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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
Joel L. McDuffee, Arthur E. Ruggles
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 232-242
Technical Paper | doi.org/10.13182/NSE97-A24270
Articles are hosted by Taylor and Francis Online.
A model is presented for predicting the pressure gradient in partially developed subcooled boiling of water for velocities from 15 to 30 m/s and inlet peaked, nonuniform axial flux profiles with channel average flux values of 6 MW/m2. The partially and fully developed boiling regions are considered separately, however; the same general modeling technique is used for both. Several correlations for the void fraction at onset of significant void are considered, and their effect on the channel pressure drop is evaluated. The effect of nonuniform axial heat flux on the channel pressure drop is also evaluated. The model is compared with pressure drop data from the thermal-hydraulic test loop at Oak Ridge National Laboratory and is found to agree with the data within 24%.