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Journal Articles

Effect of implanted helium on thermal diffusivities of SiC/SiC composites

Taguchi, Tomitsugu; Igawa, Naoki; Jitsukawa, Shiro; Shimura, Kenichiro

Nuclear Instruments and Methods in Physics Research B, 242(1-2), p.469 - 472, 2006/01

 Times Cited Count:3 Percentile:28.02(Instruments & Instrumentation)

SiC/SiC composites are one of the candidate materials for first wall in a fusion reactor because of their high strength at high temperature and low residual radioactivity after irradiation. In the fusion reactor, these materials are required to have high thermal diffusivity for heat exchange and reducing the thermal shock. Under fusion conditions, helium (He) and hydrogen (H) are produced in SiC. In this study, the effect of He ions implantation on the thermal diffusivities of SiC and SiC/SiC composite were investigated. In the results, the thermal diffusivities of SiC and SiC/SiC composites decreased after He ions implantation. However, the thermal diffusivities of SiC and SiC/SiC composites hardly reduced in the operation temperature of fusion reactor. The thermal diffusivities of He implanted specimens were partly recovered by annealing. The defect concentration induced by He implantation, X$$_{irradiation}$$, in SiC/SiC composites was estimated. The X$$_{irradiation}$$ rapidly decreased around 500 $$^{circ}$$C. The reason is that the He release from SiC starts at 500 $$^{circ}$$C.

JAEA Reports

An Irradiation test of heat-resistant ceramic composite materials, 2; Interim report on post-irradiation examinations of the second and third preliminary test, 98M-41A, 99M-30A

Baba, Shinichi; Nemoto, Makoto*; Sozawa, Shizuo; Yamaji, Masatoshi*; Ishihara, Masahiro; Sawa, Kazuhiro

JAERI-Tech 2005-055, 157 Pages, 2005/09

JAERI-Tech-2005-055.pdf:19.06MB

The Japan Atomic Energy Research Institute (JAERI) has been carrying out the research on radiation damage mechanism of heat-resistant ceramics composite materials, as one of the subjects of the innovative basic research on high temperature engineering using the High Temperature Engineering Test Reactor (HTTR). A series of preliminary irradiation tests is being made using the Japan Materials Testing Reactor (JMTR). The present report describes results of post-irradiation examinations so far on specimens irradiated in the second and third capsule, designated 98M-41A and 99M-30A, to fast neutron fluences of 1.0$$times$$10$$^{25}$$m$$^{-2}$$(E$$>$$1MeV) at temperatures of 973K-1173K and 1273K-1473K. The PIE were conducted as the fundamental statistics index of the diametral dimensions for irradiated specimen, irradiation induced dimensional change rate and thermal expansion rate.

Journal Articles

Synergistic effects of implanted helium and hydrogen and the effect of irradiation temperature on the microstructure of SiC/SiC composites

Taguchi, Tomitsugu; Igawa, Naoki; Miwa, Shuhei*; Wakai, Eiichi; Jitsukawa, Shiro; Snead, L. L.*; Hasegawa, Akira*

Journal of Nuclear Materials, 335(3), p.508 - 514, 2004/12

 Times Cited Count:38 Percentile:89.75(Materials Science, Multidisciplinary)

The microstructure of near-stoichiometric fiber SiC/SiC composites implanted with He and H ions was studied at implantation temperatures of 1000 and 1300 $$^{circ}$$C. The average size of He bubbles in the CVI SiC matrix decreases with increasing concentration of implanted H ions. Moreover, the number density of He bubbles increases with increasing irradiation temperature and amount of implanted H. At the irradiation temperature of 1000 $$^{circ}$$C, He bubbles were mainly formed at grain boundary within the matrix. On the other hand, He bubbles were formed both at grain boundaries and within grains at the irradiation temperature of 1300 $$^{circ}$$C. The average size of He bubbles at grain boundaries was much larger than within the grain. The average size of He bubbles in the fiber was smaller than that in the matrix in all cases.

