4.5 Article

Analysis of high burnup spent nuclear fuel by ICP-MS

Journal

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
Volume 263, Issue 3, Pages 581-586

Publisher

SPRINGER
DOI: 10.1007/s10967-005-0627-7

Keywords

-

Ask authors/readers for more resources

We have used inductively coupled plasma mass spectrometry (ICP-MS) as the primary tool for determining concentrations of a suite of nuclides in samples excised from high-burnup spent nuclear fuel rods taken from light water nuclear reactors. The complete analysis included the determination of Mo-95, Tc-99, Ru-101, Rh-103, Ag-109, Cs-137, Nd-143, Nd-145, Nd-148, Sm-147, Sm-149, Sm-150, Sm-151, Sm-152, Eu-151, Eu-153, Eu-155, Gd-155, Np-237, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242m, and Am-243. The isotopic composition of fissiogenic lanthanide elements was determined using high-performance liquid chromatography (HPLC) with ICP-MS detection. These analytical results allow the determination of fuel burn-up based on Nd-148, Pu, and U content, as well as provide input for storage and disposal criticality calculations. Results show that ICP-MS along with HPLC-ICP-MS are suitable of performing routine determinations of most of these nuclides, with an uncertainty of +/- 10% at the 95% confidence level.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.5
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

No Data Available
No Data Available