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Sumita, Junya; Shibata, Taiju; Fujita, Ichiro*; Kunimoto, Eiji*; Yamaji, Masatoshi*; Eto, Motokuni*; Konishi, Takashi*; Sawa, Kazuhiro
Nuclear Engineering and Design, 271, p.314 - 317, 2014/05
Times Cited Count：11 Percentile：64.59(Nuclear Science & Technology)In this study, in order to develop evaluation method for material properties and to evaluate the irradiation-induced property changes under higher neutron doses for IG-430, the oxidation and densification effects on elastic modulus of IG-430 were investigated. Moreover, the correlation of the microstructure based on the X-ray tomography images and the material properties was discussed. It was shown that the elastic modulus of the densified graphite depends on only the closed pores and it is possible to evaluate the material properties of graphite by using X-ray tomography method. However, it is necessary to take into account of the change in the number and shape of closed pores in the grain to simulate the elastic modulus of the highly oxidized and irradiated materials by the homogenization analysis.
Fujita, Ichiro*; Eto, Motokuni*; Osaki, Hirotaka; Shibata, Taiju; Sumita, Junya; Konishi, Takashi; Yamaji, Masatoshi; Kunimoto, Eiji
JAEA-Research 2013-004, 20 Pages, 2013/07
JAEA-Research-2013-004.pdf:2.4MB
Graphite components in HTGR and VHTR may be oxidized by impurities in coolant helium-gas even at normal operation, as well as by air at air-ingress accident. In this study, by air-oxidation test at 520-900
C, oxidation characteristics of IG-110 and IG-430 graphites, and associated decrease in compressive strength were examined. The following results were obtained. (1) The activation energy of the air-oxidation for IG-430 is 176 kJ/mol being almost same as for IG-110, though the oxidation rate for IG-430 is less than a half of that for IG-110. (2) There are correlations between density change and decrease in compressive strength. Decrease in strength is the largest in case that the oxidation temperature is lower than 600 C where the homogenous oxidation occurs. (3) In the process of oxidation, amorphous binder regions are predominantly oxidized. It suggests that peeling-off of cokes grains is necessary to be considered for oxidation weight loss, as well as gasification.
Sumita, Junya; Shibata, Taiju; Fujita, Ichiro*; Kunimoto, Eiji*; Yamaji, Masatoshi*; Eto, Motokuni*; Konishi, Takashi*; Sawa, Kazuhiro
Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology (HTR 2012) (USB Flash Drive), 6 Pages, 2012/10
In this study, in order to develop evaluation method for material properties and to evaluate the irradiation-induced property changes under higher neutron doses for IG-430, the oxidation and densification effects on elastic modulus of IG-430 were investigated. Moreover, the correlation of the microstructure based on the X-ray tomography images and the material properties was discussed. It was shown that the elastic modulus of the densified graphite depends on only the closed pores and it is possible to evaluate the material properties of graphite by using X-ray tomography method. However, it is necessary to take into account of the change in the number and shape of closed pores in the grain to simulate the elastic modulus of the highly oxidized and irradiated materials by the homogenization analysis.
Sumita, Junya; Shibata, Taiju; Kunimoto, Eiji*; Yamaji, Masatoshi*; Konishi, Takashi*; Sawa, Kazuhiro
IOP Conference Series; Materials Science and Engineering, 18(16), p.162012_1 - 162012_4, 2011/09
Times Cited Count：1 Percentile：52.78(Materials Science, Ceramics)For control rod element of Very High Temperature Reactor, carbon fiber reinforced carbon matrix composite (C/C composite) is one of the major candidate materials for its high strength and thermal stability. The development of a property prediction model of the two-dimensional (2D)-C/C composite is one of the most important subjects for the design methodology for control rod. Since the property of the 2D-C/C composite is strongly dependent on its microstructure, fiber/matrix, it would be possible to evaluate the properties of the 2D-C/C composite from its microstructure. In this study, in order to develop the property prediction model of the 2D-C/C composite base on its microstructure, pore distribution was investigated by using the X-ray computed tomography (X-ray CT) images and developed image based voxcel model. The compressive strength of the 2D-C/C composite was measured and evaluated by the voxcel model. This study shows that the pore distribution in the 2D-C/C composite can be confirmed visually and the volume and shape of the pores can be estimated from X-ray CT images. It is also shown that evaluation of the compressive strength by using the voxel model is useful to simulate the trend of the stress distribution of the 2D-C/C composite. However, it is necessary to characterize the property of the 2D-C/C composite and to set up the appropriate mesh to simulate the absolute stress value precisely.
