Comparison of Lehigh 3 x 3 rod bundle post-CHF data with the predictions of RELAP5/MOD2
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7124392
To date, there are only very limited data for nonequilibrium convective film boiling in rod bundle geometries. A recent nine (3 x 3)-rod bundle post-critical heat flux (CHF) from the Lehigh University test facility was simulated using RELAP5/MOD2 cycle 36.02, to assess its capabilities in predicting the overall convective mechanisms in post-CHF heat transfer in rod bundle geometries. The code calculations were compared with the experimental data. With the exception of a premature quench, the cladding temperatures were in a reasonable agreement with the data. However, the code predicted low vapor superheats and void fraction oscillations.
- Research Organization:
- Texas A and M, College Station
- OSTI ID:
- 7124392
- Report Number(s):
- CONF-861102-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 53; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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