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T. Ginsberg, O. C. Jones, Jr., J. C. Chen
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 391-398
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32344
Articles are hosted by Taylor and Francis Online.
Observations of two-phase flow fields in single-component volume-heated boiling pools were made. Photographic observations, together with pool-average void fraction measurements, indicate that the churn-turbulent flow regime is stable for superficial vapor velocities up to nearly five times the Kutateladze dispersal limit. Within this range of conditions, a churn-turbulent drift flux model provides a reasonable prediction of the pool-average void fraction data. An extrapolation of the data to transition phase accident conditions suggests that intense boilup could occur where the pool-average void fraction would be >0.6 for steel vaporization rates equivalent to power levels >1% of nominal liquid-metal fast breeder reactor power density. The extended stability of bubbly flow to unusually large vapor fluxes and void fractions, observed in some experiments, is a major unresolved issue at this time.