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Garcia Rodriguez, D.; Sakakibara, Yasuhide*
Proceedings of 2014 ASME Pressure Vessels and Piping Conference (PVP 2014) (DVD-ROM), 9 Pages, 2014/07
The behavior of high temperature (400
C) low-cycle fatigue crack propagation during in-plane bending of an elbow from Monju LMFBR is presented in three stages. 1st, experimental measurements made in a real-size laboratory specimen are presented. This test was carried out under displacement-controlled conditions, with artificial defects introduced in the crown parts, where the maximum stress arises. 2nd, the experimental setup is simulated making use of FEA, in order to obtain the actual stress distribution through the loaded elbow. Finally, based on the FEA data, deterministic fatigue crack propagation based on the J-integral criterion is compared with the experimental data.
Garcia Rodriguez, D.; Matsubara, Shinichiro
Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 9 Pages, 2014/07
Structural reliability of the circumferentially cracked core support mount of Monju FBR is analyzed using FEA. The 3D shell model employed was derived after detailed evaluation of the core support mount behavior with a specific 3D solid model. 1st, elastoplastic static analysis shows that, under nominal operating conditions, the overall structure would be able to survive a total loss of the core support mount. 2nd, using the double elastic slope method it was inferred that earthquake loading integrity could be warranted up to a crack representing over 50% of the total circumference.
Garcia Rodriguez, D.
Hozengaku, 12(4), p.45 - 47, 2014/01
In this short letter to appear in the Japanese Society of Maintenology's next issue, I present my living and working experience in Japan during the past 4 years. I came to live here for the first time in 2005, and stayed for one year as a fellow of the EU-JP Center for Industrial Cooperation Vulcanus Program, while carrying an 8 months internship at Hitachi GE Nuclear Energy. Then, after a 4 year break to obtain my PhD at the French Atomic Commission, I enrolled in JAEA as a permanent researcher in 2010.
Garcia Rodriguez, D.; Mihalache, O.; Ueda, Masashi
Proceedings of 16th International Symposium on Applied Electromagnetics and Mechanics (ISEM 2013), p.219 - 220, 2013/07
Shimomura, Kenta; Garcia Rodriguez, D.*
no journal, ,
There is a longstanding interest to improve the in-service inspection (ISI) of nuclear power plants in general, and sodium fast reactors (SFR) in particular. With the goal of improving both safety and economic performance, a risk-informed approach to in-service inspection (RI-ISI) has therefore been earmarked for future commercial-scale SFR. A reliable RI-ISI, however, can only be established based on a rich operational experience record. For long, JAEA has compiled information about SFR troubles, but up to now such effort had been limited to specific types of troubles or components, while lacking the reliability and completeness required for the RI-ISI approach. In this paper we introduce recent work aiming to develop a comprehensive SFR trouble database based on original information sources, which both expands and improves any previously available documentation.
Mihalache, O.; Garcia Rodriguez, D.*; Yamamoto, Toshihiro*; Cheng, W.*
no journal, ,
