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Journal Articles

Levelized cost of electricity evaluation of SFR system considering safety measures

Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05

The levelized cost of electricity is one of key indicator to evaluate economic competitiveness of energy systems. This report estimated the levelized cost of SFR system considering additional safety measures identified after the 1F incident and social cost, using major calculation tools: G4-ECONS and the calculation tool developed by the Governmental WG in Japan (CEWG-tool). The calculation results of G4-ECONS showed that the additional safety measures raise 160% of levelized cost in the case of the safety enhanced SFR system with 1500 MWe of twin looped cooling system. As a result of calculation with 3% discount rate and social cost, the levelized cost of the safety enhanced SFR system with 1200 MWe of Single looped cooling system was estimated 84 mills/kWh by CEWG-tool. This result is almost equal to the estimated levelized cost of similar standard LWR system, and it was indicated the economic competitiveness of the future SFR system.

Journal Articles

The Prospect of economics of fast reactor cycle

Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 61(1), p.40 - 47, 2019/01

Japan Atomic Energy Agency has proceeded on the research and development (R&D) of fast neutron rector fuel cycle with a system which has economic competitiveness in contrast with light water reactor systems as one of development objectives, from the start of its development. This report shows the evaluation results of generation cost of fast reactor fuel cycle in light of additional safety measure cost and social cost, based on the design of fast reactor and related fuel cycle facilities which considered in FaCT phase I.

Journal Articles

Common reed accumulates starch in its stem by metabolic adaptation under Cd stress conditions

Higuchi, Kyoko*; Kanai, Masatake*; Tsuchiya, Masahisa*; Ishii, Haruka*; Shibuya, Naofumi*; Fujita, Naoko*; Nakamura, Yasunori*; Suzui, Nobuo; Fujimaki, Shu; Miwa, Eitaro*

Frontiers in Plant Science (Internet), 6, p.138_1 - 138_6, 2015/03

 Times Cited Count:13 Percentile:57.96(Plant Sciences)

Journal Articles

Study of safety features and accident scenarios in a fusion DEMO reactor

Nakamura, Makoto; Tobita, Kenji; Gulden, W.*; Watanabe, Kazuhito*; Someya, Yoji; Tanigawa, Hisashi; Sakamoto, Yoshiteru; Araki, Takao*; Matsumiya, Hisato*; Ishii, Kyoko*; et al.

Fusion Engineering and Design, 89(9-10), p.2028 - 2032, 2014/10

 Times Cited Count:10 Percentile:68.92(Nuclear Science & Technology)

After the Fukushima Dai-ichi nuclear accident, a social need for assuring safety of fusion energy has grown gradually in the Japanese (JA) fusion research community. DEMO safety research has been launched as a part of BA DEMO Design Activities (BA-DDA). This paper reports progress in the fusion DEMO safety research conducted under BA-DDA. Safety requirements and evaluation guidelines have been, first of all, established based on those established in the Japanese ITER site invitation activities. The amounts of radioactive source terms and energies that can mobilize such source terms have been assessed for a reference DEMO, in which the blanket technology is based on the Japanese fusion technology R&D programme. Reference event sequences expected in DEMO have been analyzed based on the master logic diagram and functional FMEA techniques. Accident initiators of particular importance in DEMO have been selected based on the event sequence analysis.

Journal Articles

Key aspects of the safety study of a water-cooled fusion DEMO reactor

Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Gulden, W.*; Sakamoto, Yoshiteru; Araki, Takao*; Watanabe, Kazuhito*; Matsumiya, Hisato*; Ishii, Kyoko*; et al.

Plasma and Fusion Research (Internet), 9, p.1405139_1 - 1405139_11, 2014/10

Key aspects of the safety study of a water-cooled fusion DEMO reactor is reported. Safety requirements, dose target, DEMO plant model and confinement strategy of the safety study are briefly introduced. The internal hazard of a water-cooled DEMO, i.e. radioactive inventories, stored energies that can mobilize these inventories and accident initiators and scenarios, are evaluated. It is pointed out that the enthalpy in the first wall/blanket cooling loops, the decay heat and the energy potentially released by the Be-steam chemical reaction are of special concern for the water-cooled DEMO. An ex-vessel loss-of-coolant of the first wall/blanket cooling loop is also quantitatively analyzed. The integrity of the building against the ex-VV LOCA is discussed.

Oral presentation

Na$$^{+}$$ behavior in Reed under continuous saline stress

Maruyama, Teppei*; Suzui, Nobuo; Fujimaki, Shu; Kawachi, Naoki; Ishii, Satomi; Matsuhashi, Shimpei; Yoshiba, Masaaki*; Tadano, Toshiaki*; Higuchi, Kyoko*

no journal, , 

no abstracts in English

Oral presentation

Characterization of the Cd-binding macromolecule in stem of common reed

Tsuchiya, Masahisa*; Fukawa, Sayaka*; Suzui, Nobuo; Ishii, Satomi; Kawachi, Naoki; Fujimaki, Shu; Miwa, Eitaro*; Higuchi, Kyoko*

no journal, , 

no abstracts in English

Oral presentation

Study of a loss of coolant accident in a tokamak DEMO

Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Araki, Takao*; Watanabe, Kazuhito*; Kittaka, Daigo*; Ishii, Kyoko*; Matsumiya, Hisato*

no journal, , 

Recent findings on safety characteristics of a tokamak DEMO reactor are reported in the case where all the coolant water is lost completely and instantaneously. Assuming that there are neither off-site power nor active emergency cooling, we have analyzed temporal histories of the temperatures of the reactor components using the fusion reactor thermo-hydraulic analysis code MELCOR-fus. We have found that even in such an extremely severe case, the temperatures of the vacuum vessel and in-vessel components do not reach their melting points.

Oral presentation

Present status of Action Plan for fusion DEMO

Nishimura, Arata*; Okano, Kunihiko*; Ikebe, Yasushi*; Oba, Kyoko; Kasada, Ryuta*; Sakamoto, Ryuichi*; Sawa, Naoki*; Ishii, Yasutomo*; Kashiwagi, Mieko*; Takenaga, Hironobu*; et al.

no journal, , 

no abstracts in English

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