| タイトル | UF6 breeder reactor power plants for electric power generation |
| 著者（英） | Rust, J. H.; Hohl, F.; Clement, J. D. |
| 著者所属（英） | NASA Langley Research Center |
| 発行日 | 1976-09-01 |
| 言語 | eng |
| 内容記述 | The reactor concept analyzed is a U-233F6 core surrounded by a molten salt (Li(7)F, BeF2, ThF4) blanket. Nuclear survey calculations were carried out for both spherical and cylindrical geometries. Thermodynamic cycle calculations were performed for a variety of Rankine cycles. A conceptual design is presented along with a system layout for a 1000 MW stationary power plant. Advantages of the gas core breeder reactor (GCBR) are as follows: (1) high efficiency; (2) simplified on-line reprocessing; (3) inherent safety considerations; (4) high breeding ratio; (5) possibility of burning all or most of the long-lived nuclear waste actinides; and (6) possibility of extrapolating the technology to higher temperatures and MHD direct conversion. |
| NASA分類 | NUCLEAR AND HIGH-ENERGY PHYSICS |
| レポートNO | 78N26866 |
| 権利 | No Copyright |
| URI | https://repository.exst.jaxa.jp/dspace/handle/a-is/435237 |
