skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory

Abstract

The Idaho National Laboratory (INL) is actively engaged in the development of electrochemical processing technology for the treatment of fast reactor fuels using irradiated fuel from the Experimental Breeder Reactor-II (EBR-II) as the primary test material. The research and development (R&D) activities generate a low enriched uranium (LEU) metal product from the electrorefining of the EBR-II fuel and the subsequent consolidation and removal of chloride salts by the cathode processor. The LEU metal ingots from past R&D activities are currently stored at INL awaiting disposition. One potential disposition pathway is the shipment of the ingots to the Savannah River Site (SRS) for dissolution in H-Canyon. Carbon steel cans containing the LEU metal would be loaded into reusable charging bundles in the H-Canyon Crane Maintenance Area and charged to the 6.4D or 6.1D dissolver. The LEU dissolution would be accomplished as the final charge in a dissolver batch (following the dissolution of multiple charges of spent nuclear fuel (SNF)). The solution would then be purified and the 235U enrichment downblended to allow use of the U in commercial reactor fuel. To support this potential disposition path, the Savannah River National Laboratory (SRNL) developed a dissolution flowsheet for the LEU using samplesmore » of the material received from INL.« less

Authors:
 [1];  [1];  [1];  [1]
  1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Publication Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1373546
Report Number(s):
SRNL-STI-2017-00263
TRN: US1800535
DOE Contract Number:  
AC09-08SR22470
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ENRICHED URANIUM; EBR-2 REACTOR; SPENT FUELS; ELECTROREFINING; INL; EBR-II; LEU; fuel dissolution; H-canyon

Citation Formats

Daniel, G., Rudisill, T., Almond, P., and O'Rourke, P. DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory. United States: N. p., 2017. Web. doi:10.2172/1373546.
Daniel, G., Rudisill, T., Almond, P., & O'Rourke, P. DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory. United States. doi:10.2172/1373546.
Daniel, G., Rudisill, T., Almond, P., and O'Rourke, P. Wed . "DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory". United States. doi:10.2172/1373546. https://www.osti.gov/servlets/purl/1373546.
@article{osti_1373546,
title = {DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory},
author = {Daniel, G. and Rudisill, T. and Almond, P. and O'Rourke, P.},
abstractNote = {The Idaho National Laboratory (INL) is actively engaged in the development of electrochemical processing technology for the treatment of fast reactor fuels using irradiated fuel from the Experimental Breeder Reactor-II (EBR-II) as the primary test material. The research and development (R&D) activities generate a low enriched uranium (LEU) metal product from the electrorefining of the EBR-II fuel and the subsequent consolidation and removal of chloride salts by the cathode processor. The LEU metal ingots from past R&D activities are currently stored at INL awaiting disposition. One potential disposition pathway is the shipment of the ingots to the Savannah River Site (SRS) for dissolution in H-Canyon. Carbon steel cans containing the LEU metal would be loaded into reusable charging bundles in the H-Canyon Crane Maintenance Area and charged to the 6.4D or 6.1D dissolver. The LEU dissolution would be accomplished as the final charge in a dissolver batch (following the dissolution of multiple charges of spent nuclear fuel (SNF)). The solution would then be purified and the 235U enrichment downblended to allow use of the U in commercial reactor fuel. To support this potential disposition path, the Savannah River National Laboratory (SRNL) developed a dissolution flowsheet for the LEU using samples of the material received from INL.},
doi = {10.2172/1373546},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jun 28 00:00:00 EDT 2017},
month = {Wed Jun 28 00:00:00 EDT 2017}
}

Technical Report:

Save / Share: