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Journal Articles

Design study on measures to prevent loss of decay heat removal in a next generation sodium-cooled fast reactor

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.

Journal Articles

Design approach for decay heat removal systems based on the safety design criteria for Gen-IV sodium-cooled fast reactor

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.

Oral presentation

Evaluation of earthquake and tsunami on sodium cooled reactor, 2; Study of an emergency core cooling capability in case of station blackout

Nakata, Shuhei*; Chikazawa, Yoshitaka; Kubo, Shigenobu; Sato, Mitsuru*; Matsumura, Atsushi*

no journal, , 

no abstracts in English

Oral presentation

Earthquake and Tsunami proof of Sodium-cooled Fast Reactor

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.

Oral presentation

Design approach for LOHRS type event based on the safety design criteria for Generation-IV SFR, 2; Study of equipment specification

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.

Oral presentation

Transient analysis on freeze of JSFR decay heat removal system in station blackout

Chikazawa, Yoshitaka; Kato, Atsushi; Nakata, Shuhei*; Matsumura, Atsushi*; Sato, Mitsuru*

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Measures for loss of decay heat removal system in the next generation sodium-cooled fast reactor

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.

Oral presentation

Effects of DPA and helium production on radiation damage microstructures and the mechanical properties in irradiated austenitic stainless steels and ferritic steel

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

Oral presentation

Design study of a decay heat removal system and measures to suppress bypass flow of a penetrated type

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.

Oral presentation

Decay heat removal system concept and basic operation of pool-type sodium-cooled fast reactor

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.

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