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Uchibori, Akihiro; Yanagisawa, Hideki*; Takata, Takashi; Ohshima, Hiroyuki
Nihon Kikai Gakkai Rombunshu (Internet), 86(883), p.19-00353_1 - 19-00353_6, 2020/03
Evaluation of occurrence possibility of tube failure propagation under sodium-water reaction accident is an important issue. In this study, a numerical analysis method to predict occurrence of failure propagation by overheating rupture was constructed to expand application range of an existing computer code. Applicability of the method was constructed through the numerical analysis of the experiment on water vapor discharging in liquid sodium.
Yamaguchi, Yoshihito; Katsuyama, Jinya; Li, Y.
Yosetsu Kozo Shimpojiumu 2017 Koen Rombunshu, p.21 - 27, 2017/12
no abstracts in English
Uchibori, Akihiro; Yanagisawa, Hideki*; Takata, Takashi; Kurihara, Akikazu; Hamada, Hirotsugu; Ohshima, Hiroyuki
JAEA-Research 2017-007, 61 Pages, 2017/07
JAEA-Research-2017-007.pdf:4.3MB
For safety assessment of a steam generator of sodium-cooled fast reactors, it is necessary to evaluate the possibility of occurring tube failure propagation and of water leak rate under sodium-water reaction accident. In the previous studies, a computer code called LEAP-II calculating a wastage-type failure propagation and the water leak rate during long-time event progress was developed. In this study, a numerical method to evaluate the possibility of occurring overheating rupture was introduced into the LEAP-II code to expand application range of this code. The completed code is called LEAP-III. The test analysis on a tube bundle configuration demonstrated that the overheating rupture model could provide conservative prediction.
Umeda, Ryota; Kurihara, Akikazu; Shimoyama, Kazuhito
JAEA-Technology 2016-030, 50 Pages, 2016/12
JAEA-Technology-2016-030.pdf:5.22MB
In case of tube failure of a steam generator in sodium-cooled fast reactors, the reaction jet with high temperature and high velocity under highly alkaline environment is formed by cited exothermic reaction (sodium-water reaction). When the high temperature reaction jet covers the adjacent tubes, the material strength of tube decreases in the high temperature condition, and the adjacent tube may be swollen and failed by inner pressure (overheating tube rupture). For evaluation of the overheating tube rupture, tube failure is judged by comparison the hoop stress loaded by inner pressure with stress strength standard defined as creep strength depending on tube temperature. Thus, it is important to confirm the validation of this failure criterion based on the findings obtained in the simulated experiment of overheating tube rupture. In this report, for consideration on the validation of the failure criteria and elucidation on the failure mode and strength characteristics of failure, the authors carried out the rapid heating rupture experiment for the thin single and double-walled 9Cr steel tubes at high temperature up to 1500 K by using TRUST-2 rig in the Japan Atomic Energy Agency.
Miyazaki, Akemi; Kawaguchi, Kenichi*
Nihon Kenchiku Gakkai Kozokei Rombunshu, 597, p.69 - 76, 2005/11
The objective of our research is to examine the wave propagation properties of framed structures. Those structures tend to become larger and higher recently. On the case of those structures it may be possible that the structure is locally damaged before it becomes vibration state by an external force. It is seemed that for such structures then the investigation and estimation of dynamic structural behaviour from the view point of wave propagation become important. For these purposes, we planned and carried out impact hammer experiments on some lattice-type plates. In this paper the experiment results performed on three lattice-type plates and one continuum plate are shown. The results show that wave propagation properties of lattice-type plates depend on wave propagation properties of the members consist of those lattice-type plates. Preliminary experiments for evaluating the effect of the boundary conditions performed in advance of the experiments for lattice-type plate models are also shown.
Hagiwara, Shigeru*; Sakamoto, Yoshiaki*; Takebe, Shinichi; Nakayama, Shinichi
JAERI-Data/Code 2004-004, 167 Pages, 2004/03
JAERI-Data-Code-2004-004.pdf:10.14MB
no abstracts in English
Nuclear Code Evaluation Special Committee of Nuclear Code Research Committee
JAERI-Review 2002-003, 97 Pages, 2002/03
JAERI-Review-2002-003.pdf:8.64MB
no abstracts in English
Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*
Fusion Engineering and Design, 58-59, p.869 - 873, 2001/11
Times Cited Count：2 Percentile：19.6(Nuclear Science & Technology)no abstracts in English
Yamagishi, Hideshi; Soyama, Kazuhiko; Kakuta, Tsunemi; Ochiai, Masaaki; Iwamura, Takamichi; Saishu, Sadanori*; Urakami, Masao*; Masuda, Naohiro*; Yamauchi, Yuki*; Otani, Junichi*; et al.
