Critical heat flux & two phase hydraulic investigation of a 16-rod simulation of a BWR fuel assembly
- Battelle-Northwest, Richland, WA (United States)
- Jersey Nuclear Co., Bellevue, WA (United States)
The combined effects of local power distribution and grid spacers on CHF were experimentally evaluated using an electrically heated 16 rod bundle simulation of a typical BWR fuel assembly. The single and two-phase hydraulic behavior of the test assembly was also evaluated. Data were obtained over a range of pressures (1000-1500 psia), mass velocities (0.5 x 10{sup 6} - 2.0 x 10{sup 6} lb/hr ft{sup 2}), and bundle-average exit qualities (0 - .40). CHF consistently occurred upstream of the last grid spacer indicating that the grid spacer improved coolant mixing downstream of it. CHF results compared well with other rod bundle CHF data available in the literature. Rod bundle two-phase pressure losses were accurately predicted via the COBRA code using the Homogeneous two-phase model in conjunction with empirically established single-phase hydraulic correlations for the bundle components.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10120339
- Report Number(s):
- BNWL-SA--3724; ON: DE95006510
- Country of Publication:
- United States
- Language:
- English
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