TECHNOLOGY FOR THE REPROCESSING OF NONPRODUCTION REACTOR FUELS, BUDGET ACTIVITY 2790. Quarterly Report

Technical Report · Mon Mar 17 04:00:00 EST 1958

OSTI ID:4225301

Cooper, V R

This is the first in a series of quarterly reports on the research and development work carried out for activity 2790 ---Separations Development for Non- Production Reactors. By January, 1962, Hansford its to be prepared to process the fuels from the power reactors which employ depleted or slightly enriched uranaium fuels. At the present time, Hanford is plannlng to process the fuel from the following reactors: Yankee, Dresden, CPPD, Piqua, Chugach, PRDC, and Northern States. Batch studies were made to determine the requirements for removing chloride from aqua regia dissolver solution by solvent extraction. Preliminary dissolution and corrosion rates are given for stainless steel jackets in HNO/sub 3/--NF systems. The solubility of UF/sub 4/ in boiling Zirflex solutions (NH/sub 4/HF) containing dissolved Zr is given Zirflex pilot plant studies were initiated on the dissolution or Zircaloy metal with aqueous NH/sub 4/ HF solution. A welded Haynes-25 coupon showed no visible preferential attack after exposure to 5M HNO/sub 3/--2M HCl for 200 hours. The corrosion rate of 304- L stainless steel exposed for 312 hours to 6M under heat transfer conditions was 1.6 mfl-s/ month. (W.L.H.)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: W-31-109-ENG-52
• NSA Number: NSA-13-019033
• OSTI ID: 4225301
• Report Number(s): HW-55419
• Country of Publication: United States
• Language: English

Related Subjects

AMMONIUM COMPOUNDS
CHEMISTRY
CHLORIDES
CORROSION
ENRICHMENT
FUELS
HYDROCHLORIC ACID
HYDROFLUORIC ACID
NITRIC ACID
POWER PLANTS
REACTORS
REPORT
REPROCESSING
SEPARATION PROCESSES
SOLUBILITY
SOLUTIONS
SOLVENT EXTRACTION
STAINLESS STEELS
URANIUM
URANIUM TETRAFLUORIDE
WATER
ZIRCONIUM COMPOUNDS