Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Kazuyoshi Yonekura"'
Autor:
Hiroyuki Kamino, Shin Kumagai, Kazuyoshi Yonekura, Nobuo Kojima, Yoshitaka Tsutsumi, Koji Nishino, Yukio Watanabe
Publikováno v:
Volume 8: Seismic Engineering.
Seismic tests were carried out to confirm the operability limit acceleration for a standard motor-operated butterfly valve actuator in three excitation directions. Based on the results, seismic brackets that can operate valves even in three direction
Autor:
Yoshitaka Tsutsumi, Nobuo Kojima, Koji Nishino, Yukio Watanabe, Shin Kumagai, Kazuyoshi Yonekura
Publikováno v:
Volume 8: Seismic Engineering.
The functional requirements of Main Steam Safety Relief Valves (SRVs) provided in Boiling Water Reactor (BWR) nuclear power plants in Japan have been previously evaluated via seismic tests and so forth; however, since the response acceleration has in
Autor:
Yukio Watanabe, Hiroyuki Kamino, Shin Kumagai, Koji Nishino, Kazuyoshi Yonekura, Yoshitaka Tsutumi, Nobuo Kojima
Publikováno v:
Volume 8: Seismic Engineering.
Functional requirements of motor-operated valves provided in nuclear power plants during an earthquake have been previously evaluated via seismic tests and so forth; however, since the response acceleration has increased in line with a recent reasses
Autor:
Sei Ogawa, Shinji Akiba, Junichi Hakii, Tatsuo Ishida, Naoki Hiranuma, Fumio Inada, Mitsuo Kugimoto, Akitaka Hidaka, Shinsuke Ueno, Koshi Sakata, Haruhide Hatano, Haruei Miyaguchi, Kazuyoshi Yonekura
Publikováno v:
TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A. 75:118-126
Publikováno v:
Volume 4: Fluid-Structure Interaction.
The vibration response of a typical globe valve was measured to determine the characteristics of flow-induced vibration in a cavitating flow, varying valve opening rate from 20% to 40%, and flow rate from 0.2 m3 /min to 1.4 m3 /min or maximum flow ra
Autor:
Jun Mizutani, Shunichi Suzuki, Tsuneo Futami, Kazuyoshi Yonekura, Chikashi Shitara, Minoru Masuda, Katsuhiko Kumagai
Publikováno v:
Residual Stress, Fracture, and Stress Corrosion Cracking.
Through inspections of Japanese boiling water reactors (BWRs) from 2002, a high occurrence rate of Inter Granular Stress Corrosion Cracking (IGSCC) was confirmed in core shrouds and re-circulation (PLR) pipings made of low-carbon (L-grade) stainless