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Journal Articles

Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Suzudo, Tomoaki; Hasegawa, Akira*

Scientific Reports (Internet), 6, p.36738_1 - 36738_6, 2016/11

 Times Cited Count:27 Percentile:64.56(Multidisciplinary Sciences)

Modeling of the evolution of radiation-induced defects is important for finding radiation-resistant materials, which would be greatly appreciated in nuclear applications. We apply the first principles method combined with kinetic Monte Carlo to indicate a mechanism to mitigate the effect of radiation by adding particular solute elements that change the migration dimension of interstitials in W crystals. The resultant mechanism is applicable to any body-centered-cubic (BCC) metals whose SIAs have one-dimensional (1D) motion and is expected to provide a general guideline for computational design of radiation-resistant alloys in the field of nuclear applications.

Journal Articles

Modification of vacuum plasma sprayed tungsten coating on reduced activation ferritic/martensitic steels by friction stir processing

Tanigawa, Hiroyasu; Ozawa, Kazumi; Morisada, Yoshiaki*; Noh, S.*; Fujii, Hidetoshi*

Fusion Engineering and Design, 98-99, p.2080 - 2084, 2015/10

 Times Cited Count:10 Percentile:64.63(Nuclear Science & Technology)

The vacuum plasma spray (VPS) technique has been investigated as the most practical method to form Tungsten (W) layer as a plasma facing material in fusion devices. The issues are the thermal conductivity and the strength of VPS-W, i.e., the thermal conductivity of VPS-W were significantly lower than that of the bulk W, and the hardness of VPS-W is much less than that of the bulk W. These are mainly caused by the porous structure of VPS-W. In order to solve these issues, friction stir processing (FPS) was applied on VPS-W in this study. It was suggested that FSP can contribute to significant improvement both in mechanical and thermal properties of VPS-W coating.

Journal Articles

Intelligible seminar on fusion reactors, 5; Plasma facing high-heat-flux components, Walls to withstand high heat flux from fusion plasmas

Suzuki, Satoshi; Ueda, Yoshio*

Nihon Genshiryoku Gakkai-Shi, 47(4), p.266 - 271, 2005/04

no abstracts in English

Journal Articles

Modeling of hydrogen transport through plasma facing materials by use of cellular automaton

Shimura, Kenichiro*; Yamaguchi, Kenji; Terai, Takayuki*; Yamawaki, Michio*

Journal of Physics and Chemistry of Solids, 66(2-4), p.684 - 689, 2005/02

 Times Cited Count:1 Percentile:7.27(Chemistry, Multidisciplinary)

no abstracts in English

Journal Articles

Fusion materials and hydrogen

Nagasaki, Takanori*; Yamaguchi, Kenji; Konishi, Satoshi*

Nihon Genshiryoku Gakkai-Shi, 46(11), p.770 - 779, 2004/11

no abstracts in English

Journal Articles

Erosion characteristics of neutron-irradiated carbon-based materials under simulated disruption heat loads

Sato, Kazuyoshi; Ishitsuka, Etsuo; Uda, Minoru*; Kawamura, Hiroshi; Suzuki, Satoshi; Taniguchi, Masaki; Ezato, Koichiro; Akiba, Masato

Journal of Nuclear Materials, 283-287(2), p.1157 - 1160, 2000/12

 Times Cited Count:6 Percentile:42.66(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Tritium decontamination from plasma facing materials

Shu, Wataru; Oya, Yasuhisa

Purazuma, Kaku Yugo Gakkai-Shi, 76(10), p.1021 - 1028, 2000/10

no abstracts in English

Journal Articles

Studies on tritium interactions with plasma facing material at the tritium process laboratory of JAERI

Hayashi, Takumi; Ohira, Shigeru; Nakamura, Hirofumi; Tadokoro, Takahiro*; Shu, W.; Sakai, T.*; Isobe, Kanetsugu; Nishi, Masataka

Proceedings of Hydrogen Recycle at Plasma Facing Materials, p.213 - 221, 2000/00

no abstracts in English

Journal Articles

General formula of tritium permeation through plasma facing materials

Shu, W.

