Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 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

A Conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.

Mechanical Engineering Journal (Internet), 7(3), p.19-00489_1 - 19-00489_16, 2020/06

The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.

Journal Articles

A Conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.

Oral presentation

Neutron penetration behavior of Zr-H and B$$_{4}$$C in the fast reactor

Saito, Hiroyuki*; Higurashi, Koichi*; Kanazawa, Mitsuhiro*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Studies on the safety design guidelines of Generation-IV Sodium-cooled Fast Reactors, 9; Focal points of safety design guideline for containment system

Higurashi, Koichi*; Akiyama, Yo*; Yamano, Hidemasa

no journal, , 

Of important items which would be relected to safety design guideline (SDG), overview of item 14 "formation and load of containment boundary" related to containment system is described based on design concept of next generation SFR in Japan.

Oral presentation

Oral presentation

Fuel and NFBC assemblies design for the next generation sodium-cooled fast reactor, 2; Optimization of a radial shielding structure

Saito, Hiroyuki*; Higurashi, Koichi*; Masuyama, Daisuke*; Oki, Shigeo; Ohgama, Kazuya; Maeda, Seiichiro

no journal, , 

no abstracts in English

Oral presentation

A Conceptual design study on pool-type sodium-cooled fast reactor with enhanced anti-seismic capability, 2; A Study on safety design concept

Kubo, Shigenobu; Higurashi, Koichi*; Miyagawa, Takayuki*

no journal, , 

Safety design concept for a pool-type sodium cooled fast reactor was investigated based on the safety design criteria and safety design guidelines developed in the generation IV reactor international forum.

7 (Records 1-7 displayed on this page)
  • 1