| Original language | English |
|---|---|
| Pages (from-to) | 59-62 |
| Number of pages | 4 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 116 |
| State | Published - 2017 |
| Event | 2017 Transactions of the American Nuclear Society, ANS 2017 - San Francisco, United States Duration: Jun 11 2017 → Jun 15 2017 |
Funding
For the chlorination/sublimation recovery/ purification process that is being developed, previous studies1-3 include (1) lab-scale experimental tests using nonradioactive scrap cladding tubes, (2) two feasibility tests using small pieces (~15 g) of actual UNF cladding, and (3) one feasibility test on a piece of fuel rod with intact cladding and fuel, all using laboratory glassware equipment. The developmental work at ORNL has received technical support from industry representatives with cladding manufacturing expertise, through a DOE Office of Nuclear Energy (DOE-NE) industrial assistance program, and is now receiving technical support for secondary purification of the chlorination product salt, ZrCl4, from university teams through the DOE-NE Nuclear Energy University Projects (NEUP) program.