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Saijo, Tomoaki; Shimazaki, Yosuke; Ishihara, Masahiro
JAEA-Technology 2025-010, 126 Pages, 2025/12
JAEA-Technology-2025-010.pdf:12.52MB
During the operation of the High Temperature Engineering Test Reactor (HTTR), thermal stress is generated in the graphite components. In addition, graphite exhibits dimensional shrinkage and creep deformation under neutron irradiation. As a result, residual stress remains in the graphite components during reactor shutdown. Therefore, in the design of the HTTR core graphite structures, stress analyses of the graphite components have previously been performed using the finite element analysis code VIENUS. In the HTTR, the graphite components are exposed to a wide range of temperature, from approximately 400
C to 1200C, depending on their location. Consequently, irradiation-induced behaviors such as material property changes and irradiation shrinkage vary among the graphite components. On the other hand, since VIENUS code evaluates stress based on thermal fluid and heat conduction analysis results, it is not suitable for parametric studies. In this study, the influence of irradiation behavior on the stress behavior of graphite components in the wide temperature range (400C to 1200C) was analyzed using simplified viscoelastic evaluation model, consisting of two beam elements, to conduct efficient parametric studies. Operational stress exhibits two distinct patterns depending on whether the irradiation temperature is below or above 800C, due to irradiation shrinkage. Residual stress approaches the thermal stress, preventing excessive increase even when irradiation shrinkage is large. Moreover good agreement in stress behavior trends was observed between the stress analysis results by the simplified viscoelastic evaluation model and VIENUS code. These results indicate that the simplified viscoelastic evaluation model is beneficial in simulating stress behavior.
Katsuyama, Jinya; Yamaguchi, Yoshihito; Li, Y.
Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 6 Pages, 2018/07
It has become more important to develop methods for evaluating failure behavior of the nuclear components under severe conditions. We are researching on prediction methods of creep deformation and failure behavior of the nuclear components under elevated temperature conditions based on finite element analysis. In this study, as a part of a project called COSSAL, we performed failure analysis of a large scale pipe experiment to validate our prediction methods based on a creep damage evaluation method. We conclude that creep constitutive law that consider material damage can provide the highest accurate analysis.
Takeda, Takeshi; Tachibana, Yukio; Nakagawa, Shigeaki
JAERI-Tech 2002-091, 45 Pages, 2002/12
JAERI-Tech-2002-091.pdf:1.77MB
no abstracts in English
Chino, Eiichi; Maruyama, Yu; Maeda, Akio*; Harada, Yuhei*; Nakamura, Hideo; Hidaka, Akihide; Shibazaki, Hiroaki*; Yuchi, Yoko; Kudo, Tamotsu; Hashimoto, Kazuichiro*
Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.107 - 115, 2001/06
no abstracts in English
Chino, Eiichi; Maruyama, Yu; Yuchi, Yoko; Shibazaki, Hiroaki*; Nakamura, Hideo; Hidaka, Akihide; Kudo, Tamotsu; Hashimoto, Kazuichiro; Maeda, Akio*
JAERI-Conf 2000-015, p.303 - 308, 2000/11
no abstracts in English
Kunitomi, Kazuhiko; Takeda, Takeshi; Shinozaki, Masayuki; Okubo, Minoru; ; Koikegami, Hajime*
Nihon Genshiryoku Gakkai-Shi, 37(4), p.316 - 326, 1995/00
Times Cited Count：1 Percentile：17.14(Nuclear Science & Technology)no abstracts in English
Kunitomi, Kazuhiko; Shinozaki, Masayuki; Okubo, Minoru; Koikegami, Hajime*;
Proc. of ARS 94 Int. Topical Meeting on Advanced Reactors Safety,Vol. 1, 0, p.188 - 192, 1994/00
no abstracts in English
;
Bull.JSME, 26(221), p.1839 - 1848, 1983/00
no abstracts in English
Watanabe, Nao; Sugawara, Takanori; Nishihara, Kenji; Kaji, Yoshiyuki
no journal, ,
In the design of Accelerator-Driven System (ADS), a beam window is one of the structures used under severe conditions. Since the maximum temperature of the beam window at rated operation will be more than 500C, a creep damage evaluation has been required. Therefore, we have developed a coupled analysis system on ANSYS Workbench to evaluate the creep strain quantitatively. In this system, temperature distribution of the beam window is calculated by the coupled analysis of particle transport and thermal hydraulics analyses, and then is used as an input data for a creep analysis. Calculation result by this analysis system showed that the creep strain after the rated operation was less than 0.1%.
