| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1565292 | Journal of Nuclear Materials | 2013 | 6 Pages |
Abstract
A small lead–bismuth eutectic-cooled reactor concept (referred to as the Hyperion reactor concept) is being studied at Los Alamos National Laboratory and Hyperion Power Generation. In this report, a critical assessment of the lead–bismuth eutectic technology for Hyperion reactor is presented based on currently available knowledge. Included are: material compatibility, oxygen control, thermal hydraulics, polonium control. The key advances in the technology and their applications to Hyperion reactor design are analyzed. Also, the near future studies in main areas of the technology are recommended for meeting the design requirements.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
J. Zhang, R.J. Kapernick, P.R. McClure, T.J. Trapp,