JAERI-Tech 2001-053, 19 Pages, 2001/08
JAERI-Tech-2001-053.pdf:2.48MB
no abstracts in English
Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Nakahira, Masataka
Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08
Fatigue test of the weldments was performed to investigate their fatigue behavior and the effect of the incomplete penetrations on the fatigue strength. Fatigue crack propagation test of their weld metals was also carried out using CT specimen. By calculating stress intensity factors of the weldments contained the incomplete penetrations and cracks using FEM analysis, the fatigue crack propagation rates of weldments were evaluated and compared those of their weld metals. Fatigue life of the weldments was evaluated based on fracture mechanics to discuss the effect of incomplete penetrations on the fatigue strength. As the results, the incomplete penetration behaved as a crack and most of total fatigue life for the weldment was crack propagation life. The crack propagation rates of weldment were in accordance with those of the weld metals. The fatigue strength of the weldment was considerably lower than that of smoothed specimen. The incomplete penetrations affected greatly the fatigue strength of the weldments even if the depth of incomplete penetrations was small.
Neudatchin, S. V.; Takizuka, Tomonori; Shirai, Hiroshi; Fujita, Takaaki; Isayama, Akihiko; Koide, Yoshihiko; Kamada, Yutaka
Plasma Physics and Controlled Fusion, 43(5), p.661 - 675, 2001/05
Times Cited Count：8 Percentile：27.34(Physics, Fluids & Plasmas)no abstracts in English
Neudatchin, S. V.; Takizuka, Tomonori; Dnestrovskij, Y. N.*; Shirai, Hiroshi; Fujita, Takaaki; Isayama, Akihiko; Kamada, Yutaka; Koide, Yoshihiko
Proceedings of IAEA 18th Fusion Energy Conference (CD-ROM), 5 Pages, 2001/00
no abstracts in English
Suzuki, Kazuhiko*; *
JNC TJ8400 2000-052, 136 Pages, 2000/02
JNC-TJ8400-2000-052.pdf:4.16MB
Though HAZOP is recognized as the useful safety assessment method, it requires a labor-intensive and time-consuming process. So recently computer-aided HAZOP has been proposed. The research report in 1999 (PNC TJ1400 99-003) presented HAZOP system based on the plant component malfunctions basic models. By using this basic model, not only state malfunction of component but also the consequence to external circumstance can be assessed. G2, which is an excellent object-oriented developer tool in GUI (Graphical User Interface), was used as a tool for developing the system. By using the graphical editor in the system, the user can carry out HAZOP easily. The purpose of this research is to improve the ability of the HAZOP system to obtain a more detailed HAZOP results. HAZOP is carried out according to the fault propagation of component level and the one of plant level based on plant component malfunctions basic models. Furthermore, the HAZOP system which can do the cause and effect analysis in detail intended for the component which processes two or more materials is developed. It is possible to carry out HAZOP for various plants by newly adding material information to the knowledgebase. We have applied this system to the Nuclear Reprocessing Facilities to demonstrate the utilities of developing system.
Yamagishi, Hideshi; Suzuki, Katsuo; Kakuta, Tsunemi; ; *; *
JAERI-Research 99-002, 18 Pages, 1999/01
JAERI-Research-99-002.pdf:1.16MB
no abstracts in English
*; *; *; Hatano, Toshihisa
Fusion Technology 1998, 1, p.177 - 180, 1998/00
no abstracts in English
parameterKaji, Yoshiyuki; M.Roedig*; Kikuchi, Kenji
Int. J.Press. Vessels Piping, 75(15), p.1065 - 1074, 1998/00
Times Cited Count：2 Percentile：31.91(Engineering, Multidisciplinary)no abstracts in English
Kaji, Yoshiyuki; Kikuchi, Kenji
Nihon Zairyo Kyodo Gakkai-Shi, 30(2), p.59 - 73, 1996/00
no abstracts in English
Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; Nishio, Gunji
JAERI-Tech 95-024, 339 Pages, 1995/03
no abstracts in English
parameterKaji, Yoshiyuki; Kikuchi, Kenji; *
Engineering Fracture Mechanics, 50(4), p.519 - 528, 1995/00
Times Cited Count：5 Percentile：30.08(Mechanics)no abstracts in English
