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

Abstract

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.

Authors:
Publication Date:
Research Org.:
Union Carbide Corp., Oak Ridge, TN (USA). Nuclear Div.
OSTI Identifier:
5745699
Report Number(s):
ORNL/CSD/TM-78
TRN: 80-000809
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COATED FUEL PARTICLES; PERFORMANCE TESTING; PERMEABILITY; HTGR TYPE REACTORS; ANNEALING; CARBON; RARE GASES; ELEMENTS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT TREATMENTS; NONMETALS; REACTORS; TESTING; 210300* - Power Reactors, Nonbreeding, Graphite Moderated

Citation Formats

Tolliver, J S. Numerical determination of inert gas permeability parameters of High-Temperature Gas-Cooled Reactor (HTGR) fuel-particles. United States: N. p., 1979. Web. doi:10.2172/5745699.
Tolliver, J S. Numerical determination of inert gas permeability parameters of High-Temperature Gas-Cooled Reactor (HTGR) fuel-particles. United States. https://doi.org/10.2172/5745699
Tolliver, J S. 1979. "Numerical determination of inert gas permeability parameters of High-Temperature Gas-Cooled Reactor (HTGR) fuel-particles". United States. https://doi.org/10.2172/5745699. https://www.osti.gov/servlets/purl/5745699.
@article{osti_5745699,
title = {Numerical determination of inert gas permeability parameters of High-Temperature Gas-Cooled Reactor (HTGR) fuel-particles},
author = {Tolliver, J S},
abstractNote = {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.},
doi = {10.2172/5745699},
url = {https://www.osti.gov/biblio/5745699}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {11}
}