Research and examination of seismic safety evaluation and function maintenance for important equipment in nuclear facilities

Furuya, Osamu*; Fujita, Satoshi*; Muta, Hitoshi*; Otori, Yasuki*; Itoi, Tatsuya*; Okamura, Shigeki*; Minagawa, Keisuke*; Nakamura, Izumi*; Fujimoto, Shigeru*; Otani, Akihito*; et al.

Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet), 6 Pages, 2021/07

Since the Fukushima accident, with the higher safety requirements of nuclear facilities in Japan, suppliers, manufacturers and academic societies have been actively considering the reconstruction of the safety of nuclear facilities from various perspectives. The Nuclear Regulation Authority has formulated new regulatory standards and is in operation. The new regulatory standards are based on defense in depth, and have significantly raised the levels of natural hazards and have requested to strengthen the countermeasures from the perspective of preventing the simultaneous loss of safety functions due to common factors. Facilities for dealing with specific serious accidents are required to have robustness to ensure functions against earthquakes that exceed the design standards to a certain extent. In addition, since the probabilistic risk assessment (PRA) and the safety margin evaluation are performed to include the range beyond the design assumption in the safety improvement evaluation, it is very important to extent the special knowledge in the strength of important equipment for seismic safety. This paper summarizes the research and examination results of specialized knowledge on the concept of maintaining the functions of important seismic facilities and the damage index to be considered by severe earthquakes. In the other paper, the study on reliability of seismic capacity analysis for important equipment in nuclear facilities will be reported.

Stress and strain evaluation of the heat transfer tubes in the intermediate heat exchanger for the HTTR

Kunitomi, Kazuhiko; Shinozaki, Masayuki; ; Okubo, Minoru; Baba, Osamu; *; Otani, Akihito*

JAERI-M 92-147, 77 Pages, 1992/10

JAERI-M-92-147.pdf:1.77MB

no abstracts in English

Conceptual design study of small-sized high temperature gas-cooled reactor for developing countries, 6; Intermediate heat exchanger design and examination of the placement concept

Suzuki, Tetsu*; Maruyama, Shigeki*; Kamijo, Chiharu*; Otani, Akihito*; Kan, Norio*; Yan, X.; Sato, Hiroyuki; Tazawa, Yujiro; Ohashi, Hirofumi; Tachibana, Yukio

no journal, , 

no abstracts in English