Development of the JSFR main components, 3; Productivity of the transfer tubes for steam generator

Kawamura, Masaya*; Ushiki, Hiroshi*; Enuma, Yasuhiro; Futagami, Satoshi; Ogumo, Shinya*; Ichihara, Takashi*; Nakashima, Takashi*

no journal, , 

no abstracts in English

A Study on the straight double-walled tube steam generator design against sodium-water reaction in DECs

Kanda, Hironori; Enuma, Yasuhiro; Futagami, Satoshi; Kawamura, Masaya*; Ushiki, Hiroshi*; Ogumo, Shinya*; Ichihara, Takashi*; Nakashima, Takashi*

no journal, , 

Study on in-vessel coolability by decay heat removal systems in sodium-cooled fast reactors, 2; Conceptual design of components for a sodium test facility with in-vessel direct heat exchangers

Tanaka, Masaaki; Ezure, Toshiki; Ishikawa, Nobuyuki; Nabeshima, Kunihiko; Oyama, Kazuhiro*; Nakamura, Hironori*; Ichihara, Takashi*

no journal, , 

In the investigation of measures to enhance safety of a sodium cooled fast reactor, conceptual design of a test apparatus for sodium experiment named AtheNa-RV/DHRS has been conducted for feasibility study of the diverse systems for decay heat removal under various operating conditions including the sever accident. According to the knowledges of important thermal-hydraulic problems to be studied using AtheNa-RV/DHRS and significant points in the design of it, major components consisting of the simulated core and the direct heat exchanger (DHX) was preliminary designed.