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Title: Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys

Journal Article · · Nuclear Materials and Energy
 [1]; ORCiD logo [2];  [3]; ORCiD logo [4];  [5];  [6];  [3];  [5];  [2]
  1. Princeton Univ., NJ (United States). Dept. of Chemical and Biological Engineering; OSTI
  2. Princeton Univ., NJ (United States). Dept. of Chemical and Biological Engineering
  3. Princeton Univ., NJ (United States).Princeton Inst. for the Science and Technology of Materials (PRISM)
  4. Stony Brook Univ., NY (United States). Dept. of Materials Science and Chemical Engineering
  5. Univ. of California, San Diego, CA (United States). Center for Energy Research
  6. Stony Brook Univ., NY (United States). Dept. of Materials Science and Chemical Engineering; Stony Brook Univ., NY (United States). Inst. for Advanced Computational Science

Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.

Research Organization:
Princeton Univ., NJ (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); State Univ. of New York (SUNY), Albany, NY (United States); Triad National Security, LLC, Los Alamos, NM (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
89233218CNA000001; NA0003525; SC0017899; SC0019308
OSTI ID:
1803188
Journal Information:
Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Journal Issue: C Vol. 21; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (36)

Presheath profiles in simulated tokamak edge plasmas journal April 1989
Surface morphology and helium retention on tungsten exposed to low energy and high flux helium plasma journal March 2003
Review of high Z materials for PSI applications journal December 1992
Assessment of tungsten for use in the ITER plasma facing components journal October 1998
Mechanism of blister formation on tungsten surface journal September 2003
Nanoscale segregation behavior and high-temperature stability of nanocrystalline W–20at.% Ti journal July 2014
Early stage damage of ultrafine-grained tungsten materials exposed to low energy helium ion irradiation journal April 2015
High-flux plasma exposure of ultra-fine grain tungsten journal November 2016
Hydrogen blister formation and cracking behavior for various tungsten materials journal March 2005
Blister formation and deuterium retention on tungsten exposed to low energy and high flux deuterium plasma journal March 2005
Retention and surface blistering of helium irradiated tungsten as a first wall material journal December 2005
Mechanisms of retention and blistering in near-surface region of tungsten exposed to high flux deuterium plasmas of tens of eV journal August 2007
A description of stress driven bubble growth of helium implanted tungsten journal May 2009
Helium retention and early stages of helium-vacancy complexes formation in low energy helium-implanted tungsten journal February 2013
Surface damage in ultrafine and multimodal grained tungsten materials induced by low energy helium irradiation journal March 2013
Influence of crystal orientation on damages of tungsten exposed to helium plasma journal July 2013
Influence of particle flux density and temperature on surface modifications of tungsten and deuterium retention journal December 2014
The role of grain size in He bubble formation: Implications for swelling resistance journal February 2017
Surface modifications and deuterium retention in polycrystalline and single crystal tungsten as a function of particle flux and temperature journal November 2017
Quantitatively measuring the influence of helium in plasma-exposed tungsten journal August 2017
Initial growth phase of W-fuzz formation in ultra-long pulse helium discharge in LHD journal August 2017
Effect of random surface orientation on W sputtering yields journal December 2018
Softening due to Grain Boundary Cavity Formation and its Competition with Hardening in Helium Implanted Nanocrystalline Tungsten journal February 2018
Retention and thermal desorption of helium in pure tungsten journal November 2016
Observations of suppressed retention and blistering for tungsten exposed to deuterium–helium mixture plasmas journal May 2009
Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions journal August 2009
Effect of He on D retention in W exposed to low-energy, high-fluence (D, He, Ar) mixture plasmas journal August 2011
Surface modification of tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasma and its impact on deuterium retention journal January 2013
Ultrafine tungsten as a plasma-facing component in fusion devices: effect of high flux, high fluence low energy helium irradiation journal June 2014
Probing helium nano-bubble formation in tungsten with grazing incidence small angle x-ray scattering journal March 2015
Deuterium retention in TiC and TaC doped tungsten under low-energy ion irradiation journal April 2014
The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets journal March 2018
Response of tungsten surfaces to helium and hydrogen plasma exposure under ITER relevant steady state and repetitive transient conditions journal September 2017
Thermodynamics of stable nanocrystalline alloys: A Monte Carlo analysis journal February 2014
Solute stabilization of nanocrystalline tungsten against abnormal grain growth journal September 2017
Properties of Mechanically Alloyed W-Ti Materials with Dual Phase Particle Dispersion journal December 2016

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