Subchannel analysis applied to neutron noise investigation in a boiling water reactor

Thesis/Dissertation · Wed Jan 01 04:00:00 EST 1986

OSTI ID:6683484

Khan, H J

Drift flux parameters were developed for subchannel configuration of BWR rod bundle geometry in order to calculate the void fraction and void propagation velocities inside the individual subchannels. Void fraction calculations were performed using subchannel drift flux code CANAL. Using void and flow distributions, values of the distribution parameters were estimated for bundle averaged void fraction calculation. The simple geometries taken into consideration are circular tubes, rectangular channels, and parallel plates. A C/sub 0/ model was also developed for parallel subchannel configuration. Successful prediction of average void fraction is observed for the annular rod bundle geometry of the FRIGG experiment. A C/sub 0/ model developed for one-dimensional subchannel geometry was applied to annular subchannels using Zuber-Findlay's void quality model. This is the first time subchannel void fraction is predicted by subchannel drift flux parameters. It appears that the magnitude of C/sub 0/ varies between subchannels but remains almost constant within each subchannel. A two-dimensional derivation of C/sub 0/ for the three types of subchannel (corner, side, and center) of BWR rod-bundle geometry was developed.

• Research Organization: Washington Univ., Seattle (USA)
• OSTI ID: 6683484
• Country of Publication: United States
• Language: English

Related Subjects

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220100 -- Nuclear Reactor Technology-- Theory & Calculation
BWR TYPE REACTORS
CALCULATION METHODS
GEOMETRY
MATHEMATICS
NEUTRON FLUX
RADIATION FLUX
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR NOISE
REACTORS
ROD BUNDLES
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS