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New X-ray imaging for ITER-supporting tokamaks
As researchers continue to seek ways to better understand the plasma inside fusion machines to fully harness fusion energy, Princeton Plasma Physics Laboratory is leading a project to provide new X-ray imaging systems to two international tokamak projects: WEST, in southern France, and JT-60SA, in Japan—both of which are designed to support the development of ITER.
Yassin A. Hassan, Omar Rais
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 77-86
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34569
Articles are hosted by Taylor and Francis Online.
The current version of the RELAP5/MOD2 computer code underpredicts the degree of superheat in the secondary side of the steam generator bundles. Many studies have concluded that this is due to overprediction of the interphase drag force. New interphase drag correlations have been developed for the bubbly and slug regimes. These correlations were implemented in the current version of the RELAP5/MOD2 computer code. Steady-state conditions for 65, 75, and 100% power loads of 30-tube once-through steam generator tests are simulated. The calculated primary- and secondary-side temperature profiles show that the new interphase drag correlations achieve closer agreement with experimental data than the temperature profiles of the original code.