Experimental measurement of stiffness coefficient of high-temperature graphite pebble fuel elements in helium at high temperatures

Author:

Si Minghao,Gui NanORCID,Sun Yanfei,Yang Xingtuan,Tu Jiyuan,Jiang Shengyao

Funder

National Major Science and Technology Projects of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Pebble-bed modular reactor: a generation IV high-temperature gas-cooled reactor;Koster;Proc. Inst. Mech. Eng. A J. Power Energy,2004

2. Parameter analysis and wall effect of radiative heat transfer for CFD-DEM simulation in nuclear packed pebble bed;Wu;Exp. Computat. Multiphase Flow,2021

3. The design features of the HTR-10;Wu;Nucl. Eng. Des.,2002

4. Current Status and Future Development of Modular High Temperature Gas Cooled Reactor Technology[R];Agency,2001

5. Future HTGR developments in China after the criticality of the HTR-10;Zhang;Nucl. Eng. Des.,2002

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