Abstract
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.
| Original language | English |
|---|---|
| Pages (from-to) | 344-350 |
| Number of pages | 7 |
| Journal | JSME International Journal, Series B: Fluids and Thermal Engineering |
| Volume | 47 |
| Issue number | 2 |
| DOIs | |
| Publication status | Published - 2004 May |
| Externally published | Yes |
Keywords
- Advanced recycle system
- Boiling
- BWR
- Critical power
- Heat transfer
- Multi-phase flow
- Nuclear reactor
- Power plant
- Tight lattice
ASJC Scopus subject areas
- Mechanical Engineering
- Physical and Theoretical Chemistry
- Fluid Flow and Transfer Processes