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Chikazawa, Yoshitaka; Kato, Atsushi; Nabeshima, Kunihiko; Otaka, Masahiko; Uzawa, Masayuki*; Ikari, Risako*; Iwasaki, Mikinori*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05
Design study and evaluation for SDC and safety SDG on the BOP of the demonstration JSFR including fuel handling system, power supply system, component cooling water system, building arrangement are reported. For the fuel handling system, enhancement of storage cooling system has been investigated adding diversified cooling systems. For the power supply, existing emergency power supply system has been reinforced and alternative emergency power supply system is added. For the component cooling system and air conditioning, requirements and relation between safety grade components are investigated. Additionally for the component cooling system, design impact when adding decay heat removal system by sea water has been investigated. For reactor building, over view of evaluation on the external events and design policy for distributed arrangement is reported. Those design study and evaluation provides background information of SDC and SDG.
Nabeshima, Kunihiko; Aizawa, Kosuke; Chikazawa, Yoshitaka; Sato, Daisuke*; Ikari, Risako*
Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.600 - 606, 2014/04
One of the advantages in features of Japan Sodium-cooled Fast Reactor (JSFR) is that it's free from high-capacity power load or quick activation of emergency power supply because Decay Heat Removal System (DHRS) adopted natural circulation. However, the Emergency Power Supply System of JSFR is reconsidered to improve the reliability for station blackout (SBO) caused by extreme external events after the nuclear accident at Fukushima. A non-class 1E GTG are added for practically elimination of Loss of Heat Removal System (LOHRS), and alternative power supply system composed of small air-cooled DG and lead-acid batteries is newly introduced to maintain class 1E equipment against the long-term station blackout (SBO).
Ishikawa, Nobuyuki; Chikazawa, Yoshitaka; Sato, Daisuke*; Ikari, Risako*
no journal, ,
In the design of the next generation sodium fast reactor (SFR), reinforcement of the design in terms of independency, diversity and multipleness is required. To meet this requirement, optimal configuration of emergency power supply system for next generation SFR is investigated and concept of this configuration is established.
Takano, Kazuya; Kato, Atsushi; Uchita, Masato*; Okazaki, Hitoshi*; Ikari, Risako*
no journal, ,
Primary Heat Transport System (PHTS) flow rate is the most promising signal to detect the pump/diagrid link rupture in pool type SFR. The electromagnetic flowmeter is considered to measure the PHTS flow rate and is designed to install nearby outlet of the PHTS circulation pump in the current design of pool-type SFR with 600 MWe. The flowmeter could be significantly affected by the noise from pump motor. In order to improve the signal strength, the structure of flowmeter is drastically modified with the D-shape yokes and the magnetic circuits above and below an electrode.