A simplified mathematical dynamic model of the HTR-10 high temperature gas-cooled reactor with control system design purposes

Author:

Li Haipeng,Huang Xiaojin,Zhang Liangju

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Three-dimensional numerical simulation of flow and heat transport in high temperature nuclear reactors;Becker;Nuclear Engineering and Design,2003

2. Bolnov, V.A., et al., 2004a. GT-MHR code description and potential. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22–24, Paper C27.

3. Bolnov, V.A., et al., 2004b. Simulator development for GT-MHR reactor plant designing. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China, September 22–24, Paper D28.

4. A simple dynamic model of the primary circuit in VVER plants for controller design purposes;Fazekas;Nuclear Engineering and Design,2007

5. Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core;Gao;Nuclear Engineering and Design,2002

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