DOE RESL: CHEM-TP-SR.06:  Sr-89 and Sr-90 in Liquid Radioactive Wastes or Waters by Beta Counting

  • Summary
  • Analytes
  • Revision
  • Data and Sites
Official Method Name
Sulfate Method for Sr-89 and Sr-90 in Liquid Radioactive Wastes or Waters
Current Revision
June 1999
Media
OTHER
Instrumentation
Beta Counter
Method Subcategory
Radiochemical
Method Source
  DOE RESL
Citation
  Dept. of Energy RESL Technical Procedure
Brief Method Summary
Strontium sulfate (SrSO4) is precipitated and then dissolved in a EDTA solution. SrSO4 is preferentially precipitated from EDTA and a lower pH. The sulfate precipitate is metathesized to a carbonate. After barium is separated as a chromate, the Sr is reprecipitated as a sulfate. Total radioactive Sr is determined by beta counting the SrSO4. The strontium sample is then dissolved in EDTA and set aside for Y-90 ingrowth. After a suitable ingrowth period, Y-90 is separated and counted on Y2(C2O4)3 - 9H2O. The Sr-90 is determined by beta counting its Y-90 daughter. Sr-89 is determined as the difference between total radioactive Sr and Sr-90.
Scope and Application
This procedure is applicable to samples that must be analyzed for Sr-89, 90 in liquid radioactive wastes or waters and for samples that must be decontaminated from Ba-140.
Applicable Concentration Range
None given.
Interferences
None given.
Quality Control Requirements
QC procedures based on internal laboratory requirements for radiochemical analysis.
Sample Handling
Procedure calls for the use of 10 M NaOH, Glacial acetic acid, 15 M NH4OH, and 1.5 M Na2CrO4. Take proper precautionary measures. Use a fume hood, Wear gloves, safety glasses/face shield, and protective clothing.
Maximum Holding Time
None given.
Relative Cost
$51 to $200
Sample Preparation Methods