Journal Articles

Thermal diffusivity/conductivity of Tyranno SA fiber- and Hi-Nicalon type S fiber-reinforced 3-D SiC/SiC composites

Yamada, Reiji; Igawa, Naoki; Taguchi, Tomitsugu

Journal of Nuclear Materials, 329-333(Part1), p.497 - 501, 2004/08

 Times Cited Count:32 Percentile:86.83(Materials Science, Multidisciplinary)

SiC fiber reinforced SiC composites (SiC/SiC) have a potential for a structural material for a blanket wall of advanced fusion reactors. To reduce thermal stresses in the wall under heavy thermal loads SiC/SiC composites are expected to have high thermal conductivity as possible. Advanced SiC fibers recently developed, such as Tyranno SA and Hi-Nicalon Type S have been employed for weaving 3D textures as well as those 2D unwoven fabrics. The CVI and PIP/CVI fabrication methods were used. The thermal conductivity at RT was 40-50 W/mK and 35-40 W/mK for Tyranno CVI and PIP/CVI composites, respectively, whereas about 25 and about 17 W/mK at 1000 $$^{circ}$$C. 2D unwoven CVI composites had less than 12 W/mK for RT-1000 $$^{circ}$$C. For Hi-Nicalon Type S, 3D CVI composites had about 35 and about 20 for RT and 1000 $$^{circ}$$C, respectively. The reason of these high thermal conductivities was ascribed to higher density as well as better SiC crystallinity. The fiber configuration effects on the thermal conductivity of SiC/SiC composites were dominant in the low temperature region.

JAEA Reports

Integrity of the first wall in fusion reactors

Kurihara, Ryoichi

JAERI-Tech 2004-052, 39 Pages, 2004/07

JAERI-Tech-2004-052.pdf:2.1MB

The problems in the thermal structural design of the plasma facing component such as the blanket first wall and the divertor plate which receives very high heat flux were examined in the design of the fusion power reactors. Compact high fusion power reactor must give high heat flux and high-speed neutron flux from the plasma to the first wall and the divertor plate. In this environmental situation, the micro cracks should be generated in material of the first wall. Structural integrity of the first wall would be very low during the operation of the reactor, if those micro-cracks grow in a crack having significant size by the fatigue or the creep. The crack penetration in the first wall can be a factor which threatens the safety of the fusion power reactor. This paper summarizes the problems on the structural integrity in the first wall made of the SiC/SiC composite material or the ferritic steel.

Journal Articles

Fusion power reactor designs adopting SiC/SiC composite as the structural material

Nishio, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 80(1), p.14 - 17, 2004/01

SiC/SiC composite is a promising structural material candidate for fusion power cores and has been considered internationally in several power plant studies. It offers safety advantages arising from its low induced radioactivity and afterheat, and the possibility of high efficiency of energy conversion through high temperature operation. The latest SiC/SiC-based power core design studies are summarized, and the key SiC/SiC parameters affecting the performance of power core components are highlighted.

JAEA Reports

Report of the 2nd Joint Research Committee for Fusion Reactor and Materials; July 12, 2002, Tokyo, Japan

Research Committee for Fusion Reactor; Research Committee for Fusion Materials

JAERI-Review 2003-015, 123 Pages, 2003/05

JAERI-Review-2003-015.pdf:24.89MB

no abstracts in English

Journal Articles

Optimizing the fabrication process for superior mechanical properties in the FCVI SiC matrix/stoichiometric SiC fiber composite system

Igawa, Naoki; Taguchi, Tomitsugu; Snead, L. L.*; Kato, Yudai*; Jitsukawa, Shiro; Koyama, Akira*; McLaughlin, J. C.*

Journal of Nuclear Materials, 307-311(Part2), p.1205 - 1209, 2002/12

 Times Cited Count:17 Percentile:70.93(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Highly thermal conductive sintered SiC fiber-reinforced 3D SiC/SiC composites; Experiments and finite-element analysis of the thermal diffusivity/conductivity

