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Udagawa, Makoto; Katsuyama, Jinya; Nishikawa, Hiroyuki; Onizawa, Kunio
Yosetsu Gakkai Rombunshu (Internet), 28(3), p.261 - 271, 2010/07
Stainless steel is welded as a cladding on the inner surface of a reactor pressure vessel (RPV) made of low alloy steel. In order to assess the structural integrity of an RPV more precisely, the residual stress distribution caused by weld-overlay cladding and post-weld heat treatment (PWHT) is to be evaluated. Although cladding layer is very thin compared to vessel wall, it is not easy to evaluate steep residual stress distribution which occurs in dissimilar metal weld. In this study, cladded specimens were fabricated using different welding methods. Residual stress measurements using both sectioning and DHD methods were then performed to evaluate the residual stress distributions. It was shown that thermal-elastic-plastic-creep analysis results based on finite element method were agreed with experimental results. It was also clarified that the main cause of residual stress due to welding and PWHT was the difference of thermal expansion between weld and base metals.
Ihara, Ryohei*; Katsuyama, Jinya; Onizawa, Kunio; Hashimoto, Tadafumi*; Mikami, Yoshiki*; Mochizuki, Masahito*
Yosetsu Kozo Shimpojiumu 2009 Koen Rombunshu, p.393 - 396, 2009/11
Stress Corrosion Cracking (SCC) has been observed near the weld zone of the primary loop recirculation pipes made of SUS316L. For the evaluation of initiation and propagation of SCC for non-sensitization material, residual stress distribution generated by surface-machining is the most important factors. In this study, residual stress distributions generated are evaluated by varying cutting speed, and crack growth analysis are performed using evaluated residual stress distributions. As a result, crack growth highly depends on residual stress distributions by surface-machining.
Nakajima, Hideo; Takano, Katsutoshi; Tsutsumi, Fumiaki; Kawano, Katsumi; Chida, Yutaka; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Nishimura, Arata*; Nakajima, Hideo; Nakasone, Yuji*; Takahashi, Yukio*; Irie, Hirosada*; Suzuki, Tetsuya*
no journal, ,
no abstracts in English
Shibama, Yusuke; Masaki, Kei; Sakurai, Shinji; Shibanuma, Kiyoshi; Sakasai, Akira
no journal, ,
JT-60SA is a combined JA-EU satellite tokamak program, aiming at the ITER program supports as well as the supplements toward the DEMO, under both broader approach agreement and the JA domestic program. The VV is a vessel to ensure sufficient ultrahigh vacuum space and one turn toroidal resistance for plasma breakdown. A double wall structure is selected to secure the higher rigidity against operational mechanical loads. The space between walls is utilized for the neutron shielding by 323 K boron water circulation, as well as for baking at 473 K by nitrogen gas flow to achieve the vacuum less than 10-5 Pa. The feasibility of the VV manufacture is studied and latest status is presented.
