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Science and Technology of Nuclear Installations
Volume 2016, Article ID 7481793, 15 pages
http://dx.doi.org/10.1155/2016/7481793
Research Article

ROSA/LSTF Tests and RELAP5 Posttest Analyses for PWR Safety System Using Steam Generator Secondary-Side Depressurization against Effects of Release of Nitrogen Gas Dissolved in Accumulator Water

1Japan Atomic Energy Agency, 2-4 Shirakata-Shirane, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195, Japan
2Mitsubishi Heavy Industries, Ltd., 1-1 Wadasaki 1-Chome, Hyogo-ku, Kobe-shi, Hyogo-ken 652-8585, Japan
3The Kansai Electric Power Co., Inc., 8 Yokota, 13 Goichi Mihama-cho, Mikata-gun, Fukui-ken 919-1141, Japan

Received 27 January 2016; Accepted 10 May 2016

Academic Editor: Tim Haste

Copyright © 2016 Takeshi Takeda et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

How to Cite this Article

Takeshi Takeda, Akira Ohnuki, Daisuke Kanamori, and Iwao Ohtsu, “ROSA/LSTF Tests and RELAP5 Posttest Analyses for PWR Safety System Using Steam Generator Secondary-Side Depressurization against Effects of Release of Nitrogen Gas Dissolved in Accumulator Water,” Science and Technology of Nuclear Installations, vol. 2016, Article ID 7481793, 15 pages, 2016. https://doi.org/10.1155/2016/7481793.