Yamada, Reiji; Igawa, Naoki; Taguchi, Tomitsugu; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1215 - 1220, 2002/12

 Times Cited Count:25 Percentile:81.11(Materials Science, Multidisciplinary)

SiC fiber-reinforced SiC composites (SiC/SiC) are considered an advanced structural material for blanket modules of a fusion reactor, which requires high thermal conductivity in order to keep thermal stresses in the material lower than the allowable design stress. The sintered SiC fiber recently developed has obtained high thermal conductivity, so it is highly expected that sintered SiC fiber-reinforced SiC/SiC composites would also show high thermal conductivity. In this study several types of 3D SiC/SiC composites were fabricated by either CVI or PIP method. The results of the thermal conductivity measurements show that the maximum thermal conductivity at room temperature was about 60 W/mK for CVI composites or 25W/mK for PIP ones. These values are considerably higher than those of non-sintered SiC fiber reinforced SiC/SiC composites, which indicates a possibility that the developed materials would be promising. The FEM thremal analysis shows the good agreement between the caluculated and experimental results.

Journal Articles

Effect of simultaneous ion irradiation on microstructural change of SiC/SiC composites at high temperature

Taguchi, Tomitsugu; Wakai, Eiichi; Igawa, Naoki; Nogami, Shuhei*; Snead, L. L.*; Hasegawa, Akira*; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1135 - 1140, 2002/12

 Times Cited Count:19 Percentile:74.28(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Report of Joint Research Committee for Fusion Reactor and Materials; July 16, 2001, Tokyo, Japan

Research Committee for Fusion Reactor; Research Committee for Fusion Materials

JAERI-Review 2002-008, 79 Pages, 2002/03

JAERI-Review-2002-008.pdf:9.92MB

Joint research committee for fusion reactor and materials was held in Tokyo on July 16, 2001. In the committee, a review of the development programs and the present status on the blanket technology, materials and IFMIF(International Fusion Materials Irradiation Facility) in JAERI and Japanese Universities was reported, and the direction of these R&D was discussed. Moreover, the progress of the collaboration between JAERI and Japanese Universities was discussed. This report consists of the summaries of the presentations and the viewgraphs which were used at the committee.

Journal Articles

Optimizing the fabrication process for excellent mechanical properties in stoichiometric SiC fiber/FCVI SiC matrix composites

Taguchi, Tomitsugu; Igawa, Naoki; Jitsukawa, Shiro; Nozawa, Takashi*; Kato, Yudai*; Koyama, Akira*; Snead, L. L.*; McLaughlin, J. C.*

Advanced SiC/SiC Ceramic Composites: Developments and Applications in Energy Systems; Ceramic Transactions Vol. 144, p.69 - 76, 2002/00

Process optimization for Forced-thermal gradient Chemical Vapor Infiltration (FCVI) fabrication of 75 mm diameter size SiC composites with advanced SiC fibers; Hi-Nicalon Type S and Tyranno SA, was carried out. The SiC/SiC composites fabricated by FCVI exhibited significant reduction in porosity (15.1%) and more uniform pore distribution by decreasing the MTS and H$$_{2}$$ gases flow rates in the latter part of the FCVI process. The tensile strength of the both composites using Hi-Nicalon Type S or Tyranno SA fibers was slightly increased with increased thickness of carbon interphase in the range of 75-300 nm. In order to perform the comparative testing required to directly compare the thermomechanical property changes following neutron irradiation, larger composites with uniform microstructural property are required. From the results of process optimization for fabrication of 75 mm diameter size FCVI SiC/SiC composites, the definitive purpose in this study is the fabrication of the 300 mm diameter size SiC/SiC composite with the uniform microstructural properties.

