Assay of zirconium and americium in the irradiated U-Zr metal alloy fuel slug
Source abstract
Abstract
An alloy-based fuel comprised of U-Pu-Zr is under development for the futuristic fast reactors to improve fissile atom utilization. As the technical data available with the metal fuel reactors is limited, it is imperative to have an exhaustive comprehension of behavior of fission and activation products before deploying the U-Pu-Zr metal fuel for commercial applications. Towards meeting this objective, the present paper highlights the analytical estimation of Zr and Am in the irradiated U-Zr metal that has experienced a low burn-up. The estimation of Zr was carried out by a modified spectrophotometric method developed in our laboratory. The estimation of Am was accomplished through initial liquid-liquid extraction-based removal of U and Pu by tri- n ‑butyl phosphate followed by the separation of Am by TODGA from the raffinate. Am was estimated with the help of alpha spectrometry of the Am-separated TODGA phase, and the same has been substantiated by comparing it with the results of gamma spectrometry.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (30)
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