Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Conceptual design study for the demonstration reactor of JSFR, 5; Reactor cooling system design

Kisohara, Naoyuki; Ishikawa, Hiroyasu; Futagami, Satoshi; Xu, Y.*; Shimoji, Kuniyuki*; Kawamura, Masaya*

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 9 Pages, 2011/10

The cooling system of the JSFR adopts an integrated primary sodium pump/intermediate heat exchanger (IHX), dual structure straight tube steam generator (SG) and short elbow sodium piping layout. Since, however, this is the first experience applying these technologies to SFRs in Japan, design approaches have been evaluated and R&D has been undertaken. This paper addresses the design study of the cooling system of the demonstration reactor JSFR in terms of thermal-hydraulic and structural integrity. Recent studies have shown that these new technologies have potential to be applied to the JSFR.

Oral presentation

Conceptual design toward the commercial reactor of JSFR, 6; Integrated intermediate heat exchanger with primary pump

Shimoji, Kuniyuki*; Hayafune, Hiroki; Oda, Yasushi*; Kotake, Shoji*

no journal, , 

An intermediate heat exchanger (IHX) integrated with the primary pump is being developed for the cooling system of Japan Sodium-cooled Fast Reactor (JSFR) as a candidate of innovative technology for the purposes such as streamlining its facilities and layout in the Fast Reactor Cycle Technology Development (FaCT) project. This paper reports the result of applicability study of the innovative technology.

Oral presentation

Evaluation of earthquake and tsunami on sodium cooled reactor, 1; Seismic structural integrity evaluation of main components

Fukasawa, Tsuyoshi*; Shimoji, Kuniyuki*; Kawamura, Masaya*; Okamura, Shigeki*; Kisohara, Naoyuki; Enuma, Yasuhiro

no journal, , 

no abstracts in English

Oral presentation

Design study for flow around pump shaft of Integrated IHX/pump of fast reactor JSFR, 2; Study of liquid sloshing caused by rotating pump shaft

Handa, Takuya; Enuma, Yasuhiro; Ono, Yukihiko*; Nakamura, Yuki*; Sakata, Nobuyasu*; Kushioka, Kiyonori*; Shimoji, Kuniyuki*; Inoue, Tomoyuki*; Matsumoto, Iwao*

no journal, , 

no abstracts in English

4 (Records 1-4 displayed on this page)
  • 1