Plasma processed tungsten for fusion reactor first-wall material

被引:9
|
作者
Vas, J. V. [1 ]
Pan, J. Q. [2 ]
Wang, N. L. [2 ]
Xu, J. H. [2 ]
Medwal, R. [1 ]
Mishra, M. [1 ]
Pae, J. Y. [1 ,3 ]
Matham, M., V [3 ]
Paul, L. C. K. [1 ]
Rawat, R. S. [1 ]
机构
[1] Nanyang Technol Univ, Natl Inst Educ, Nat Sci & Sci Educ, Singapore 637616, Singapore
[2] Hwa Chong Inst, Singapore 269734, Singapore
[3] Nanyang Technol Univ, Ctr Opt & Laser Engn COLE, Singapore 639798, Singapore
关键词
OPTICAL-EMISSION SPECTROSCOPY; FACING MATERIALS; FOCUS; TEMPERATURE; DENSE; HELIUM; ION; DEPOSITION; SPECTRA; DEVICES;
D O I
10.1007/s10853-021-05917-y
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Tungsten is one of the prime candidates for a first-wall material near the divertor area due to its high temperature strength, high thermal conductivity, low erosion rate and low tritium retention. The erosion resistance of tungsten to the edge plasmas and transient events are carefully investigated in a simulated fusion environment. Here, we use the dense plasma focus (DPF) device operated in a D-2 as a source for pulsed fusion plasma. The tungsten (alpha-W) substrates with a preferential growth direction along (110) plane were used. These pristine-W samples were nanostructurized using a (i) low-temperature continuous nitrogen RF plasma system and (ii) coated with 60 nm tungsten film, using high-temperature argon plasma in a dense plasma focus (DPF) device. The low- temperature plasma treatment created mesh-like porous nanostructure on the surface of pristine-W with change in crystalline orientation to (200), while the DPF-based deposition resulted in a nanocrystal (30-50 nm) decorated surface with enhanced (200) orientation. The crack propagation and bubble formation during DPF D-2 plasma exposure were significantly controlled by the surface modification of tungsten. The mesh-like structure was modified to form loosely bound spherical nanoparticles, while the nanocrystals remained tightly bound and grew in size with D-2 plasma exposure. The better adhesion of the nanocrystals and controlled growth along the (200) direction resulted in least change in hardness measurements for the nanocrystal decorated samples. Thus, nanocrystal decoration of tungsten with a preferential growth direction of (200) can help reduce the fusion-induced damage in first-wall materials.
引用
收藏
页码:10494 / 10509
页数:16
相关论文
共 50 条
  • [1] Plasma processed tungsten for fusion reactor first-wall material
    J. V. Vas
    J. Q. Pan
    N. L. Wang
    J. H. Xu
    R. Medwal
    M. Mishra
    J. Y. Pae
    M. V. Matham
    L. C. K. Paul
    R. S. Rawat
    [J]. Journal of Materials Science, 2021, 56 : 10494 - 10509
  • [2] Phase transformation research of fusion reactor first wall material tungsten
    Wang, Zenghui
    Zhao, Kaixuan
    Chen, Weiming
    Chen, Xiaodi
    Zhang, Longyan
    [J]. APPLIED THERMAL ENGINEERING, 2013, 59 (1-2) : 498 - 503
  • [3] SIMULATION OF FUSION FIRST-WALL ENVIRONMENT IN A FISSION REACTOR.
    Hassanein, A.M.
    Kulcinski, G.L.
    Longhurst, G.R.
    [J]. Nuclear technology/fusion, 1982, 2 (01): : 120 - 132
  • [4] FIRST-WALL PROTECTION CONCEPTS FOR AN ELECTRON-BEAM FUSION REACTOR
    CARLSON, GA
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 20 - 20
  • [5] Atomistic modeling of diffusion coefficient in fusion reactor first wall material tungsten
    Wang, Zenghui
    Zhao, Kaixuan
    Chen, Weiming
    Chen, Xiaodi
    Zhang, Longyan
    [J]. APPLIED THERMAL ENGINEERING, 2014, 73 (01) : 111 - 115
  • [6] FUSION REACTOR FIRST-WALL COOLING FOR VERY HIGH ENERGY FLUXES
    HOFFMAN, MA
    WERNER, RW
    ROOSE, TR
    CARLSON, GA
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 19 (OCT27): : 8 - 8
  • [7] HYDROGEN ISOTOPES TRANSPORT IN FUSION-REACTOR FIRST-WALL MATERIALS
    GERVASINI, G
    REITER, F
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 1379 - 1383
  • [8] Tungsten as first wall material in fusion devices
    Kaufmann, M.
    Neu, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (5-14) : 521 - 527
  • [9] FIRST-WALL EROSION IN FUSION DEVICES
    GARCIAROSALES, C
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 97 - 100
  • [10] DIFFUSION, TRAPPING AND RELEASE PROCESS IN THE FIRST-WALL OF THERMONUCLEAR FUSION-REACTOR
    ABRAMOV, E
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 1384 - 1389