skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Changes in the structure and D desorptive release from W-D co-deposit layers caused by thermal annealing

Journal Article · · Nuclear Materials and Energy

Sponsoring Organization:
USDOE
Grant/Contract Number:
-FG02-07ER54912; -SC0022528
OSTI ID:
1960098
Journal Information:
Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Vol. 34 Journal Issue: C; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (26)

Deuterium retention and release in tungsten co-deposited layers journal June 2009
Alpha- vs. beta-W nanocrystalline thin films: A comprehensive study of sputter parameters and resulting materials' properties journal February 2015
Deuterium and Helium Release and Microstructure of Tungsten Deposition Layers Formed by RF Plasma Sputtering journal August 2008
Codeposition of deuterium with ITER materials journal February 2009
Tungsten-deuterium co-deposition: Experiment and analytical description journal March 2018
Making tungsten work – ICFRM-14 session T26 paper 501 Nygren et al. making tungsten work journal October 2011
The microstructure of sputter‐deposited coatings journal November 1986
Dependence of spin pumping in W/CoFeB heterostructures on the structural phase of tungsten journal January 2019
Use of tungsten material for the ITER divertor journal December 2016
Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency journal January 2019
Diffusion-trapping modelling of hydrogen recycling in tungsten under ELM-like heat loads journal January 2016
Modeling of Hydrogen Retention and Outgassing from Co-Deposits with Distributed Energy States: Modeling of Hydrogen Retention and Outgassing from Co-Deposits with Distributed Energy States journal June 2014
Expanding the capability of reaction-diffusion codes using pseudo traps and temperature partitioning: Applied to hydrogen uptake and release from tungsten journal September 2018
Super-saturated hydrogen effects on radiation damages in tungsten under the high-flux divertor plasma irradiation journal July 2015
Reduced defect recovery in self-ion damaged W due to simultaneous deuterium exposure during annealing journal January 2022
Retention in tungsten resulting from extremely high fluence plasma exposure journal December 2016
Control of plasma parameters by using noble gas admixtures
  • Taylor, Kurt J.; Yun, Seokmin; Tynan, George R.
  • Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, Vol. 22, Issue 5 https://doi.org/10.1116/1.1772375
journal September 2004
Comparing deuterium retention in tungsten films measured by temperature programmed desorption and nuclear reaction analysis journal April 2013
Deuterium trapping in tungsten deposition layers formed by deuterium plasma sputtering journal April 2010
Effect of He on D retention in W exposed to low-energy, high-fluence (D, He, Ar) mixture plasmas journal August 2011
XRD line profile analysis of tungsten thin films journal October 2005
Deuterium retention and release behaviours of tungsten and deuterium co-deposited layers journal April 2018
Experimental study and modelling of deuterium thermal release from Be–D co-deposited layers journal April 2014
Recent progress in research on tungsten materials for nuclear fusion applications in Europe journal January 2013
Recrystallisation temperature of tungsten as a function of the heating ramp journal July 2006
Modeling of Multispecies Dynamics in Fusion-Related Materials with FACE journal January 2017

Similar Records

Thermal release of D2 from new Be-D co-deposits on previously baked co-deposits
Journal Article · Tue Dec 01 00:00:00 EST 2015 · Journal of Nuclear Materials · OSTI ID:1960098

TMAP modeling of D release from baked multi-layer Be–D co-deposits
Journal Article · Fri Mar 06 00:00:00 EST 2020 · Physica Scripta · OSTI ID:1960098

The influence of D 2 pressure on D retention and release from Be co-deposits
Journal Article · Wed Sep 01 00:00:00 EDT 2021 · Nuclear Materials and Energy · OSTI ID:1960098

Related Subjects