternatives. Among the technologies being developed to meet these goals are pyroprocesses that build on the success of the demonstration of EBR-II metallic fuel treatment. A primary thrust of research in the pyroprocess area has been to develop the individual unit operations required to treat spent fuel. So far, general process flowsheets and much of the viability demonstrations have been completed. However, integration of the unit operations into an operational facility is needed to provide an economical recycle process. The focus of the research depicted in this poster is to start this integration by determining the overall requirements to encompass the needs of the process, facility, mechanical and electrical equipment design, operations, maintenance and safeguarding, and to translate these requirements into a conceptual design of an actual treatment facility.

This research is supported by Laboratory Director Research and Development (LDRD) funds.

Contact Art Frigo (630-252-4351, frigo@cmt.anl.gov). View Poster

Direct Electrolytic Reduction of Oxides

Karthick Gourishankar, Laszlo Redey, and Mark Williamson

Argonne has developed a direct electrolytic reduction process for converting oxides to metals with application in the recovery of actinides from spent oxide fuels. The reduction occurs by a solid-state electrochemical transformation without the need for dissolution of the feed oxide in the electrolyte. The oxygen in the solid-oxide charge is ionized into a soluble species at the cathode, leaving behind the reduced metal, and the oxide ion is transported to the anode, where it is converted to oxygen gas. The major advantages of the electrolytic reduction process are that it is performed in a single step in one process vessel, requires no transfer of molten salts and lithium metal between process vessels and produces a product that is more compatible with the electrorefiner technology. In this poster, we present key results from our experimental program on the development of the electrolytic reduction process.

This research is supported by the U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.

Contact Karthick Gourishankar (630-252-7294, gourishankar@cmt.anl.gov). View Poster

Development of Nonconsumable Anode for Electrolytic Reduction of Spent Oxide Fuel

Laurel Barnes, Andrew Hebden, Mark Hash, and Leonard Leibowitz

Stable oxygen-evolving anodes are being developed for use in the oxide reduction process that is part of the Advanced Fuel Cycle Initiative for the pyrochemical treatment of spent oxide fuel. This process will be used to convert the spent fuel oxides to metals, which will then be treated to separate U and transuranics (TRUs) from the cladding, noble metals, and fission products. The U/TRU product will be reused in fresh fuel while the remainder of the product stream will be disposed of as waste. The oxide reduction process comprises the direct electrolytic reduction of the metal oxides to the metals in a molten LiCl electrolyte at 650ºC. Oxide feed is reduced to metal at the cathode and oxygen is evolved at the anode. Chlorine may also be generated at the anode under some conditions. The anode environment is therefore severe and this program is devoted to developing a useful anode material. Significant success has been achieved with the development of composite ruthenium-containing anodes.

Research funded by U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.

Contact Laurel Barnes (630-252-3359, barnes@cmt.anl.gov). View Poster

Corrosion of Structural Materials in Lead and Lead-Bismuth Eutectic Coolants

Karthick Gourishankar, Laurel Barnes, and Leonard Leibowitz

The Lead-Cooled Fast Reactor (LFR) is one of the six advanced nuclear reactor systems selected by the Generation IV International Forum to meet challenging technology goals for advanced nuclear energy systems. The LFR system is a fast-spectrum reactor utilizing lead or lead/bismuth eutectic liquid metal coolant and a closed fuel cycle for efficient conversion of uranium and management of actinides. The LFR is cooled by natural convection with a reactor outlet temperature of 550^oC, which could possibly range up to 800^oC with advanced materials. Of significant concern is the compatibility of structural materials with these coolants at high temperatures. In order to evaluate candidate structural materials, a thermal-convection-based test method is being utilized to expose these materials to molten lead and lead-bismuth flowing under a temperature gradient. The temperature gradient is essential for natural circulation, which induces liquid metal flow, as well as for discerning preferential dissolution and transport of alloy components.

Research funded by U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.

Contact Len Leibowitz (630-252-4333, leibowitz@cmt.anl.gov). View Poster

Structural Materials Development for the Electrochemical Reduction of Spent Oxide Nuclear Fuel in Molten Salt Electrolyte

C. T. Snyder, L. E. Putty, J. Figueroa,.L. Leibowitz, J.E. Indacochea,^a A. Polar,a F. Rumiche,^a S. M. McDeavitt^b
University of Illinois-Chicago,^a Purdue University^b

The Chemical Engineering Division is currently collaborating with the Korea Atomic Energy Research Institute to develop advanced structural materials for use in a new technology for the treatment of spent nuclear fuel. A segment of the technology uses electrolytic reduction of spent nuclear fuel in a high-temperature molten lithium salt..This process liberates oxygen and creates a chemically aggressive environment that is too corrosive for typical structural materials. The objective of this corrosion study is to assess and select commercially available candidate materials, including superalloys, for service in the electrolyte reduction process vessel. The successful implementation of this project will provide an enabling solution for the effective management of spent fuel, and contribute to the establishment of a nuclear fuel cycle technology that is proliferation-resistant and cost-effective. Our recent corrosion testing has contributed to this effort.

This work is funded by the U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.

Contact Chris Snyder (630-252-4743, snyder@cmt.anl.gov). View Poster

Hybrid Process Development — Chlorination

Christine T. Snyder, Javier Figueroa, Leonard Leibowitz

Hybrid separations processes are being developed to address the Advanced Fuel Cycle Initiative spent nuclear fuel treatment goals and meet the separations criteria. The development of a chlorination method represents an initial step in the advancement of a chlorination process for the treatment of uranium extraction raffinate. The experiments this year mark the beginning of an evolution of chlorinating methods tha. will eventually be adapted for use in a glovebox, where actinide oxides found in spent nuclear fuel will be converted to chlorides.

This research is funded by the U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.

Contact Chris Snyder (630-252-4743, snyder@cmt.anl.gov). View Poster

Chemical Vapor Deposition of Niobium Coating on Zirconia Microspheres

C. T. Snyder, L. E. Putty, T. C. Carter,^a A. S. Hebden, B. W. Campbell,^b L. Leibowitz, and S. M. McDeavitt^c
University of Florida,^a Iowa State University,^b Purdue University^c

The Chemical Engineering Division (CMT) is supporting DOE’s Advanced Fuel Cycle Initiative program in its mission to develop and demonstrate the technologies needed to transmute the long-lived transuranic (TRU) actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. One area in which CMT is specifically involved is the development of fuels for higher actinide transmutation systems. As part of this support effort, one objective is the development of methods for coating TRU microspheres to ensure fission product containment and thermochemical stabilization in a metal matrix, and to fabricate experimental cermet fuel pins containing the coated TRU microspheres. Recent method development experiments using nonradioactive materials included laboratory coating experiments using chemical vapor deposition to deposit a niobium coating onto 100- to 300-µm zirconium oxide microspheres. The spheres were examined by scanning electron microscopy, and subsequent energy dispersive spectroscopy confirmed that the coating was niobium. The coating method will ultimately be adapted for use in a glovebox to remotely coat (Pu,Np,Am) O₂ fuel particles.

Research supported by U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.

Contact Chris Snyder (630-252-4743, snyder@cmt.anl.gov). View Poster