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Silicon carbide tritium permeation barrier for steel structural components

Buchenauer, D.A.; Kolasinski, Robert K.; Youchison, Dennis L.; Garde, J.; Holschuh, Thomas V.

Chemical vapor deposited (CVD) silicon carbide (SiC) has superior resistance to tritium permeation even after irradiation. Prior work has shown Ultrametfoam to be forgiving when bonded to substrates with large CTE differences. The technical objectives are: (1) Evaluate foams of vanadium, niobium and molybdenum metals and SiC for CTE mitigation between a dense SiC barrier and steel structure; (2) Thermostructural modeling of SiC TPB/Ultramet foam/ferritic steel architecture; (3) Evaluate deuterium permeation of chemical vapor deposited (CVD) SiC; (4) D testing involved construction of a new higher temperature (> 1000 C) permeation testing system and development of improved sealing techniques; (5) Fabricate prototype tube similar to that shown with dimensions of 7cm {theta} and 35cm long; and (6) Tritium and hermeticity testing of prototype tube.

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Plasma-materials interaction results at Sandia National Laboratories

Kolasinski, Robert K.; Buchenauer, D.A.; Cowgill, D.F.; Karnesky, Richard A.; Whaley, Josh A.; Wampler, William R.

Overview of Plasma Materials Interaction (PMI) activities are: (1) Hydrogen diffusion and trapping in metals - (a) Growth of hydrogen precipitates in tungsten PFCs, (b) Temperature dependence of deuterium retention at displacement damage, (c) D retention in W at elevated temperatures; (2) Permeation - (a) Gas driven permeation results for W/Mo/SiC, (b) Plasma-driven permeation test stand for TPE; and (3) Surface studies - (a) H-sensor development, (b) Adsorption of oxygen and hydrogen on beryllium surfaces.

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The impact of specific surface area on the retention of deuterium in carbon fiber composite materials

Fusion Engineering and Design

Kolasinski, Robert K.; Umstadter, K.R.; Sharpe, J.P.; Causey, Rion A.; Pawelko, R.J.; Whaley, Josh A.; Buchenauer, D.A.; Shimada, M.

In this study, the PISCES-A linear plasma instrument has been used to characterize retention in several carbon fiber composites in order to better understand the factors which lead to elevated retention levels in these materials. The PISCES instrument is capable of subjecting materials to intense fluxes (up to 1022 m-2 s-1) of low energy (150 eV) D+ ions, producing conditions similar to those encountered by plasma facing components in a fusion reactor. In this investigation, three CFCs (fabricated with different manufacturing processes) are compared with the N11 composite used in the Tore Supra reactor. The specific surface areas for these materials were within the range of 0.14-0.55 m2/g. The plasma bombardment conditions were adjusted to provide doses on the order of 1025-1026 m-2 at a sample temperature of 200 °C. After removal from PISCES-A, the amount of D retained in the sample surface was determined via thermal desorption spectroscopy. The measured retention showed a strong correlation with the type of material used and the corresponding BET surface area. By using a CFC with a lower internal porosity, one could expect a reduction in retention by a factor of 5 or more. © 2008 Elsevier B.V.

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Results 51–61 of 61
Results 51–61 of 61