Open Access. Powered by Scholars. Published by Universities.®
- Keyword
-
- Accelerator (1)
- Electrons (1)
- Graphite (1)
- Isotopes (1)
- Linear accelerators (1)
-
- Neptunium – Isotopes – Absorption and adsorption (1)
- Nuclear medicine (1)
- RTGs (1)
- Radioactive tracers (1)
- Radioactive wastes – Storage (1)
- Radioisotopes (1)
- Radiopharmeceuticals (1)
- Repository (1)
- Rhodium compounds (1)
- Sorption (1)
- TRISO (1)
- Technetium (1)
- Uranium – Isotopes – Absorption and adsorption (1)
Articles 1 - 2 of 2
Full-Text Articles in Physics
Novel Production Techniques Of Radioisotopes Using Electron Accelerators, Daniel Robert Lowe
Novel Production Techniques Of Radioisotopes Using Electron Accelerators, Daniel Robert Lowe
UNLV Theses, Dissertations, Professional Papers, and Capstones
Non-traditional radioisotope production techniques using a compact, high power linear electron accelerator have been demonstrated and characterized for the production of 18F, 47Sc, 147Pm, and 99mTc from a variety of target candidates. These isotopes are used extensively in the medical field as diagnostic and therapy radioisotopes, as well as the space industry as RTG's. Primary focus was placed on 99mTc as it constitutes approximately 80% of all diagnostic procedures in the medical community that use radioactive tracers. It was also the prime focus due to recent events at the Chalk River nuclear reactor, which caused global shortages of this isotope …
Evaluating Actinide Sorption To Graphite With Regards To Triso Repository Performance, Corey Christopher Keith
Evaluating Actinide Sorption To Graphite With Regards To Triso Repository Performance, Corey Christopher Keith
UNLV Theses, Dissertations, Professional Papers, and Capstones
Graphite has the potential for inclusion in nuclear waste for disposal in waste repository settings. Implementation of High Temperature Gas-cooled Reactors contributes to this potential through use of TRISO fuel, if direct disposal of the graphite matrix surrounding the fuel is employed. The inclusion of the large mass and volume in the TRISO fuel waste form differs significantly from used light water reactor fuel waste forms, requiring new performance models to describe the behavior in a repository setting. The purpose of this study is to evaluate the potential for the graphite to improve actinide, specifically uranium and neptunium, retardation from …