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Assessment of Thermal-Hydraulic Characteristics of the Primary Circuit

G. Francois, G. Azarian, J. C. Astegiano, C. Lacroix, G. Poet

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 55-63

Technical Paper / dx.doi.org/10.13182/NSE90-A23757

Thermal-hydraulic studies are presented of the primary circuit performed in a large number of water mock-ups in relation to physical problems that occurred during the commissioning of Superphénix. Mock-up results and numerical model predictions are compared with reactor measurements in steady-state or in transient conditions.