Hydrogen trapping in and release from tungsten: Modeling and comparison with graphite with regard to its use as fusion reactor material

Franzen, P.; Garcı́a-Rosales, C.; Plank, Harald; Alimov, V. Kh.

doi:10.1016/s0022-3115(97)80198-5

Cited by 69 publications

(33 citation statements)

References 8 publications

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“…The corresponding value of 6.9 ϫ 10 Ϫ5 traps0 tungsten was calculated by Anderl et al 71 from permeation data of a polycrystalline sample. We also found a value of ;10 Ϫ2 traps0tungsten in the literature, 32 calculated from reemission data for single-crystalline and wrought samples. This latter value was not used since it seems quite high in comparison with the previous one.…”

Section: Iiic Kmcss Of Hydrogen Implantationsupporting

confidence: 73%

“…of hydrogen and its isotopes in tungsten, measured over various temperature ranges. [28][29][30][31][32][33] The result that is recommended by at least Causey and Venhaus 2 and Causey 34 is that of Frauenfelder:~D 0 , E M ! ϭ 4.1 Ϫ2.0 ϩ5.0 ϫ 10 Ϫ7 m 2 s Ϫ1 , 0.39 6 0.09 eV!~Ref.…”

Section: Ia Hydrogen and Helium Bubbles In Tungstenmentioning

confidence: 99%

“…This type of datum exists for small clusters, consisting of 1 to 2 hydrogen atoms in a vacancy 75 ; but without some growth mechanism that actually increases the size of the cavity~from one vacancy!, these clusters cannot account for the large bubbles. In the literature there are reports of traps with energies between 0.5 eV~"natural traps" in unirradiated single-crystalline tungsten 32 ! and 1.6 eV~traps in an unirradiated and unannealed polycrystalline tungsten 72 !, but the dependence of the binding energies on the hydrogen occupancy has not been reported.…”

Section: Ivb1 Hydrogenmentioning

confidence: 99%

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The Depths of Hydrogen and Helium Bubbles in Tungsten: A Comparison

Henriksson

Nordlund

Krasheninnikov

et al. 2006

Fusion Science and Technology

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Section: Iiic Kmcss Of Hydrogen Implantationsupporting

confidence: 73%

Section: Ia Hydrogen and Helium Bubbles In Tungstenmentioning

confidence: 99%

Section: Ivb1 Hydrogenmentioning

confidence: 99%

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The Depths of Hydrogen and Helium Bubbles in Tungsten: A Comparison

Henriksson

Nordlund

Krasheninnikov

et al. 2006

Fusion Science and Technology

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“…[4] reported two trap sites, one at 0.85 eV with a density of 0.01 trap/W and a second at 1.4 eV with a density of 0.07 trapN. From thermal desorption data, Franzen et al [5] gave one trap at 0.5 eV with a trap/W value of 0.01 and a second at 1.2 eV with 0.16 t r a p N existing only in the implantation zone. Anderl et al [6] reported their deuterium transport in polycrystalline tungsten to be dominated by a 1.34 to 1.56 eV trap that decreased in concentration due to annealing.…”

Section: Methodsmentioning

confidence: 99%

Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons

Causey

Wilson

Venhaus

et al. 1998

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Tungsten is a candidate material for ITER as well as other future magnetic fusion energy devices. Tungsten is well suited for certain hsion applications in that it has a high threshold for sputtering as well as a very high melting point. As with all materials to be used on the inside of a tokamak or similar device, there is a need to know the behavior of hydrogen isotopes embedded in the material. With this need in mind, the Tritium Plasma Experiment (TPE) has been used to examine the retention of tritium in tungsten exposed to very high fluxes of 100 eV tritons. Both tungsten and tungsten containing 1% lanthanum oxide were used in these experiments. Measurements were performed over the temperature range of 423 to 973 K. After exposure to the tritium plasma, the samples were transferred to an outgassing system containing an ionization chamber for detection of the released tritium. The samples were outgassed using linear ramps from room temperature up to 1473 K. Unlike most other materials exposed to energetic tritium, the tritium retention in tungsten reaches a maximum at intermediate temperatures with low retention at both high and low temperatures. For the very high triton fluences used (>lo25 T/m2), the fractional retention of the tritium was below 0.02% of the incident particles. This report presents not only the results of the tritium retention, but also includes the modeling of the results and the implication for ITER and other future fusion devices where tungsten is used. DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness. or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer. or otherwise does not necessarily constitute or imply its endorsement, m o mmendktion, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect thosc of the United States Government or any agency thereof.

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“…Although many studies concerning hydrogen retention and release in tungsten (W) have been performed [1][2][3][4][5][6][7], the behavior of implanted hydrogen isotopes in W is still not fully understood: The published data are often in disagreement and sometimes even contradictory. In the present paper, deuterium (D) retention in W is studied in a wide range of experimental conditions: various fluences, temperatures and energies.…”

Section: Introductionmentioning

confidence: 99%