The goal of this project is to determine changes in adsorption and desorption of fission products to/from nuclear-grade graphite in response to a changing chemical environment. First, the project team will employ principle calculations and thermodynamic analysis to predict stability of fission products on graphite in the presence of structural defects commonly observed in very high- temperature reactor (VHTR) graphites. Desorption rates will be determined as a function of partial pressure of oxygen and iodine, relative humidity, and temperature. They will then carry out experimental characterization to determine the statistical distribution of structural features. This structural information will yield distributions of binding sites to be u...
A proposal is given of an approach to a fission-product trapping system which appears feasible on th...
Supplementary information for the article "A Grand Canonical Monte Carlo simulation for the evaluat...
This thesis investigates graphites used in nuclear materials engineering applications – so called nu...
A clear understanding of the diffusive behaviour of a wide variety of impurities is essential for th...
A clear understanding of the diffusive behaviour of a wide variety of impurities is essential for th...
A clear understanding of the diffusive behaviour of a wide variety of impurities is essential for th...
The entire thesis text is included in the research.pdf file; the official abstract appears in the sh...
The present report attempts to give an introduction into the subject of fission-product-transport in...
High-temperature gas-cooled reactors (HTGRs) are one of the candidates being considered for the repl...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
The transport of fission products from points of origin in unclad graphite matrix-type fuels to the ...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
The experimental data on sorption and solubility of hydrogen isotopes in graphite in a wide ranges o...
The geometries, adsorption energies, and electronic structures of Cs, Sr, and Ag atoms on matrix gra...
A new development in graphite fuel elements for high temperature reactors is the application of a si...
A proposal is given of an approach to a fission-product trapping system which appears feasible on th...
Supplementary information for the article "A Grand Canonical Monte Carlo simulation for the evaluat...
This thesis investigates graphites used in nuclear materials engineering applications – so called nu...
A clear understanding of the diffusive behaviour of a wide variety of impurities is essential for th...
A clear understanding of the diffusive behaviour of a wide variety of impurities is essential for th...
A clear understanding of the diffusive behaviour of a wide variety of impurities is essential for th...
The entire thesis text is included in the research.pdf file; the official abstract appears in the sh...
The present report attempts to give an introduction into the subject of fission-product-transport in...
High-temperature gas-cooled reactors (HTGRs) are one of the candidates being considered for the repl...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
The transport of fission products from points of origin in unclad graphite matrix-type fuels to the ...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
The experimental data on sorption and solubility of hydrogen isotopes in graphite in a wide ranges o...
The geometries, adsorption energies, and electronic structures of Cs, Sr, and Ag atoms on matrix gra...
A new development in graphite fuel elements for high temperature reactors is the application of a si...
A proposal is given of an approach to a fission-product trapping system which appears feasible on th...
Supplementary information for the article "A Grand Canonical Monte Carlo simulation for the evaluat...
This thesis investigates graphites used in nuclear materials engineering applications – so called nu...