Numerical determination of inert gas permeability parameters of High-Temperature Gas-Cooled Reactor (HTGR) fuel-particles

Technical Report · Thu Nov 01 00:00:00 EST 1979

DOI:https://doi.org/10.2172/5745699· OSTI ID:5745699

Tolliver, J S

The high temperature diffusion of inert gases through an outer layer of dense carbon into the ThO/sub 2/ core of biso-coated High-Temperature Gas-Cooled Reactor (HTGR) fuel-particles is studied numerically. A mathematical model of diffusion through a dense spherical shell into a spherical core is used to numerically calculate the theoretical gas content of the core. This theoretical calculation, in tandem with an optimizing computer code and experimental data, is used to determine the diffusion coefficient of the shell and the porosities of the shell and inner core. The activation energy is also determined for use in an Arrhenius relationship between the diffusion coefficients and absolute temperature.

• Research Organization: Union Carbide Corp., Oak Ridge, TN (USA). Nuclear Div.
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5745699
• Report Number(s): ORNL/CSD/TM-78; TRN: 80-000809
• Country of Publication: United States
• Language: English

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