Flow-induced vibration evaluation of primary hot-leg piping in advanced loop-type sodium-cooled fast reactor for demonstration

Yamano, Hidemasa; Xu, Y.*; Sago, Hiromi*; Hirota, Kazuo*; Baba, Takeo*

Proceedings of 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016) (CD-ROM), p.1029 - 1038, 2016/04

This study conducted the flow-induced vibration evaluation of the primary hot-leg piping in the demonstration reactor design of advanced loop-type sodium-cooled fast reactor in order to confirm the integrity of the piping. Following the description of the primary hot-leg piping design and a design guideline of the flow-induced vibration evaluation, this paper describes mainly the flow-induced vibration evaluation and thereby the integrity assessment. In the fatigue evaluation for the flow-induced vibration, the pipe stresses considering the stress concentration factor and so on, at representative locations were less than the design fatigue limit. Therefore, this evaluation confirmed the integrity of the primary hot-leg piping in the demonstration reactor.

Analysis of steam generator tube rupture as a severe accident using MELCOR1.8.4

H.Yang*; Hidaka, Akihide; Sugimoto, Jun

JAERI-Tech 99-013, 97 Pages, 1999/03

JAERI-Tech-99-013.pdf:3.24MB

no abstracts in English

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium cooled fast reactor, 45; Structural integrity evaluation of the primary hot leg pipe due to flow-induced vibration

Xu, Y.*; Sago, Hiromi*; Hirota, Kazuo*; Baba, Takeo*; Yamano, Hidemasa

no journal, , 

Structural integrity evaluation has been carried out for a hot-leg pipe due to random vibration induced by turbulence of pipe flow using "proposed guideline of flow-induced vibration evaluation for the primary hot-leg piping in sodium-cooled fast reactor", which has reflected the R&D results of the flow-induced vibration for a large-diameter piping. This gave the prospect of integrity of the primary hot-leg piping in the demonstration fast reactor.