Abstract
The current BWR fuel assembly has seven spacers for maintaining a constant gap between fuel rods. Spacer design has a significant effect on the thermal hydraulic performance of a BWR fuel assembly. The purpose of this study is to develop an accurate method for predicting the effect of spacer shape on critical power. The critical power prediction method combining the CFD code of droplet deposition rate and the conventional subchannel code was verified by the critical power data of 4×4 rod bundle with various spacer shapes. From the verification, this method was found to be effective for predicting the critical power change with the change of the spacer shape.
| Original language | English |
|---|---|
| Pages (from-to) | 573-579 |
| Number of pages | 7 |
| Journal | Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B |
| Volume | 67 |
| Issue number | 654 |
| Publication status | Published - 2001 Feb |
| Externally published | Yes |
Keywords
- Critical heat flux
- Critical Power
- Nuclear reactor
- Spacer
- Subchannel analysis
ASJC Scopus subject areas
- Mechanical Engineering
- Condensed Matter Physics