Journal ArticleDOI
Modelling deuterium release during thermal desorption of D + -irradiated tungsten
M. Poon,A.A. Haasz,J.W. Davis +2 more
TLDR
In this article, the authors used SIMS measurements of implantation profiles and using the multi-trap diffusion code TMAP7 to model the thermal desorption profiles of single crystal tungsten.About:
This article is published in Journal of Nuclear Materials.The article was published on 2008-03-15. It has received 168 citations till now. The article focuses on the topics: Thermal desorption & Thermal desorption spectroscopy.read more
Citations
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Journal ArticleDOI
Hydrogen in tungsten: Absorption, diffusion, vacancy trapping, and decohesion
TL;DR: In this article, the authors report results from periodic density-functional theory calculations for three crucial aspects of this interaction: surface-to-subsurface diffusion of H into W, trapping of H at vacancies, and Henhanced decohesion, with a view to assess the likely extent of hydrogen isotope incorporation into tungsten reactor walls.
Journal ArticleDOI
Investigating behaviours of hydrogen in a tungsten grain boundary by first principles: from dissolution and diffusion to a trapping mechanism
TL;DR: In this paper, the authors investigated the dissolution, segregation and diffusion of hydrogen in a tungsten grain boundary (GB) using a first-principles method in order to understand the GB trapping mechanism of H.
Book ChapterDOI
4.17 – Tungsten as a Plasma-Facing Material
TL;DR: The characterization and understanding of the material's behavior under high transient thermal loads, neutron irradiation-induced material degradation and transmutation, hydrogen and helium attack at the plasma-facing surface, and thermal fatigue under steady state heat fluxes as part of a tungsten component are studied in this paper.
Journal ArticleDOI
Hydrogen diffusion and vacancies formation in tungsten: Density Functional Theory calculations and statistical models
TL;DR: In this paper, the authors investigated the interaction of hydrogen with tungsten by means of the density functional theory (DFT) and statistical methods based on the transition-state theory and thermodynamics, and concluded that the discrepancy existing between the experimental diffusion coefficient measured by Frauenfelder (1969) and the one calculated by DFT would be reconciled provided one uses two different diffusion regimes that would depend on temperature and vacancies concentration.
Journal ArticleDOI
Recent advances on hydrogen retention in ITER's plasma-facing materials: Beryllium, carbon and tungsten
C. H. Skinner,A.A. Haasz,V.Kh. Alimov,N. Bekris,R. A. Causey,R. E. H. Clark,J. P. Coad,J.W. Davis,R. P. Doerner,M. Mayer,A. Pisarev,J. Roth,Tetsuo Tanabe +12 more
TL;DR: The results of the Coordinated Research Project (CRP) on the overall topic of tritium inventory in fusion reactors during the period 2001-2006 are summarized in this paper together with recommendations for ITER as discussed by the authors.
References
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Journal ArticleDOI
Interstitial Atomic Diffusion Coefficients
Charles Wert,Clarence Zener +1 more
TL;DR: In this paper, an attempt is made to interpret the temperature independent factor of the previously determined diffusion coefficients of interstitial solute atoms in metals, and the associated entropy factors are consistent with the theoretical range.
Journal ArticleDOI
Solution and Diffusion of Hydrogen in Tungsten
TL;DR: In this paper, the authors used mass spectroscopic and ultrahigh vacuum techniques to investigate the solubility and diffusion of hydrogen in tungsten with high temperatures between 1100 and 2400 K. The authors derived the diffusion constants, D = 4.1×10−3×exp (−9000/RT) cm2/sec.
Journal ArticleDOI
Deuterium retention in tungsten in dependence of the surface conditions
TL;DR: In this paper, a review of hydrogen isotope retention and migration in tungsten (W) is presented, where a large scatter of the deuterium (D) retention database is used to clarify the mechanism of hydrogen inventory in W. Several points are reviewed: (i) inventory in pure W, (ii) inventory of W pre-implanted by carbon ions, and (iii) inventory inventory in Tungsten oxide.
Journal ArticleDOI
Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons
TL;DR: The Tritium Plasma Experiment Experiment (TPE) has been used to examine the retention of tritium in tungsten exposed to very high fluxes of 100 eV tritons as mentioned in this paper.
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Deuterium retention in tungsten in dependence of the surface conditions
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Recent analysis of key plasma wall interactions issues for ITER
J. Roth,E. Tsitrone,A. Loarte,Th. Loarer,G.F. Counsell,Rudolf Neu,V. Philipps,S. Brezinsek,Michael Lehnen,P. Coad,Ch. Grisolia,Klaus Schmid,K. Krieger,A. Kallenbach,Bruce Lipschultz,R.P. Doerner,Rion A. Causey,V.K. Alimov,W. M. Shu,O. V. Ogorodnikova,A. Kirschner,Gianfranco Federici,A.S. Kukushkin +22 more