Purazuma, Kaku Yugo Gakkai-Shi, 75(4), p.409 - 415, 1999/04

no abstracts in English

Journal Articles

Molecular dynamics evaluation of self-sputtering of beryllium

Ueda, Shuzo; *; *

Journal of Nuclear Materials, 258-263, p.713 - 718, 1998/00

 Times Cited Count:10 Percentile:63.67(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of B$$_{4}$$C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, part 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60

*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; Goto, Yoshitaka*

Nihon Seramikkusu Kyokai Gakujutsu Rombunshi, 105(1228), p.1091 - 1098, 1997/12

 Times Cited Count:1 Percentile:18.67(Materials Science, Ceramics)

no abstracts in English

JAEA Reports

Thermal conductivity of neutron-irradiated uni-directional carbon fiber reinforced carbon material

Saito, Tamotsu; K.Deng*; Nakano, Junichi; Yamada, Reiji

JAERI-Research 97-001, 18 Pages, 1997/01

JAERI-Research-97-001.pdf:0.85MB

no abstracts in English

Journal Articles

Preliminary characterization of interlayer for Be/Cu functionally gradient materials; Thermophysical properties of Be/Cu sintered compacts

Saito, Shigeru; *; *; Kawamura, Hiroshi

Functionally Graded Materials 1996, 0, p.215 - 220, 1996/00

no abstracts in English

Journal Articles

Study of tritium behavior in plasma facing materials

Okuno, Kenji; Ohira, Shigeru; Hayashi, Takumi

Purazuma, Kaku Yugo Gakkai-Shi, 71(5), p.394 - 399, 1995/05

no abstracts in English

Journal Articles

Thermal tests on B$$_{4}$$C-overlaid carbon fibre reinforced composites under disruption heat load conditioned

Nakamura, Kazuyuki; Akiba, Masato; Araki, Masanori; Dairaku, Masayuki; Sato, Kazuyoshi; ; ; Ando, Toshiro; *; Saido, Masahiro; et al.

Fusion Engineering and Design, 30, p.291 - 298, 1995/00

 Times Cited Count:2 Percentile:28.65(Nuclear Science & Technology)

no abstracts in English

Journal Articles

PFC/PSI studies in JT-60U

Saido, Masahiro; Ando, Toshiro

Proc. of Japan-US Workshop P243 on High Heat Flux Components and Plasma Surface Interactions for Next, 0, p.107 - 118, 1995/00

no abstracts in English

Journal Articles

Sputtering characteristics of B$$_{4}$$C-overlaid graphite for keV energy deuterium ion irradiation

Goto, Yoshitaka*; Yamaki, Takahiro*; Ando, Toshiro; Jimbo, Ryutaro*; Ogiwara, Norio; Saido, Masahiro; Teruyama, Kazuhiro*

Journal of Nuclear Materials, 196-198, p.708 - 712, 1992/12

 Times Cited Count:19 Percentile:83.58(Materials Science, Multidisciplinary)

no abstracts in English

Oral presentation

Effect of Re and Os in W under irradiation; Comparison between numerical and experimental results

Suzudo, Tomoaki; Tsuru, Tomohito; Hasegawa, Akira*

no journal, , 

Tungsten is expected to be a promising plasma-facing material for future fusion devices, but radiation-induced precipitation (RIP), which leads the material to hardening, is a concern at their practical use. One of the keys to accurate prediction of the emergence of RIP is stability and migration of solute atoms, rhenium (Re) and osmium (Os), that are produced by nuclear transmutation through irradiation. We conduct a series of numerical simulations using ab initio and an atomic kinetic Monte Carlo method to examine the behaviour of these solute elements. We find that tungsten interstitial atoms displaced by radiation favourably form mixed dumbbell with the solute atoms, and these mixed dumbbells have 3D motion instead of 1D motion of SIAs.

18 (Records 1-18 displayed on this page)
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