Sumita, Junya; Shibata, Taiju; Kunimoto, Eiji*; Yamaji, Masatoshi*; Konishi, Takashi*; Sawa, Kazuhiro
Journal of Nuclear Science and Technology, 47(4), p.411 - 420, 2010/04
Times Cited Count：4 Percentile：30.63(Nuclear Science & Technology)Two dimensional carbon fiber reinforced carbon composite (2D-C/C composite) is one of the candidate materials for a reactor internals, e.g. control rod element, of Very High Temperature Reactor (VHTR) because of its high strength at high temperature and thermal stability. From the viewpoint of its application to the reactor internals of VHTR, it is important to investigate the anisotropy effect on its properties for the design and safety analysis of VHTR. Moreover, the property of 2D-C/C composite is strongly related to its microstructure, therefore, it is necessary to observe the internal microstructure to investigate the relationship between the microstructural change and the property change. This study has shown that the X-ray tomography could be applied to observe the microstructural change of thermally 2D-C/C composite. The relationship between the thermal conductivity and the coefficient of thermal expansion (CTE) change and burn-off of thermally oxidized 2D-C/C composite could be expressed by the empirical exponential decay formula in both directions perpendicular and parallel to lamina. It could be explained the direction of hexagonal graphite crystal structure from carbon atoms and microstructural change of 2D-C/C composite.
Baba, Shinichi; Yamaji, Masatoshi*; Matsui, Yoshinori; Ishihara, Masahiro; Sawa, Kazuhiro
JAEA-Technology 2007-012, 142 Pages, 2007/03
JAEA-Technology-2007-012.pdf:20.81MB
The creep test under irradiation with thermal gradient for the cylindrical carbon fiber reinforced carbon composites (c/c composite) are carried out in the Japan Material Testing Reactor (JMTR). This report described 4-items; first item is design/evaluation of the capsule for the irradiation test, second is before irradiation measurements for the residual strain due to manufactured cylindrical c/c composite, and third is also before irradiation measurements of the distance between 2-holes of predrilled in the specimen and last item is examination of analysis for the irradiation creep with thermal gradient by VIENUS Code.
Shibata, Taiju; Sumita, Junya; Baba, Shinichi; Yamaji, Masatoshi*; Ishihara, Masahiro; Iyoku, Tatsuo; Tsuji, Nobumasa*
Key Engineering Materials, 297-300, p.728 - 733, 2005/11
no abstracts in English
Ishihara, Masahiro; Yamaji, Masatoshi*; Baba, Shinichi; Hanawa, Satoshi
Key Engineering Materials, 297-300, p.201 - 206, 2005/11
no abstracts in English
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
10
m
(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.
Baba, Shinichi; Yamaji, Masatoshi*; Shibata, Taiju; Ishihara, Masahiro; Sawa, Kazuhiro
JAERI-Tech 2005-002, 83 Pages, 2005/02
JAERI-Tech-2005-002.pdf:14.02MB
The innovative basic research concerns the association of basic and technology with high temperature irradiation environments. The direction of research involves novel and bold challenges both in nuclear and non-nuclear fields. The innovative basic research on high-temperature engineering is one of the key subjects using the HTTR as well as other research reactors. The aim of this paper is to describe the preliminary irradiated test conditions such as irradiated fluence, irradiated temperature and installed specimen on the capsules, and also to show the specifications and performances of the apparatus for Post/Ante Irradoation Experiment.
