Publications
Showing 71 results for Author: Shalina C. Metzger
Nov, 2023
Journal
Direct isotopic analysis of solid uranium particulates on cotton swipes by microextraction-ICP-MS
Direct isotope ratio analysis of solid uranium particulates on cotton swipes was achieved using a solution-based microextraction technique, coupled to a quadrupole inductively coupled plasma - mass spectrometer (ICP-MS). This microextraction-ICP-MS methodology provides rapid isotopic analysis which could be applicable to nuclear safeguards measurements. Particulates of ura…
Nov, 2023
Journal
The need for speed – Burnup determination of spent nuclear fuel
Here we present the application of a novel analytical approach for high-speed evaluation of burn-up in spent nuclear fuel. This automated online separation–direct analysis method, which simultaneously measures the isotopic compositions and concentrations of Nd, Pu, and U using isotope dilution-inductively coupled plasma mass spectrometry, enables the determination of burnu…
Nov, 2023
ORNL Report
Analytical Report for Nuclear Regulatory Commission High Burnup Fuel Specimens
Nov, 2023
Journal
Analysis of solid uranium particulates on cotton swipes with an automated microextraction-ICP-MS system
An automated microextraction method coupled to an inductively coupled plasma – mass spectrometer (ICP-MS) was developed for the direct analysis of solid uranium particulates on the surface of cotton swipes. The microextraction probe extracts particulates from the sample surface, in a flowing solvent, and directs the removed analyte to an ICP-MS for isotopic determination.…
Nov, 2023
Journal
Faraday detector uranium isotope ratio measurement: Insights from solution- and laser ablation-based sampling methodologies on the Neoma MC-ICP-MS
In this study we utilize an all-faraday cup detector configuration on the Neoma MC-ICP-MS to perform uranium isotope ratio determinations from certified reference materials and a nuclear fuel precursor material via solution and laser ablation based sampling methodologies. The goal in performing these measurements is primarily to demonstrate that the all-faraday cup method…
Nov, 2023
ORNL Report
Mid-Year Report for: 24.1.3.4 – Quantification of Analytical Background from GSR Tabs during Microbeam Uranium Isotope Analysis
This document constitutes the mid-year report for an FY23 project sponsored by the Office of International Nuclear Safeguards- Safeguards Technology Development Program (SG-Tech). The report is supported by existing project work plan (PWP) having the same title as this report as well as a field test plan (FTP), both of which are available upon request. This report provides…