[Author]: and A. Tahir Documents

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Number of files: 1

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1987-06-01---------Jump to [Top]

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1. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by M.B. Carver, R.A. Judd, J.e. Kiteley, and A. Tahir, CNS, 1987-06-01. Doc type: Paper.
   Summary: The ASSERT subchannel code has been developed specifically to model flow and phase distributions within CANDU fuel bundles. ASSERT uses a drift-flux model that permits the phases to have unequal velocities, and can thus model phase separation tendencies that may occur in horizontal flow. The basic principles of ASSERT are outlined, and computed results are compared against data from various experiments for validation purposes. The paper concludes with an example of the use of the code to predict critical heat flux in CANDU geometries.
   Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering Nuclear Engineering [Topic] Fluid Mechanics [Phase] Design Analysis [Audience] Engineer Grad Ugrad
   - The Drift Flux Model in the ASSERTSubchannel Code NJC-1-2-08.pdf (742 kb)