Abstract
In a boiling water nuclear reactor (BWR), liquid film dryout may occur on a fuel rod surface when the fuel assembly power exceeds the critical power. The spacers supporting fuel rods affect the thermal hydraulic performance of the fuel assembly. The spacer is designed to enhance the critical power significantly. If spacer effects for two-phase flow could be estimated analytically, the cost and time required for the development of the BWR fuel would be decreased. The final goal of this study is to be able to analytically predict the critical power of a new BWR fuel assembly without any tests. Initially, we focused on estimating the spacer effect on the droplet deposition because the spacer effect on the droplet deposition was larger than on the droplet entrainment. Therefore, the finite element method code with large eddy simulation model was developed to calculate the droplet behavior. Moreover, the estimation of droplet deposition around the two types of spacer was performed. The estimation results showed the tendency of deposited droplet volume to be in agreement with the tendency of the critical power.
| Original language | English |
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| Title of host publication | American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED |
| Editors | Anon |
| Place of Publication | New York, NY, United States |
| Publisher | ASME |
| Volume | 16 |
| Publication status | Published - 1997 |
| Externally published | Yes |
| Event | Proceedings of the 1997 ASME Fluids Engineering Division Summer Meeting, FEDSM'97. Part 16 (of 24) - Vancouver, Can Duration: 1997 Jun 22 → 1997 Jun 26 |
Other
| Other | Proceedings of the 1997 ASME Fluids Engineering Division Summer Meeting, FEDSM'97. Part 16 (of 24) |
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| City | Vancouver, Can |
| Period | 97/6/22 → 97/6/26 |
ASJC Scopus subject areas
- Engineering(all)