연구동향 분석

Effect of surface quality on hydrogen/helium irradiation behavior in tungsten

Hongyu Chen Qiu Xu Jiahuan Wang Peng Li Julong Yuan Binghai Lyu Jinhu Wang Kazutoshi Tokunaga Gang Yao Laima Luo Yucheng Wu 2022년

논문상세정보
인용/피인용
' Effect of surface quality on hydrogen/helium irradiation behavior in tungsten' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • D2
  • He irradiation
  • Radiation resistance
  • Surface quality
  • Tungsten
  • þ retention
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
62 0

0.0%

' Effect of surface quality on hydrogen/helium irradiation behavior in tungsten' 의 참고문헌

  • The effect of hot isostatic pressing on thermal conductivity of additively manufactured pure tungsten
    J. H. Chen [2020]
  • Suppression of blister formation and deuterium retention on tungsten surface due to mechanical polishing and helium pre-exposure
  • Sublimation of advanced tungsten alloys under DEMO relevant accidental conditions
    F. Klein [2019]
  • Plasma-surface interaction experimental device : PSIEC and its first plasma exposure experiments on bulk tungsten and coatings
    Y. Xu [2021]
  • Physics basis and design of the ITER plasma-facing components
    R. A. Pitts [2011]
  • Overview of the present progress and activities on the CFETR
    Y. X. Wan [2017]
  • Microstructural evolution induced by low energy hydrogen ion irradiation in tungsten
    R. Sakamoto [1995]
  • Ion radiation albedo effect : influence of surface roughness on ion implantation and sputtering of materials
    Y. G. Li [2017]
  • Investigation of the interaction of He and D in FeBSi alloy
    Q. Xu [2013]
  • Investigation of microstructure and microhardness of pure W and W-2Y2O3 materials before and after ionirradiation
  • Investigation of microstructure and irradiation behavior of W-Nb/Ti composites prepared by spark plasma sintering
    J. B. Chen [2016]
  • Impact of low energy helium irradiation on plasma facing metals
    N. Yoshida [2005]
  • Hydrogen isotope retention in plasma-facing materials : review of recent experimental results
  • High heat flux components-Readiness to proceed from near term fusion systems to power plants
  • Formation mechanism of bubbles and holes on tungsten surface with low-energy and high-flux helium plasma irradiation in NAGDIS-II
  • First-principles calculations on interface stability and migration of H and He in W-ZrC interfaces
    X. Zhang [2020]
  • Enhanced mechanical properties and interface structure characterization of W-La2O3 alloy designed by an innovative combustion-based approach
    Pengqi Chen [2021]
  • Effects of zirconium element on the microstructure and deuterium retention of W-Zr/Sc2O3 composites
    H. Y. Chen [2016]
  • Effects of thickness reduction on recrystallization process of warm-rolled pure tungsten plates at 1350 C
    K. Wang [2017]
  • Effects of fusion relevant transient energetic radiation, plasma and thermal load on PLANSEE double forged tungsten samples in a low-energy plasma focus device
    S. Javadi [2018]
  • Effects of dislocations on thermal helium desorption from nickel and iron
    X. Z. Cao [2011]
  • Effect of tungsten crystallographic orientation on He-ion-induced surface morphology changes
  • Effect of crystal orientation on low flux helium and hydrogen ion irradiation in polycrystalline tungsten
    F. S. Liu [2014]
  • Development of re-crystallized W-1. 1%TiC with enhanced room-temperature ductility and radiation performance
  • Deuterium irradiation resistance and relevant mechanism in W-ZrC/Sc2O3 composites prepared by spark plasma sintering
    G. Yao [2020]
  • Detection of deuterium trapping sites in tungsten by thermal desorption spectroscopy and positron annihilation spectroscopy
    K. Sato [2016]
  • D2 retention behavior and microstructural evolution of W-2wt. %Y2O3 alloy during He-ion irradiation at high temperature
    Q. Xu [2020]
  • Crystallographic orientation effect on the polishing behavior of LiTaO3 single crystal and its correlation with strain rate sensitivity
    Wei Hang [2022]
  • Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten
  • Blister formation on rough and technical tungsten surfaces exposed to deuterium plasma
    A. Manhard [2017]
  • An overview of oxidation-resistant tungsten alloys for nuclear fusion
    D. G. Liu [2018]
  • A review of modelling and simulation of hydrogen behaviour in tungsten at different scales
    G. H. Lu [2014]