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Science and Technology of Nuclear Installations
Volume 2012, Article ID 351809, 13 pages
http://dx.doi.org/10.1155/2012/351809
Research Article

Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor

Research Institute of Nuclear Engineering, University of Fukui, 1-2-4 Kanawa-cho, Tsuruga-shi, Fukui 914-0055, Japan

Received 4 November 2011; Accepted 12 January 2012

Academic Editor: Massimo Salvatores

Copyright © 2012 Toshikazu 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

Toshikazu Takeda, W. F. G. van Rooijen, Katsuhisa Yamaguchi, Masayoshi Uno, Yuji Arita, and Hiroyasu Mochizuki, “Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor,” Science and Technology of Nuclear Installations, vol. 2012, Article ID 351809, 13 pages, 2012. https://doi.org/10.1155/2012/351809.