Refine your search:     
Report No.
 - 
Search Results: Records 1-3 displayed on this page of 3
  • 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

Development of elevated temperature structural design method for fast reactor vessels, 1; Concept of development in strength evaluation

Kawasaki, Nobuchika; Nagae, Yuji; Kato, Shoichi; Ando, Masanori; Kasahara, Naoto

Dai-13-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.507 - 510, 2008/06

Concept of development in strength evaluation for fast reactor vessels was introduced. Based on the characteristics of reactor vessel for developing fast breeder reactor, creep-fatigue strength and ratcheting deformation criterion are under developing. For the creep-fatigue strength, intermediate dwelling creep-fatigue, aging effect and strain concentration are selected as developing items. The ratcheting deformation criterion will be determined by ratcheting fatigue and ratcheting creep-fatigue test results.

Journal Articles

Investigation on enhancement of reliability for components of reactor system in sodium-cooled fast reactor toward commercialization

Sakamoto, Yoshihiko; Kubo, Shigenobu*; Kotake, Shoji; Kamishima, Yoshio*

Dai-13-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.505 - 506, 2008/06

This paper describes the enhancement of reliability for components of the reactor system in JSFR design. As for manufacturability, compact design of the RV enables its manufacture in a factory. This results in high quality welding and in precise machining of the RV. The adoption of ring-shaped forgings contributes for securing the reliability against thermal stress as well as securing the dimension precision. Regarding maintenability, the in-vessel structures have simple configurations, so it is comparatively easy for inspection equipments to reach inspection targets. In the JSFR design, sodium boundary area is reduced significantly, which makes double-walled design of the piping easier, and reduces welding lines. So, the reactor system of JSFR is desirable to inspect the in-vessel structures efficiently, and there is a prospect of reliable plant operation. Advanced inspection technologies are also under development for the inspection of the in-vessel structures under sodium.

Journal Articles

Development of thermal hydraulic computer code for steam-water flow in steam generator of fast breeder reactor

Yoshikawa, Ryuji; Hamada, Hirotsugu; Ohshima, Hiroyuki; Yanagisawa, Hideki*

Dai-13-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.495 - 496, 2008/06

In Japan Atomic Energy Agency, investigations on heat transfer characteristics of steam generator are being performed for the development of commercialized sodium-cooled fast breeder reactor. In this study, the computer code for flow instability analysis in single heat transfer tube was developed with drift-flux model which included the effects of subcooled boiling and two phase slip. The special algorithm to calculate inlet flow rate with inlet pressure, outlet pressure and heat flux as boundary conditions for the density-wave instability analysis has been established. The subcooled model was verified by calculating the void fraction distribution of steady heat transfer flow. The capability of drift flux model for simulating density-wave instability in single tube was confirmed.

3 (Records 1-3 displayed on this page)
  • 1