抄録
An innovative fuel cycle system concept named BARS (BWR with an Advanced Recycle System) has been proposed as a future fuel cycle option aiming at enhanced utilization of uranium resources and reduction of radioactive wastes. In BARS, the spent fuel from conventional light water reactors (LWRs) is recycled as a mixed oxide (MOX) fuel for a BWR core with the fast neutron spectrum by means of oxide dry-processing and vibro-packing fuel fabrication. The fast neutron spectrum is obtained by means of triangular tight fuel lattice. Further study on BARS, especially on tight lattice MOX fuel, has been initiated as a joint study by Toshiba and Gifu University. The objective of this paper is to show the latest progress of the study on BARS, especially concerning the thermal-hydraulics measurements for tight lattice bundle.
| 本文言語 | English |
|---|---|
| ページ（範囲） | 344-350 |
| ページ数 | 7 |
| ジャーナル | JSME International Journal, Series B: Fluids and Thermal Engineering |
| 巻 | 47 |
| 号 | 2 |
| DOI | |
| 出版ステータス | Published - 2004 5月 |
| 外部発表 | はい |
ASJC Scopus subject areas
- 機械工学
- 物理化学および理論化学
- 流体および伝熱