Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma

Wang, Shiwei; Zhu, Xiu-Li; Cheng, Long; Guo, Wangguo; Liu, Mi; Xu, Chuan; Yuan, Yue; Fu, Engang; Cao, Xingzhong; Lü, Guang-Hong

doi:10.1016/j.jnucmat.2018.05.082

Cited by 28 publications

(24 citation statements)

References 28 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…However, under the deuterium-tritium fusion reaction, PFMs-W has to withstand tremendous damages produced by high energy neutron (~ 14 MeV) and high thermal flux (~ 10 MW•m −2 ). Besides, a continuous production of helium (He) through (n, α) transmutation reactions in the bulk of PFMs-W are easy to be captured by irradiation-induced defects (such as vacancies, clusters, voids and dislocations) to form He-defect complexes even He bubbles during the diffusion process, leading to the degradation of the material mechanical properties including irradiation hardening and swelling [4,5]. Therefore, it is significant to understand the physical fundamental behind these changes introduced by fusion neutrons.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Thermal kinetics of micro-defects in He-ion implanted W and W5Re alloys

Liu

Song

et al. 2021

Tungsten

Self Cite

View full text Add to dashboard Cite

To investigate the thermal evolution of vacancy-type defects in He-ion irradiated W and W5Re alloy, different isochronal annealing treatments from 373 to 1273 K were conducted on the irradiated materials. Positron annihilation spectroscopy including positron annihilation lifetime spectroscopy and Doppler broadening spectroscopy were mainly used to characterize the micro-defects evolution. The results showed that the thermal evolution characteristics of defects in both W and W5Re were similar. After He-ion irradiation, mono-vacancies with positron annihilation lifetime of ~ 190 ps were detected in W, together with a large amount of dislocation loops with positron annihilation lifetime of ~ 150 ps in W5Re alloys. The coarsening of vacancy clusters at the expense of small vacancy clusters was the main thermal evolution feature of vacancy-type defects in both W and W5Re when annealing temperature increased to 1073 K. In this progress, the positron annihilation lifetime increased to ~ 350 ps (clusters composed of 4 –8 mono-vacancies) in both W and W5Re. As the temperature increased to 1273 K, the positron annihilation lifetime decreased to ~ 240 ps, which was attributed to a significant population reduction of the dislocation loops, the dissociation of large HenVm complexes and the annealing of micro-voids in both W and W5Re. The vacancy-type defects in W5Re were more susceptible to the annealing temperature because of the formation of vacancy cluster-Re complexes. Re clusters in irradiated W5Re alloy could serve as the nucleation sites of He bubbles, which promoted the swelling and protrusion formation on the surface.

show abstract

Section: Introductionmentioning

confidence: 99%

“…High resolution transmission electron microscopy (TEM) is preferred by many researchers to investigate the structure of neutron/ion irradiation-induced micro-defects [5,10]. However, it is difficult to detect the defect with size smaller than 1 nm by TEM.…”

Section: Introductionmentioning

confidence: 99%

Thermal kinetics of micro-defects in He-ion implanted W and W5Re alloys

Liu

Song

et al. 2021

Tungsten

Self Cite

View full text Add to dashboard Cite

show abstract

“…The retention of hydrogen isotopes in W is mainly affected by trap sites, such as dislocations, grain boundaries, vacancies and microvoids in the matrix material [7][8][9][10] .…”

Section: Introductionmentioning

confidence: 99%

“…It is necessary to evaluate the release behaviors of hydrogen isotopes trapped in different sites. There have been extensive studies on the thermal desorption of deuterium(D) in W by plasma exposure [7,[11][12][13] . The 'ion-induced' vacancies are usually associated with D agglomeration in molecules and bubbles near the implanted surface.…”

Section: Introductionmentioning

confidence: 99%

Comparison of deuterium retention in tungsten exposed to deuterium plasma and gas

Wang

Pan

et al. 2020

Nuclear Materials and Energy

View full text Add to dashboard Cite

“…Recent research in STEP involves plasma testing of new W-based materials [22][23][24][25], characterizations of H plasmainduced defects [26,27], synergetic effects of high-energy ion implantation and plasma irradiation [28,29], and He behaviours in steels [30,31]. This contribution will first devote one session to the investigation of H plasma-induced defects in pure W to shed light on the fundamental evolution of defects during plasma irradiation.…”

Section: Introductionmentioning

confidence: 99%

Recent studies of tungsten-based plasma-facing materials in the linear plasma device STEP

et al. 2019

Self Cite

View full text Add to dashboard Cite

This contribution summarized the recent studies of tungsten-based plasma-facing materials in the linear plasma device like the simulator for tokamak edge plasma (STEP), focusing on the examination of newly developed tungsten (W)-based materials and plasma-induced defects in pure W. Pure W, W-V, W-Y 2 O 3 and W-ZrC samples were exposed to a high-flux plasma of ~ 10 21 -10 22 m −2 s −1 with a fluence up to 10 26 m −2 at a surface temperature below 500 K. The investigation of fundamental evolution of plasma-induced defects in pure W indicated a critical role of hydrogen-dislocation interactions. Suppressed surface blistering was observed in all W-based materials, but deuterium desorption behavior and retention were distinct with respect to different materials. The studies showed that the linear plasma device like the STEP was indispensable in the understanding of plasma-material interactions and the qualification of new materials for future fusion reactors.

show abstract

Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma

Cited by 28 publications

References 28 publications

Thermal kinetics of micro-defects in He-ion implanted W and W5Re alloys

Thermal kinetics of micro-defects in He-ion implanted W and W5Re alloys

Comparison of deuterium retention in tungsten exposed to deuterium plasma and gas

Recent studies of tungsten-based plasma-facing materials in the linear plasma device STEP

Contact Info

Product

Resources

About