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Evaluation of high resolution X-ray monochromatic wavelength dispersive X-ray fluorescence instrument for determining Pu and U in nuclear reprocessing streams

Journal Article · · Spectrochimica Acta. Part B, Atomic Spectroscopy
 [1];  [1];  [2];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
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In this study, an alpha-prototype benchtop instrument was developed and tested for measuring Pu and U in spent fuel dissolver tanks in a nuclear fuel reprocessing plant. The high resolution X-ray (hiRX) instrument was designed with the aim of providing a new capability to measure samples with high radiation background with selectivity, accuracy, and precision using ultra-low volumes (7 μL) of liquid. The instrument was tested with specimens from the operational reprocessing facility at Savannah River National Laboratory. The results showed that bias was <6% for Pu nitrate process solution and < 18% for Pu in U/HNO3 matrix. Instrumental precision was <1% RSD while between microcell repeatability was <6% RSD. The limit of detection for Pu in HNO3 matrix was 3 × 10-5 g/L (100 s, 35 W). Finally, this study demonstrates that hiRX technology has the potential to provide rapid and simultaneous quantification of Pu and U without sample preparation, making it suitable for process monitoring and materials control and accountability applications.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC52-06NA25396
OSTI ID:
1479934
Alternate ID(s):
OSTI ID: 1564294
OSTI ID: 23106315
Report Number(s):
LA-UR--17-29121
Journal Information:
Spectrochimica Acta. Part B, Atomic Spectroscopy, Journal Name: Spectrochimica Acta. Part B, Atomic Spectroscopy Journal Issue: C Vol. 148; ISSN 0584-8547
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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journal April 2015
Determination of plutonium in spent nuclear fuel using high resolution X-ray journal August 2015
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Low-Level Sulfur in Fuel Determination Using Monochromatic WD XRF—ASTM D 7039-04 journal January 2005

Cited By (1)

A direct and safe method for plutonium determination using total reflection X-ray fluorescence spectrometry journal January 2019

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Accountancy
Elemental analysis
MWDXRF
Reprocessing
hiRX