Analyzing reactor water level measurements in the Fukushima Daiichi 1 accident
Year of publication
2023
Authors
Sevón, Tuomo
Abstract
<p>Measuring the water level in the Fukushima Daiichi reactors was based on measuring the pressure difference between two pipes, connected to the reactor at different elevations and filled with water. Boiling of the water in the measurement system distorted the measurements. The water level readings during the unit 1 accident were analyzed with the MELCOR code. The behavior of the measurement system can be reproduced by assuming a small leak of superheated steam from a steam line to the drywell before 6.5 h after the earthquake. This confirms earlier conclusions of a Japanese accident investigation committee and analyses performed by TEPCO. The steam leak did not have any significant effect on the cesium release to the environment.</p>
Show moreOrganizations and authors
VTT Technical Research Centre of Finland Ltd
Sevón Tuomo 
Publication type
Publication format
Article
Parent publication type
Journal
Article type
Original article
Audience
ScientificPeer-reviewed
Peer-ReviewedMINEDU's publication type classification code
A1 Journal article (refereed), original researchPublication channel information
Journal
Volume
160
Article number
104707
ISSN
Publication forum
Publication forum level
1
Open access
Open access in the publisher’s service
Yes
Open access of publication channel
Partially open publication channel
License of the publisher’s version
CC BY
Self-archived
No
Other information
Fields of science
Materials engineering
Keywords
[object Object],[object Object],[object Object],[object Object]
Language
English
International co-publication
No
Co-publication with a company
No
DOI
10.1016/j.pnucene.2023.104707
The publication is included in the Ministry of Education and Culture’s Publication data collection
Yes