Baba, Shinichi; Shibata, Taiju; Yamaji, Masatoshi*; Sumita, Junya; Ishihara, Masahiro; Motohashi, Yoshinobu*; Sawa, Kazuhiro
Nihon Kikai Gakkai Kanto Shibu Ibaraki Koenkai (2004) Koen Rombunshu (No.040-3), p.61 - 62, 2004/09
no abstracts in English
Shibata, Taiju; Baba, Shinichi; Yamaji, Masatoshi*; Sumita, Junya; Ishihara, Masahiro
Nihon Kikai Gakkai M&M 2004 Zairyo Rikigaku Kanfarensu Koen Rombunshu, p.407 - 408, 2004/00
no abstracts in English
Oshima, Takeshi; Morishita, Norio; Kamiya, Tomihiro; Isoya, Junichi*; Baba, Shinichi; Aihara, Jun; Yamaji, Masatoshi*; Ishihara, Masahiro
Proceedings of OECD/NEA 3rd Information Exchange Meeting on Basic Studies in the Field of High Temperature Engineering (OECD/NEA No.5309), p.197 - 202, 2004/00
For the application of SiC to electronic devices, it is necessary to develop the fabrication technique of high quality SiC substrates with uniform carrier concentration. Since phosphorus (P) atoms become shallow donors in SiC, nuclear transmutation doping (NTD) is thought to be a good method for the fabrication of n-type SiC substrates with uniform electron concentration. However, defects are also introduced in SiC by neutron irradiation. Although thermal annealing at high temperatures above 1500C is carried out to remove defects after irradiation, heavy damage in SiC is hard to recover. Therefore, the process for the reduction of defects in SiC irradiated with neutrons is necessary to develop. In this study, neutron irradiation into SiC at elevated temperature was carried out to decrease radiation damage. The electrical properties of the samples are studied using Hall effect measurement. Furthermore, to establish the measurement technique for the estimation of P atoms created in SiC by NTD, P atoms in SiC were investigated using Electron Spin Resonance (ESR).
Sogabe, Toshiaki; Ishihara, Masahiro; Baba, Shinichi; Tachibana, Yukio; Yamaji, Masatoshi*; Iyoku, Tatsuo; Hoshiya, Taiji*
Materials Science Research International, 9(3), p.235 - 241, 2003/09
2D-C/C composite is one of the promising materials as a next-generation core material in gas-cooled reactors. Effect of air-oxidation on the thermal diffusivity up to 1673K of the 2D-C/C composite was investigated. The C/C composite specimens for measurement of thermal diffusivity were oxidized from 1 to 11 percent weight loss in air at 823K. Thermal diffusivity at room temperature declined 10
20 percent for parallel to lamina direction and 59 percent for that of perpendicular within 11 percent weight loss by oxidation. Thermal diffusivity tended to decrease gradually as the increase of oxidation loss in parallel to lamina, however, it decreased in the beginning of oxidation pretty much and not so changed by further oxidation loss in perpendicular to lamina. Change in thermal conductivity under oxidation condition was also estimated.
Sogabe, Toshiaki; Ishihara, Masahiro; Baba, Shinichi; Kojima, Takao; Tachibana, Yukio; Iyoku, Tatsuo; Hoshiya, Taiji; Hiraoka, Toshiharu*; Yamaji, Masatoshi*
JAERI-Research 2002-026, 22 Pages, 2002/11
JAERI-Research-2002-026.pdf:2.41MB
Carbon Fiber Reinforced Carbon-carbon Composites, C/C composites, have been developed and extensively studied their characteristics. C/C composites are considered to be promising materials for the application of a control rod in the next high performance high temperature gas-cooled reactors. In the present paper, details of the development of the candidate C/C composite are described. In the course of the development of the material, especially, feasibility of the production, stableness of the supply and cost are much taken into consideration. As the physical properties of the material, high mechanical strength such as tensile and bending, high fracture strain and fracture toughness and low dimensional change by neutron irradiation have to be met. The developed 2D-C/C composite consists of plain-weave PAN-based carbon fiber cloth and pitch derived matrix. Also, high purification up to the level of nuclear grade was successfully attained in the composite.
