A.S. Teimane , E. Pajuste , A. Actins , P. Kalnina , A. Zekunde , A. Kizilovs , D. Demange , J. Somvanshi , J. van der Laan
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引用次数: 0
Abstract
Permeation, effective diffusivity and solubility experiments of tritium in thermal insulation materials proposed for ITER is vital for assessing the conditions required for the operation of the Test Blanket System, including its maintenance. With these results, simulation models can be prepared to predict tritium migration behaviour and therefore, air in the estimation of tritium inventory within the concerned components, and the concerned outgassing rates.
This paper looks at three different grades of microporous thermal insulation material, which have been tested for the behaviour of tritium in the form of HT. Effective diffusion coefficients, activation energy and effective solubility has been assess together with characterization of the material.
An effective diffusion coefficient, which involves gas transport through structure defects, has been evaluated based on Fick's law. Effective diffusivity results are obtained in the range of 1 to 5 × 10–1 cm2/s and the results show no significant difference between the three grades analysed. Effective diffusivity was found to be significantly larger than in other silica-based materials, which can be explained by structural defects observed using SEM. Calculations show that the material's solubility is mostly dominated by its porosity.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.