Validation of the sub-channel code F-COBRA-TF

Author:

Glück M.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. Aydogan, F., Hochreiter, L.E., Ivanov, K., 2007. Correlation for the bundle averaged void fraction measured with X-ray densitometers in the OECD/NRC BFBT benchmark database. Technical note within the scope of the OECD/NRC BFBT benchmark, April 29.

2. A Two-Phase Turbulent Mixing Model for Flow in Rod Bundles;Beus,1970

3. Contributions with the sub-channel code F-COBRA-TF to the NUPEC BWR full-size fine-mesh bundle test (BFBT) benchmark (Exercises I-1 and II-0);Glück,2006

4. KATHY: FRAMATOME ANP's thermal hydraulic test loop;Kreuter,2004

5. The Thermal Hydraulics of a Boiling Water Nuclear Reactor;Lahey,1977

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