Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Feasibility of processing the experimental breeder reactor-II driver fuel from the Idaho National Laboratory through Savannah River Site's H-Canyon facility

Technical Report ·
DOI:https://doi.org/10.2172/1374364· OSTI ID:1374364
 [1]
  1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

Savannah River National Laboratory (SRNL) was requested to evaluate the potential to receive and process the Idaho National Laboratory (INL) uranium (U) recovered from the Experimental Breeder Reactor II (EBR-II) driver fuel through the Savannah River Site’s (SRS) H-Canyon as a way to disposition the material. INL recovers the uranium from the sodium bonded metallic fuel irradiated in the EBR-II reactor using an electrorefining process. There were two compositions of EBR-II driver fuel. The early generation fuel was U-5Fs, which consisted of 95% U metal alloyed with 5% noble metal elements “fissium” (2.5% molybdenum, 2.0% ruthenium, 0.3% rhodium, 0.1% palladium, and 0.1% zirconium), while the later generation was U-10Zr which was 90% U metal alloyed with 10% zirconium. A potential concern during the H-Canyon nitric acid dissolution process of the U metal containing zirconium (Zr) is the explosive behavior that has been reported for alloys of these materials. For this reason, this evaluation was focused on the ability to process the lower Zr content materials, the U-5Fs material.

Research Organization:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC09-08SR22470
OSTI ID:
1374364
Report Number(s):
SRNL-STI--2017-00420
Country of Publication:
United States
Language:
English

Similar Records

DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory
Technical Report · Wed Jun 28 00:00:00 EDT 2017 · OSTI ID:1373546

Electrorefining Experience For Pyrochemical Reprocessing of Spent EBR-II Driver Fuel
Conference · Sat Oct 01 00:00:00 EDT 2005 · OSTI ID:911150

Selected uranium product characteristics for the EBR-II spent-fuel treatment program
Journal Article · Sun Nov 30 23:00:00 EST 1997 · Transactions of the American Nuclear Society · OSTI ID:552372