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Title: Behavior and properties of helium cavities in ductile-phase-toughened tungsten irradiated with He+ ions at an elevated temperature

Journal Article · · Materialia

Ductile-phase toughened tungsten (DPT W) composites have demonstrated a great potential for plasma-facing components in fusion power systems. These materials can retain the outstanding thermomechanical properties of W while significantly enhancing the fracture toughness. The DPT W composite in this study consists of W particles (88 wt.%) embedded in a ductile NiFeW (12 wt.%) solution matrix. Irradiation of the composite was performed with 90 keV He+ ions to 1.0 × 1017 He+/cm2 at 973 K. The He cavities formed in both W and NiFeW phases are examined using convergent-beam scanning transmission electron microscopy (CB-STEM) at an atomic-level resolution. Full-range depth profiles of the He cavity diameters and number densities are analyzed. The results show that the average cavity diameter in NiFeW is ~2.7 times that in W, while the number density is an order of magnitude lower. A quantitative analysis of the He density and pressure in the cavities is also achieved using STEM electron energy loss spectroscopy (STEM-EELS) mapping. The He atoms in the cavities in NiFeW are found to be under-pressurized, while those in similar-sized cavities in W are not detectable. Further, the He energy-loss shift exhibits a linear relationship with the He density in cavities in NiFeW, with the slope comparable to that for martensitic steel.

Research Organization:
Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)
Grant/Contract Number:
AC05-76RL01830
OSTI ID:
1974623
Alternate ID(s):
OSTI ID: 2000657; OSTI ID: 1984253
Report Number(s):
PNNL-SA-182610
Journal Information:
Materialia, Journal Name: Materialia Vol. 29; ISSN 2589-1529
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (48)

Effect of purity on the vacancy defects induced in self–irradiated tungsten: A combination of PAS and TEM journal December 2021
On the coarsening of gas-filled pores in solids journal November 1973
The density and pressure of helium in bubbles in implanted metals: A critical review journal January 1985
Continuum-scale modeling of helium bubble bursting under plasma-exposed tungsten surfaces journal November 2018
Fusion power: a challenge for materials science journal July 2010
Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade journal December 2018
Probing Physical Properties of Confined Fluids within Individual Nanobubbles journal January 2008
Molecular dynamics study of helium bubble pressure in tungsten journal June 2015
Atomistic simulations and experimental measurements of helium nano-bubbles in nickel journal November 2017
Helium Bubble Behaviour in b.c.c. Metals Below 0.65Formula journal June 1981
A new equation of state for helium nanobubbles embedded in UO2 matrix calculated via molecular dynamics simulations journal May 2019
STEM–EELS analysis reveals stable high-density He in nanopores of amorphous silicon coatings deposited by magnetron sputtering journal January 2015
Radiation damage problems in high power spallation neutron sources journal August 1995
A procedure for measuring the helium density and pressure in nanometre-sized bubbles in irradiated materials using electron-energy-loss spectroscopy journal July 2000
The Use of Tungsten in Fusion Reactors: A Review of the Hydrogen Retention and Migration Properties journal January 2001
Precipitation in a liquid phase sintered WNiFe alloy journal December 1985
EELS log-ratio technique for specimen-thickness measurement in the TEM journal February 1988
The association of hydrogen with nanometre bubbles of helium implanted into zirconium journal July 2018
Structural materials for fission & fusion energy journal November 2009
Theoretical Model of Helium Bubble Growth and Density in Plasma-Facing Metals journal February 2020
Behavior of helium cavities in ion-irradiated W-Ni-Fe ductile-phase toughened tungsten journal April 2022
Competing Kinetics and He Bubble Morphology in W journal March 2015
Annealing of radiation-induced defects in tungsten: Positron annihilation spectroscopy study journal April 2019
Predicting the performance of tungsten in a fusion environment: a literature review journal June 2016
Surface Self‐Diffusion and Surface Energy of Nickel journal February 1967
Corrigendum and Addendum: Helium flux effects on bubble growth and surface morphology in plasma-facing tungsten from large-scale molecular dynamics simulations (2019 Nucl. Fusion 59 066035) journal October 2020
Helium retention, bubble superlattice formation and surface blistering in helium-irradiated tungsten journal March 2021
Helium accumulation in metals during irradiation – where do we stand? journal December 2003
Calculated Size Distributions for Gas Bubble Migration and Coalescence in Solids journal January 1967
Recent progress in research on tungsten materials for nuclear fusion applications in Europe journal January 2013
In situ controlled modification of the helium density in single helium-filled nanobubbles journal March 2014
Neutron-induced transmutation effects in W and W-alloys in a fusion environment journal March 2011
Theoretical interpretation of the vacuum ultraviolet reflectance of liquid helium and of the absorption spectra of helium microbubbles in aluminum journal September 1983
Thermal annealing behavior of hydrogen and surface topography of H 2 + ion implanted tungsten journal January 2018
Investigation of interfacial strength in nacre-mimicking tungsten heavy alloys for nuclear fusion applications journal January 2023
Formation of bubbles and blisters in hydrogen ion implanted polycrystalline tungsten journal October 2018
The influence of helium on the bulk properties of fusion reactor structural materials journal August 1984
Dose rate effects on damage accumulation and void growth in self-ion irradiated tungsten journal July 2021
Investigation of the behaviour of helium and radiation defects after room temperature he-implantation of nickel and copper journal January 1983
An improved equation of state for inert gases at high pressures journal December 1980
Study by EELS of helium bubbles in a martensitic steel journal August 2009
The density and pressure of helium in bubbles in metals journal January 1983
The role of fission gas re-solution during post-irradiation heat treatment journal February 1962
Equilibrium Crystal Shape of Ni from First Principles journal October 2013
On the remarkable fracture toughness of 90 to 97W-NiFe alloys revealing powerful new ductile phase toughening mechanisms journal March 2020
First simultaneous detection of helium and tritium inside bubbles in beryllium journal December 2019
Review on the EFDA programme on tungsten materials technology and science journal October 2011
Erratum to “On the use of SRIM for computing radiation damage exposure” [Nucl. Instrum. Methods Phys. Res. B 310 (2013) 75–80] journal November 2019