Accident Analysis of Fukushima Daiichi Nuclear Power Station Unit 1

This paper analyzes and reviews various seismic damage at the Fukushima Daiichi Nuclear Power Station (F1) caused by the Great East Japan Earthquake (the Earthquake) on March 11 in 2011. Moreover, descriptions of various F1 accident reports on on-site seismic damage are comparatively analyzed. At first, impacts of the Earthquake and tsunami as well as damage at four influenced Nuclear Power Stations (NPSs), including F1, are comparatively analyzed. Although no safety-related equipment were seismically damaged at F1, there occurred various on-site seismic damage which should be learned at NPSs worldwide in preparation for next possible beyond-design-basis disasters. Particularly damaged were the main administration building as well as various on-site high-voltage equipment to receive off-site electric power. Owing largely to this on-site damage F1 lost the off-site power, eventually leading the entire NPS to station black-out. Other on-site seismic damage includes loss of an emergency data transmission system, roads, coolant water tanks, leakage of radio-contaminated water from spent fuel pools (SFP), presumably the Unit-1/2 exhaust stack among others.

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Seismic response and its analysis for components of Fukushima Daiichi Nuclear Power Plants in 2011 Great East Japan Earthquake

Nagasawa

Narabayashi

2016

Transactions of the JSME (In Japanese)

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The Fukushima Daiichi (1F) accident in unit 1 to 4 was likely to be caused by the tsunami induced loss of emergency power and seawater heat sink that is consistently elucidated based on the performance of the plants until the tsunami hit after the seismic SCRAM by Great East Japan Earthquake. However it is fact that the actual damages of components have difficulty to be completely inspected under high radioactivity, and to make clear distinction between tsunami induced damage and seismic induced damage. This paper will support above conclusion based on the result of seismic response analysis for safety related components of each plant, the result of the plant walk down in the similar unit in the same station, and also the result of analysis for the observed seismic records from the perspective of generalization of the damage possibility of nuclear components designed by Japanese seismic standards. The result of seismic response analysis using observed seismic motion shows all safety related components fulfill the seismic criteria and seem to maintain structural integrity. Also we could find few seismic induced damage in the walk down for unit 5 of 1F that shows similar result would be expected in unit 1 to 4. It is concluded that the design method using seismic static load contributes additional robustness of nuclear components, even the lower seismic class components, and that the damage by the earthquake should be quite limited based on the analysis of observed seismic motions.

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Accident Analysis of Fukushima Daiichi Nuclear Power Station Unit 1

Cited by 3 publications

References 2 publications

Classification method of severe accident condition for the development of severe accident instrumentation and monitoring system in nuclear power plant

Classification method of severe accident condition for the development of severe accident instrumentation and monitoring system in nuclear power plant

Seismic Damage at the Fukushima Daiichi Nuclear Power Station With Emphasis on Unit 1

Seismic response and its analysis for components of Fukushima Daiichi Nuclear Power Plants in 2011 Great East Japan Earthquake

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