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Journal Articles

R&D of lifetime extension for primary materials by active chemistry control for coolant helium

Sakaba, Nariaki

Dai-4-Kai Genshiryoku Shisutemu Kenkyu Kaihatsu Jigyo Heisei-21-Nendo Seika Hokokukai Shiryoshu (CD-ROM), p.117 - 118, 2010/01

no abstracts in English

Journal Articles

Development of physical model describing the dynamic interaction characteristics of component connections for the analysis of an entire nuclear facility

Nishida, Akemi

Dai-4-Kai Genshiryoku Shisutemu Kenkyu Kaihatsu Jigyo Heisei-21-Nendo Seika Hokokukai Shiryoshu (CD-ROM), p.25 - 26, 2010/01

The objective of this project is to contribute to the seismic design evaluation of nuclear facilities through the construction of a numerical evaluation system which is able to evaluate both global and local behaviors of facilities under severe seismic events especially. As one of the technology components to realize this objective, we are developing and incorporating into the system a physical model describing the dynamic interaction characteristics of component connections. In this paper, we summarized about the development of the connection interaction model and the application of the model to a real plant simulation. As the results, it was verified that the responses of plant components decreased in consideration of the partial damage of the connection. It was shown that the introduction of the dynamic interaction characteristics of component connections in detail was important in the seismic design evaluation of nuclear facilities under severe seismic events.

Oral presentation

The Study of highly sensitivity technique for sodium leak detection using laser resonance ionization mass spectrometry to improve fast reactor plant safety

Aoyama, Takafumi; Ito, Chikara; Araki, Yoshio; Naito, Hiroyuki; Iwata, Yoshihiro; Okazaki, Koki*; Harano, Hideki*; Watanabe, Kenichi*; Iguchi, Tetsuo*; Takegawa, Nobuyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of core damage evaluation technology (Level 2 PSA)

Nakai, Ryodai

no journal, , 

The evaluation methodlogies for core material relocation phase and for ex-vessel phase have been developed in order to establish the core damage evaluation methodology for a sodium cooled fast reactor. Also the technical basis is developed for the construction and quantification of phenomenological event trees.

Oral presentation

Development and future perspective of fast reactors in the world

Sagayama, Yutaka

no journal, , 

no abstracts in English

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