Analysis of turbulence intensity and coolant droplet behavior around spacers in a BWR fuel assembly
- Hitachi Ltd., Ibaraki-ken (Japan); and others
A subchannel analysis code has been developed to survey the critical power of a wide variety of boiling water reactor (BWR) fuel bundle designs. The code is based on a film flow model, which calculates the depletion of the liquid film flow along the fuel rod surface. Fuel spacers are supposed to influence bundle critical power by enhancing the coolant droplet deposition onto the liquid film. In the code, the spacer influence is expressed by experimentally defined coefficients. Hence, a mechanistic model of the spacer effects is desired to extend the applicability of the code. In a previous study, dispersed flow around a spacer flow tab was analyzed. The coolant droplets deposited on fuel rod surfaces due to flow deflection by the spacer flow tab, but the turbulence influence was not taken into consideration. In this study, the turbulence intensity and the coolant droplet behavior downstream from the spacers were evaluated by using the turbulent flow analysis code.
- OSTI ID:
- 186720
- Report Number(s):
- CONF-950601--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 72; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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