Studies on supercritical water reactor fuel assemblies using the sub-channel code COBRA-EN

Author:

Ammirabile Luca

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

Reference20 articles.

1. Basile, D., Beghi, M., Chierici, R., Salina, E., Brega, E., 1999. COBRA-EN: an upgraded version of the COBRA-3C/MIT code for thermal hydraulic transient analysis of light water reactor fuel assemblies and cores. Report 1010/1, ENELCRTN, Milano.

2. Bishop, A.A., Sandberg, R.O., Tong, L.S., 1964. Forced convection heat transfer to water at near critical temperatures and supercritical pressures, WCAP-2056-P, Part-III-B.

3. Core design and subchannel analysis of a superfast reactor;Cao;Journal of Nuclear Science and Technology,2008

4. Cheng, X., Schulenberg, T., 2001. Heat transfer at supercritical pressures—literature review and application to an HPLWR. Scientific Report FZKA 6609, FzK.

5. Design analysis of core assemblies for supercritical pressure conditions;Cheng;Nuclear Engineering and Design,2003

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