Journal Articles

A Finite-element analysis of the thermal diffudivity/conductivity of SiC/SiC composites

Yamada, Reiji; Igawa, Naoki; Taguchi, Tomitsugu

Advanced SiC/SiC Ceramic Composites: Developments and Applications in Energy Systems; Ceramic Transactions Vol. 144, p.289 - 299, 2002/00

A Finite-element method(FEM) was applied for a computer simulation of a laser flash method for measuring thermal diffusivity of SiC/SiC composites. To understand the effect of individual fiber and matrix thermal conductivities as well as fiber volume on the overall composite's thermal diffusivity, the cases of high and low values for the fiber and matrix thermal conductivities were calculated as a function of fiber volume fraction at specimen temperatures of 200 and 900$$^{circ}C$$. The results of calculations showed that if low thermal conductive SiC fibers were used, the increase of fiber volume worsened the composite thermal diffusivity with highly conductive matrix, whereas when using highly conductive SiC fiber, the effect of increasing fiber volume was positive for increasing the composite diffusivity with low matrix thermal conductivity. The specimen temperatures altered the values of the composite thermal diffusivity but the qualitative tendencies above mentioned were maintained.

Journal Articles

Fracture mechanics evaluation of a crack generated in SiC/SiC composite first wall

Kurihara, Ryoichi; Ueda, Shuzo; Nishio, Satoshi; Seki, Yasushi

Fusion Engineering and Design, 54(3-4), p.465 - 471, 2001/04

 Times Cited Count:10 Percentile:58.60(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Mechanical and thermal properties of dense SiC/SiC composite fabricated by reaction-bonding process

Taguchi, Tomitsugu; Igawa, Naoki; Yamada, Reiji; Futakawa, Masatoshi; Jitsukawa, Shiro

Ceramic Engineering and Science Proceedings (25th Annual Conference on Composites, Advanced Ceramics, Materials, and Structures: A), 22(3), p.533 - 538, 2001/03

no abstracts in English

Journal Articles

Thermal stress analyses in first wall subjected to high heat flux from fusion plasma

Kurihara, Ryoichi; Nishio, Satoshi; Konishi, Satoshi

Thermal Stresses 2001, p.81 - 84, 2001/00

no abstracts in English

Journal Articles

Mechanical and thermal properties of 2-D and 3-D SiC/SiC Composites

Yamada, Reiji; Taguchi, Tomitsugu; Igawa, Naoki

Journal of Nuclear Materials, 283-287(Part.2), p.574 - 578, 2000/12

 Times Cited Count:73 Percentile:96.77(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Physics design of advanced steady-state tokamak reactor A-SSTR 2

Nishio, Satoshi; Ushigusa, Kenkichi; Ueda, Shuzo; Polevoi, A.*; Kurita, Genichi; Tobita, Kenji; Kurihara, Ryoichi; Hu, G.; Okada, Hidetoshi*; Murakami, Yoshiki*; et al.

JAERI-Research 2000-029, 105 Pages, 2000/10

JAERI-Research-2000-029.pdf:4.19MB

no abstracts in English

Journal Articles

Mg-Si-Al-O coatings on Hi-Nicalon SiC fiber by Alkoxide method

Igawa, Naoki; Taguchi, Tomitsugu; Yamada, Reiji; Jitsukawa, Shiro

Ceramic Engineering and Science Proceedings (24th Annual Conference on Composites, Advanced Ceramics, Materials, and Structures: B), 21(4), p.237 - 242, 2000/09

no abstracts in English

Journal Articles

Fracture behavior of high densified SiC/SiC composites fabricated by reaction bonding; Effect of SiC coating as interface layer

Taguchi, Tomitsugu; Igawa, Naoki; Yamada, Reiji; Futakawa, Masatoshi; Jitsukawa, Shiro

Proceedings of 24th Annual Conference on Composites, Advanced Ceramics, Materials, and Structures A, 21(3), p.453 - 458, 2000/00

no abstracts in English

26 (Records 1-20 displayed on this page)