In situ neutron diffraction analysis of microstructural evolution-dependent stress response in austenitic stainless steel under cyclic plastic deformation

Kumagai, Masayoshi*; Kuroda, Masatoshi*; Matsuno, Takashi*; Harjo, S.; Akita, Koichi*

Materials & Design, 221, p.110965_1 - 110965_8, 2022/09

https://doi.org/10.1016/j.matdes.2022.110965

A Statistical approach for modeling the effect of hot press conditions on the mechanical strength properties of HTGR fuel elements

Aihara, Jun; Kuroda, Masatoshi*; Tachibana, Yukio

Proceedings of 28th International Conference on Nuclear Engineering (ICONE 28) (Internet), 9 Pages, 2021/08

https://doi.org/10.1115/ICONE28-64507

To maintain the structural integrity of fuel elements for a high-temperature gas-cooled reactor (HTGR) under disaster conditions, strong and oxidation-resistant fuel elements should be further developed. The HTGR fuel elements employ a hot-pressed silicon carbide (SiC)/carbon (C) mixed matrix to improve the oxidative resistance. Hot-press conditions such as pressure, temperature, and duration would be one of the factors that affect the strength of the HTGR fuel elements. To identify the optimal hot-press conditions for preparing the high-strength fuel elements, modelling their effects on the mechanical-strength properties of the HTGR fuel elements should be evaluated quantitatively. In this study, the response surface model, which represents the relationship between the hot-press conditions and the mechanical-strength properties, has been constructed by introducing statistical design-of-experiment approaches.

Detection of fatigue damage in stainless steel by EBSD analysis; Applicability of EBSD pattern quality

Kuroda, Masatoshi*; Kamaya, Masayuki*; Yamada, Teruaki*; Akita, Koichi

Nihon Kikai Gakkai Rombunshu (Internet), 83(852), p.17-00072_1 - 17-00072_7, 2017/07

https://doi.org/10.1299/transjsme.17-00072

In order to assess the fatigue damage of austenitic stainless steels by electron backscatter diffraction (EBSD) method more simply and easily, it should be more preferable to use a commercially available general-purpose EBSD analysis software rather than to employ an in-house developed EBSD analysis programme. In the present study, EBSD measurement was performed for Type 316 austenitic stainless steels subjected to cyclic loading, and the applicability of the EBSD parameter relevant to the pattern quality, which could be obtained by the commercial software, to the fatigue damage assessment was discussed by comparing the other EBSD parameter of the averaged local misorientation (Mave), which could be calculated by the in-house developed programme. As a result, the EBSD parameter relevant to the pattern quality, which signified the full width at half maximum (FWHM) of the histogram distribution of the image quality (IQ), was saturated at the beginning stage of the fatigue cycles, while Mave was increased monotonically with the cycles. This suggested that the FWHM of IQ could be useful to detect the initial stage of the fatigue damage, while Mave was suitable for the quantitative evaluation of the fatigue damage. XRD measurement was also carried out for the same samples employed in the EBSD measurement, and the XRD data was compared with the EBSD data to discuss the crystallographic mechanism of the change in the FWHM of IQ. As a result, it was found that the FWHM of the (111) XRD peak correlated well with the FWHM of IQ. Because the (111) plane in fcc metal such as austenitic stainless steel was most preferable for slip system, this implied that the change in the distribution of the pattern quality generated by the fatigue loading could be due to the slip deformation.

Evaluation of fracture toughness of fine-grained isotropic graphites for HTGR

Yamada, Teruaki*; Matsushima, Yuki*; Kuroda, Masatoshi*; Sumita, Junya; Shibata, Taiju; Fujita, Ichiro*; Sawa, Kazuhiro

Nuclear Engineering and Design, 271, p.323 - 326, 2014/05

https://doi.org/10.1016/j.nucengdes.2013.11.055

In order to investigate the effects of the experimental methodology and the notch angle on the fracture toughness of the fine-grained isotropic nuclear graphites IG-110 and IG-430, the three-point-bending test, which has been recently proposed as the methodology to evaluate the fracture toughness of graphite for high temperature gas-cooled reactors (HTGRs), was performed using two types of the specimens with different notch angles. The results obtained in this study could be summarized as follows: (1) The values of the fracture toughness of IG-110 and IG-430 measured in this study were 0.890 MPa m and 1.031 MPa m, respectively. It was also found that the value of the fracture toughness of IG-110 was nearly equal to or smaller than the values obtained by the other method reported previously. (2) The values of the fracture toughness of the fine-grained isotropic graphites were not affected between the notch angles introduced by the incisive razor blade. (3) The ratio of the tensile strengths of IG-110 and IG-430 was estimated from Griffith Theory using the experimental data obtained in this study. The estimated strength ratio was in good agreement with the strength ratio obtained from the supplier's data.

Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics

Kuroda, Masatoshi*; Yamanaka, Shinsuke*; Nagase, Fumihisa; Uetsuka, Hiroshi

Nuclear Engineering and Design, 203(2-3), p.185 - 194, 2001/01

https://doi.org/10.1016/S0029-5493(00)00323-X

no abstracts in English

Development of high-strength oxidation-resistant fuel components for high-temperature gas-cooled reactor; Evaluation of mechanical strength properties of fuel compact

Tojo, Takuya*; Yamamoto, Takenori*; Kuroda, Masatoshi*; Aihara, Jun; Tachibana, Yukio

no journal, , 

Fuel compact of high-temperature gas-cooled reactor (HTGR) with inherent safety employs fuel component which was molded from graphite. Development of oxidation-resistant fuel component has been advancing at present, which is fuel component having oxidation resistance formed by SiC. In this study, mechanical properties were obtained on oxidation-resistant fuel components prepared under various molding parameters. Young's modulus was measured by ultrasonic pulse velocity test, and compressive strength was measured by compression test. High correlation was not observed between Young's modulus and hot pressing conditions of temperature and time. There was no correlation between compressive strength and hot pressing time in range of hot pressing temperature of 1573-1873 K and time of 40-120 min, but high negative correlation was observed within range of hot pressing temperatures. Therefore, it was predicted that compressive strength was increased by decreasing hot pressing temperature.

Research on advanced fuel element for upgrading safety of high temperature gas-cooled reactors, 1; Outlines

Tachibana, Yukio; Ohira, Koichi*; Kuroda, Masatoshi*

no journal, , 

For the purpose of upgrading safety of High Temperature Gas-cooled Reactor (HTGR), research on advanced fuel element was conducted with cooperation of Nuclear Fuel Industries and Kumamoto University. The advanced fuel element contains SiC as the matrix material and oxidation resistance is highly improved so that shape and integrity of the fuel element should be maintained even when large unexpected amount of air enters into the core in the air ingress (pipe rupture) accident which is a typical event for the HTGR. This presentation shows outlines of the contracted research from FY2014 to 2016.

Prediction modeling of the surface characteristics of shot peened stainless steel

Kuroda, Masatoshi*; Akita, Koichi; Kobayashi, Yuji*; Tsuji, Toshiya*; Shimasaki, Tomonori*

no journal, , 

no abstracts in English

Effect of notch-tip geometry on the fracture toughness of fine-grained isotropic graphite

Matsushima, Yuki*; Yamada, Teruaki*; Kuroda, Masatoshi*; Sumita, Junya; Shibata, Taiju; Sawa, Kazuhiro

no journal, , 

In order to investigate the effect of notch-tip geometry on the fracture toughness of fine-grained isotropic graphite ETU-10, three-point-bending fracture toughness tests have been performed by using two types of single-edge notched beam specimens with different notch angles of approximately 15 and 30. The values of the fracture toughness were calculated based on linear elastic fracture mechanics by using the maximum force which could be obtained by the load-displacement curve. As a result, the values of the fracture toughness of the specimens with the notch angles of approximately 15 and 30 were 0.933 MPa mand 0.926 MPa m, respectively. This suggested that the values of the fracture toughness were not affected between the notch angles. Further work has been ongoing to discuss the effect of the notch-tip geometry such as angle and root radius of notch in terms of finite element analysis.

Fracture mechanism of fine- and coarse-grain graphite

Sumita, Junya; Shibata, Taiju; Tachibana, Yukio; Kuroda, Masatoshi*

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. The Very High Temperature Reactor (VHTR) is one of the most promising candidates as the Generation-IV nuclear reactor systems. During operation of the HTGR, the graphite structure is subjected to various loadings such as external forces and internal stresses resulted from neutron irradiation-induced dimensional and material property changes and a thermal gradient. In order to acquire the fundamental data to evaluate the integrity of the graphite structure of HTGR by fracture mechanics, it is important to investigate the fracture toughness and strain energy release rate of graphite. In this study, the fracture toughness of fine-grain and coarse-grain graphite was measured and calculated the strain energy release rate of them. Moreover, the crack propagation in these graphite and coarse-grain graphite were observed by microscope and the difference between them was discussed from the viewpoint of the grain size.