Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Chikazawa, Yoshitaka; Kubo, Shigenobu; Shimakawa, Yoshio*; Kaneko, Fumiaki*; Shoji, Takashi*; Nakata, Shuhei*
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04
Sodium-cooled reactor (SFR) has superior characteristics thanks to sodium coolant features such as low pressure and high natural convection capability. Involving lessons learned from the 1F accident, requirements on design base DHRS have been modified. In that modification, safety requirements on design extended conditions have been clarified and sodium temperature criteria have been changed taking into account design margin even for design extended conditions. With the new DHRS configuration including ACS, designs of component cooling water system and emergency power supply have been updated.
Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Hayafune, Hiroki; Yokoi, Shinobu*; Nakata, Shuhei*; Tani, Akihiro*; Shimakawa, Yoshio*
Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.616 - 623, 2014/04
This paper focuses on loss of heat removal system (LOHRS) type event as Design Extension Condition (DEC) and describes candidates design measures to improve the decay heat removal system of JSFR against LOHRS type DEC. The design requirements are determined based on the Safety Design Criteria for Generation-IV Sodium-cooled fast reactor system. Effectiveness and reliability of the candidate design measures are discussed with preliminary evaluations.
Nakata, Shuhei*; Chikazawa, Yoshitaka; Kubo, Shigenobu; Sato, Mitsuru*; Matsumura, Atsushi*
no journal, ,
no abstracts in English
Kato, Atsushi; Chikazawa, Yoshitaka; Yamano, Hidemasa; Kubo, Shigenobu; Hayafune, Hiroki; Sagawa, Hiroshi*; Okamura, Shigeki*; Nakata, Shuhei*
no journal, ,
Earthquake and Tsunami proof of the Sodium-cooled Fast Reactor (SFR) has been evaluated. As for seismic design, safety grade components are confirmed to maintain their functions even against recent strong earthquakes. As for Tsunami, in the SFR design, safety grade components are independent from component cooling water system. A gas turbine system with air cooling is adopted for emergency power supply, since the SFR does not basically require quick start-up of the emergency power supply thanks to the natural convection Decay Heat Removal System (DHRS). Even in case of long station blackout, the DHRS could be activated by emergency batteries or manually and be operated continuously by natural convection.
Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Nakata, Shuhei*; Yokoi, Shinobu*
no journal, ,
Plant design studies against "Loss of heat removal system" event were carried out based on the safety design criteria for 4th generation sodium-cooled fast reactor discussing in the Generation-IV international forum (GIF-SFR-SDC). This presentation introduces equipment specification study to match the GIF-SFR-SDC.
Chikazawa, Yoshitaka; Kato, Atsushi; Nakata, Shuhei*; Matsumura, Atsushi*; Sato, Mitsuru*
no journal, ,
no abstracts in English
Sato, Daisuke*; Nakata, Shuhei*; Kubo, Shigenobu
no journal, ,
no abstracts in English
Chikazawa, Yoshitaka; Kubo, Shigenobu; Shimakawa, Yoshio*; Kaneko, Fumiaki*; Shoji, Takashi*; Nakata, Shuhei*
no journal, ,
Measures against loss of heat removal system (LOHRS) type events in the next generation sodium-cooled reactor (SFR) have been developed. While the next generation SFR already has three-independent decay heat removal systems for design basis. An additional auxiliary cooling system is installed.
Wakai, Eiichi; Takaya, Shigeru; Nagae, Yuji; Suzudo, Tomoaki; Hirade, Tetsuya; Matsui, Yoshinori; Nogami, Shuhei*; Hasegawa, Akira*; Abe, Hiroaki*; Iwai, Takeo*; et al.
no journal, ,
no abstracts in English
Kato, Atsushi; Yamane, Yuma*; Nakata, Shuhei*
no journal, ,
As one of the decay heat removal systems for sodium-cooled fast reactors (SFRs), a penetrated through-core type direct reactor core cooling system (penetrated type DRACS) has been investigated. This paper describes the configuration of the decay heat removal system and the bypass flow suppression structure of the penetrated type DRACS.
Kato, Atsushi; Ichikawa, Kenta*; Nakata, Shuhei*; Chikazawa, Yoshitaka; Ando, Masato
no journal, ,
In the conceptual study of a tank-type sodium-cooled fast reactor, a decay heat removal system concept was developed, taking into account the use of natural circulation heat removal and the diversity of heat removal methods, and a basic plant operation way after the reactor trip was established.