Abstract
Characterization of nuclear materials in solid particles or particles in liquid slurry, particularly in high level waste, can establish the elemental, organic, and isotopic compositions that effect the properties of the materials during nuclear fuel cycle activities and processes. Techniques to evaluate such detailed information, even at small concentrations, can support nuclear materials and science programs by increasing our ability to manage and control nuclear materials. However, radioactive materials analysis in liquids and slurries can be challenging using bulk approaches. We have developed a vacuum compatible microfluidic interface, system for analysis at the liquid vacuum interface (SALVI), to enable surface analysis of liquids and liquid-solid interactions using scanning electron microscopy (SEM) and time-of-flight secondary ion mass spectrometry (ToF-SIMS). In this work, we illustrate the initial results from the analysis of liquid samples of importance in the geologic disposal of uranium dioxide (UO2) spent nuclear fuel in a repository environment using in situ liquid SEM and SIMS. Our results demonstrate that multimodal analysis of UO2 materials is possible using SALVI and in situ chemical imaging. Both in situ liquid SEM and SIMS can be used as new approaches to analyze radioactive materials in liquid and slurry forms of high level nuclear wastes.
| Original language | English |
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| Pages | 311-315 |
| Number of pages | 5 |
| State | Published - 2019 |
| Externally published | Yes |
| Event | 17th International High-Level Radioactive Waste Management Conference, IHLRWM 2019 - Knoxville, United States Duration: Apr 14 2019 → Apr 18 2019 |
Conference
| Conference | 17th International High-Level Radioactive Waste Management Conference, IHLRWM 2019 |
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| Country/Territory | United States |
| City | Knoxville |
| Period | 04/14/19 → 04/18/19 |
Funding
XYY, JY and ZZ thank the support of the Pacific Northwest National Laboratory TOP program for the support to obtain the initial in situ liquid SIMS results of uranium samples. The programmatic support of this work is from the DOE Nuclear Energy Spent Fuel Waste Science Technology (SFWST) program. Pacific Northwest National Laboratory is operated by Battelle under the contract DE-AC05-76RL01830.