Development of ultra-fine grained W–(0.25–0.8)wt%TiC and its superior resistance to neutron and 3MeV He-ion irradiations

Kurishita, Hiroaki; Kobayashi, Sengo; Nakai, Kenta; Ogawa, Takayuki; Hasegawa, Akira; Abe, Katsunori; Arakawa, Hideo; Matsuo, Seitaro; Takida, Tomohiro; Takebe, K.; Kawai, Masayoshi; Yoshida, N.

doi:10.1016/j.jnucmat.2008.02.055

Cited by 175 publications

(65 citation statements)

References 29 publications

(48 reference statements)

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“…A promising solution to these problems is to develop nanostructures that can offer much-improved mechanical properties in the recrystallized state. UFG, densified W-(0.25-1.5)%TiC compacts with recrystallized, equiaxed grain sizes of 50-200 nm and fine TiC dispersoids at grain boundaries (GBs) were developed by PM methods utilizing MA and HIPping [26,27]. TiC was selected because of its high melting point (~3400 K) and a self-adjustment capability of the lattice constant by forming a solid solution with W and non-stoichiometric TiCx.…”

Section: Recent Progress In Nanostructured W-tic Materialsmentioning

confidence: 99%

“…TiC was selected because of its high melting point (~3400 K) and a self-adjustment capability of the lattice constant by forming a solid solution with W and non-stoichiometric TiCx. UFG W-0.5TiC compacts exhibit negligibly small hardening by neutron irradiation [27], no blistering nor flaking by 3 MeV He irradiation [28], and superplastic deformation by GB sliding above 1673K [26,[29][30][31].…”

Section: Recent Progress In Nanostructured W-tic Materialsmentioning

confidence: 99%

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Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

Wurster¹,

Baluc²,

Battabyal³

et al. 2013

Journal of Nuclear Materials

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282

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Tungsten materials are candidates for plasma-facing components for the International Thermonuclear Experimental Reactor and the DEMOnstration power plant because of their superior thermophysical properties. Because these materials are not common structural materials like steels, knowledge and strategies to improve the properties are still under development. These strategies discussed here, include new alloying approaches and microstructural stabilization by oxide dispersion strengthened as well as TiC stabilized tungsten based materials. The fracture behavior is improved by using tungsten laminated and tungsten wire reinforced materials. Material development is accompanied by neutron irradiation campaigns. Self-passivation, which is essential in case of loss-of-coolant accidents for plasma facing materials, can be achieved by certain amounts of chromium and titanium. Furthermore, modeling and computer simulation on the influence of alloying elements and heat loading and helium bombardment will be presented.

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Section: Recent Progress In Nanostructured W-tic Materialsmentioning

confidence: 99%

Section: Recent Progress In Nanostructured W-tic Materialsmentioning

confidence: 99%

Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

Wurster¹,

Baluc²,

Battabyal³

et al. 2013

Journal of Nuclear Materials

Self Cite

282

View full text Add to dashboard Cite

show abstract

“…(1) Grains: 23,25,29) TEM (Transmission Electron Microscopy) observations show that the UFGR WTiC exhibits equiaxed grains in the recrystallized state. TiC addition, even with 0.25 mass%, has a significant effect of grain refinement.…”

Section: Microstructuresmentioning

confidence: 99%

Development of Nanostructured Tungsten Based Materials Resistant to Recrystallization and/or Radiation Induced Embrittlement

et al. 2013

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Mitigation of embrittlement caused by recrystallization and radiation is the key issue of tungsten (W) based materials for use in the advanced nuclear system such as fusion reactor applications. In this paper, our nanostructured W materials development performed so far to solve the key issue is reviewed, including new original data. Firstly, the basic concept of mitigation of the embrittlement is shown. The approach to the concept has yielded ultra-fine grained, recrystallized (UFGR) W(0.251.5) mass%TiC compacts containing fine TiC dispersoids (precipitates). The UFGR W(0.251.5)%TiC exhibits favorable as well as unfavorable features from the viewpoints of microstructures and various thermo-mechanical properties including the response to neutron and ion irradiations. Most of the unfavorable features stem from insufficient strengthening of weak random grain boundaries (GBs) in the recrystallized state. The focal point on this study is, therefore, to develop a new microstructural modification method to significantly strengthen the random GBs. The method is designated as GSMM (GB Sliding-based Microstructural Modification) and has lead to the birth of toughened, fine-grained W1.1%TiC in the recrystallized state (TFGR W1.1TiC). The TFGR W1.1TiC exhibits much improved thermo-mechanical properties. The applicability of TFGR W1.1TiC to the divertor in ITER is discussed.

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“…The rolling direction of the samples was perpendicular to the surface, similar to the proposed grade of W to be used in ITER. Re-crystallized pure W (RC-W) and toughness enhanced, fine-grained W-1.1 mass% TiC (TFG W-TiC) 5) were also used for comparison. The primary difference in these samples is their grain sizes; the grain size of SR-W and RC-W is ³100 µm, while that of TFG W-TiC is approximately 1 µm.…”

Section: Methodsmentioning

confidence: 99%

Microstructures and Deuterium-Retention Behavior of Tungsten Exposed to D+(He and/or Be) Mixture Plasmas

et al. 2013

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ITER-relevant mixed species (D, He, Be) plasma exposure experiments on microstructural changes and their impacts on D retention behavior in W are reviewed. It was observed that seeding of He into pure D plasma resulted in a significant reduction of D retention and suppression of surface blistering. TEM observations and ellipsometric measurements revealed that nano-sized high-density He bubbles were formed and percolated in the near surface region. Based on the experimental results, a mechanism to explain the reduced D retention was proposed, i.e., implanted D atoms can easily diffuse back to the surface through the percolating bubbles and escape from the surface during plasma exposure. Additional Be seeding to D+He mixture plasma suppressed this He seeding effect. Thus, it is considered that Be seeding has a more dominant influence than He seeding on microstructures and D retention in plasma-exposed W.

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Development of ultra-fine grained W–(0.25–0.8)wt%TiC and its superior resistance to neutron and 3MeV He-ion irradiations

Cited by 175 publications

References 29 publications

Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

Development of Nanostructured Tungsten Based Materials Resistant to Recrystallization and/or Radiation Induced Embrittlement

Microstructures and Deuterium-Retention Behavior of Tungsten Exposed to D+(He and/or Be) Mixture Plasmas

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