|Series||Report of investigations (United States. Bureau of Mines) -- 5758|
|Contributions||Baker, D., Nettle, J., Knudsen, H.|
A pyrochemical electrorefining process for the recovery of actinides from metallic nuclear fuel based on actinide-zirconium alloys (An–Zr) in a molten salt is being investigated. In this process actinides are group-selectively recovered on solid aluminium cathodes as An–Al alloys using a LiCl–KCl eutectic melt at a temperature of ° by: 4. Structure of zirconium and zirconium as shown by the reactions ⁹²Zr(d,p)⁹³Zr and ⁹²Zr(d,t)⁹¹Zr / (Washington, D.C.: National Aeronautics and Space Administration ; [Springfield, Va. This paper describes the metallurgical characterization of deposits produced in molten salt electrorefining of uranium and uranium - % zirconium alloy. The techniques of characterization are described with emphasis on considerations given to the radioactive and pyrophoric nature of the samples. The morphologies observed and their implications for deposit performance are also presented Author: T.C. Totemeier. The present electrochemical study on zirconium in the molten fluoride system will be a theoretical reference for future zirconium electrorefining from Zr alloy or scraps. View Show abstract.
A pyrochemical electrorefining process for the recovery of actinides from metallic nuclear fuel based on actinide-zirconium alloys (An-Zr) in a molten salt is being investigated. A pyrochemical electrorefining process for the recovery of actinides from metallic nuclear fuel based on actinide-zirconium alloys (An-Zr) in a molten salt is being investigated. In this process actinides are group-selectively recovered on solid aluminium cathodes as AnAl alloys using a LiCl-KCl eutectic melt at a temperature of ° by: 4. Environmental analysis of zirconium alloy production Mikael Lundberg The generation of electricity in light water nuclear power plants uses zirconium alloys as the primary containment and cladding of the nuclear fuel. The environmental impacts of the production of zirconium alloys . Since the committee's previous site visit on October , , ANL-W has continued its efforts toward characterizing and optimizing the operating conditions for the Mark-IV ER. 1 These efforts to date have been conducted while meeting their scheduled throughput for processing two irradiated EBR-II driver assemblies, 2 on average, per month. Process characterization has included studies of.
The integral fast reactor (IFR, originally advanced liquid-metal reactor) is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor).IFR would breed more fuel and is distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.. IFR development began in and the U.S. Department of Energy built a prototype, the. electrorefining process should be developed by both experiments and modeling to separate niobium from zirconium. Decontamination Factor Needs for LLW To decontaminate Zircaloys, radioactivity of pressure tube has to be confirmed. ORIGEN-2 code is used to . facilitate subsequent electrorefining. – However, degraded UZr would introduce significant quantities of partially to fully oxidized zirconium into a LiCl-Li2O electrolytic reduction system at °C, in which the behavior of zirconium oxide and zirconium metal is not well defined. 2 Degraded EBR-II fuel element. The metallurgy of zirconium. David Leslie Douglass. International Atomic Energy Agency, - Science - pages. 0 Reviews. From inside the book. What people are saying - Write a review. We haven't found any reviews in the usual places. Contents. INTRODUCTION i. 1: DEFORMATION AND TEXTURES.