By Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment, National Research Council
Ultimate record evaluates the technical viability of electrometallurgial expertise as a style for treating U.S. division of strength (DOE) spent nuclear gasoline (SNF). Softcover.
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Additional info for Electrometallurgical Techniques for DOE Spent Fuel Treatment Final Report
The salt and zeolite are combined and processed in a V-mixer where they are heated to 500 °C for approximately 15 h. In this operation the salt is occluded into the zeolite structure. Twenty-two V-mixer experiments were performed by ANL with nonradioactive materials. The V-mixer is also used to mix 25 wt % glass with the saltloaded zeolite. The nominal batch size is 50 kg, but an 80-kg batch was also successfully tested by ANL. The glass/salt-loaded zeolite mixture is loaded into stainless-steel cans for processing through the HIP.
12. , 1996, p. 5. Copyright © 2003 National Academy of Sciences. All rights reserved. edu) for research purposes are copyrighted by the National Academy of Sciences. Distribution, posting, or copying is strictly prohibited without written permission of the NAP. 1 Overview block diagram of ANL’s electrometallurgical process for DOE spent nuclear fuel. This is the process as originally proposed by ANL for the treatment of spent nuclear fuel. , 1995, p. 9. Data supplied by James Laidler, Argonne National Laboratory, January 1995.
Distribution, posting, or copying is strictly prohibited without written permission of the NAP. 12 Ceramic waste process flow sheet. SOURCE: Argonne National Laboratory. solidified. The salt released easily from the tray. It was transferred by cask from the FCF to HFEF. 2 wt % fission product chlorides. Four kilograms of salt were processed into a 50-kg batch of glass and salt-loaded zeolite. From this material, 10 HIP cans were processed through the HIP. 5 in. 13). For inventory operations, the can diameter will be approximately 20 in.
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