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Journal Articles

Arrangements for telephone consultation on radiation health effects in a nuclear emergency in Japan; Lessons learned from the nuclear accident in Fukushima, Japan, 2011

Okuno, Hiroshi; Kawakami, Takeshi; Watanabe, Fumitaka; Horikoshi, Hidehiko*

Journal of Disaster Research, 18(8), p.911 - 917, 2023/12

In response to residents' concerns about the radiation health effects following the nuclear accidents at the Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company in March 2011, the Japan Atomic Energy Agency (JAEA) established a telephone consultation system. Eight toll-free telephone lines were prepared, and employees with knowledge of radiation health effects were assigned for consultation. Approximately 35,000 consultations were conducted from March 17, 2011, to September 18, 2012. The results of the text mining analysis revealed that the greatest source of anxiety was the impact on children's health from radiation. The JAEA's system for telephone consultation was improved following this telephone consultation experience. The description of telephone hotlines in the International Atomic Energy Agency (IAEA) guide, GSG-14, was discussed for further improvements of the JAEA's telephone consultation system.

Journal Articles

Investigating the gap between actual and perceived distance from a nuclear power plant; A Case study in Japan

Kato, Takaaki*; Takahara, Shogo; Homma, Toshimitsu

Journal of Disaster Research, 10(4), p.627 - 634, 2015/08

Journal Articles

Design evaluation method of steel-plate reinforced concrete structure containment vessel for sodium-cooled fast reactor

Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Negishi, Kazuo

Journal of Disaster Research, 7(5), p.645 - 655, 2012/10

Japan Sodium-cooled Fast Reactor (JSFR) adopts a new concept of a containment vessel called steel plate reinforced concrete containment vessel (SCCV). The SCCV is considered to be effective to shorten construction period thanks for elimination of rebar work at a site compared with applying a reinforced concrete CV. An SFR CV is lower pressure environment than the LWR CV, although environmental temperature of the SFR is much higher than that of LWR in the accident of coolant leakage. Therefore it is important to investigate its characteristics under high temperature to adopt the SC structure to the JSFR CV because the CV shall keep their containment function in the accidents to be assumed in design. This paper describes the construction of design evaluation method from design, experimental and analytical point of view.

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