Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes

Author:

Zheng Yanhua,Lapins J.,Laurien E.,Shi L.,Zhang Z.

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

Reference17 articles.

1. Experimental investigations of thermo-hydraulics in HTR-spherical granule assembly in comparison with the code THERMIX;Burthels,1983

2. Cleveland, J.C., Greene, S.R., 1986. Application of THERMIX-KONVEK code to accident analysis of modular pebble bed high temperature reactors (HTRs). ORNL/TM-9905, August.

3. TINTE modular code system for computational simulation of transient processes in the primary circuit of a pebble-bed high-temperature gas-cooled reactor;Gerwin;Nucl. Sci. Eng.,1989

4. Consequences of delayed air ingress following a depressurization accident in a high temperature reactor;Haque,2006

5. Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRs;Hossain;Nucl. Eng. Des.,2008

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