Shibata, Taiju; Kunimoto, Eiji; Sumita, Junya; Yamaji, Masatoshi*; Konishi, Takashi*; Sawa, Kazuhiro
no journal, ,
Fine-grained isotropic graphite IG-110 (Toyo Tanso Co.) is used for the core components in the HTTR. It is a proven graphite and a major candidate for in-core components of the VHTR. Japanese graphite code and standard for the HTTR show the criteria of IG-110 for the application to the in-core components. They include IG-110 property data, oxidation effect, irradiation effect and so on. They are established on the basis of IG-110 component test results. It is thought that the code and standard for the IG-110 would be applicable to the VHTR with some adjustments. For this purpose, establishment of the IG-110 design data for the VHTR condition is one of the key subjects. The development of interpolation and extrapolation for the irradiation data would help the design data establishment. The R&D subjects on the IG-110 for the in-core VHTR components will be summarized and presented in this study.
Sumita, Junya; Shibata, Taiju; Fujita, Ichiro; Kunimoto, Eiji; Yamaji, Masatoshi; Eto, Motokuni*; Konishi, Takashi; Sawa, Kazuhiro
no journal, ,
no abstracts in English
Sumita, Junya; Shibata, Taiju; Fujita, Ichiro; Yamaji, Masatoshi; Eto, Motokuni*; Konishi, Takashi; Sawa, Kazuhiro
no journal, ,
no abstracts in English
Sumita, Junya; Osaki, Hiroki*; Kunimoto, Eiji*; Yamaji, Masatoshi*; Konishi, Takashi*
no journal, ,
Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor (HTGR) which is a graphite-moderated and helium gas-cooled reactor. The HTGR is particularly attractive due to capability of producing high temperature helium gas, and its passive and inherent safety features. It is required for core support graphite structure, which support the core, to have oxidation resistance in the case of air ingress accident in order to maintain the core arrangement and cool the core from a viewpoint of ensuring high safety of HTGR. Boron-doped graphite is one of candidate materials for oxidation-resistant graphite. It was reported that B
O
, which was generated by oxidation of B
C, prevented boron-doped graphite from oxidation. To apply boron-doped graphite to core support graphite structure of HTGR, it is necessary to understand oxidation mechanism of boron-doped graphite. This study reports evaluation results of oxidation mechanism of boron-doped graphite on the basis of oxidation test, bending strength test and surface observation.
Kunimoto, Eiji*; Sumita, Junya; Osaki, Takashi*; Osaki, Hiroki*; Yamaji, Masatoshi*; Konishi, Takashi*
no journal, ,
Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor (HTGR) which is a graphite-moderated and helium gas-cooled reactor. The major features of the HTGR are that the HTGR can take out the high-temperature helium gas at the reactor outlet and has inherent safety characteristics. The Very High Temperature Reactor (VHTR) is one of the most promising candidates as the Generation-IV nuclear reactor systems. IG-110 graphite having high strength and resistance to oxidation is used in the HTTR of JAEA and HTR-10 in China. Moreover, IG-110 graphite provides highly consistent quality and long-term stable supply. IG-110 graphite is a major candidate for the in-core graphite components of VHTR. IG-430 graphite having the higher strength and resistance to oxidation than IG-110 is an advanced candidate for the VHTR. However, a new material of IG-430 does not have enough databases for the design of HTGR. Therefore, preparation of the necessary database for the design, mechanical and thermal properties, irradiation effect on them, is underway. In this study, the tensile strength, compressive strength and fatigue strength of IG-430 were statistically evaluated and the applicability of IG-430 as HTGR graphite materials was discussed. Moreover, the Su value of tensile and compressive strength of IG-430 was evaluated and compared to that of IG-110. It was found that IG-430 has excellent properties.
