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

Publication Information

Title

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

Author

Japanese:	Toshikazu Takeda, W.F.G. van Rooijen, Katsuhisa Yamaguchi, Masayoshi Uno, Yuji Arita, Hiroyasu Mochizuki.
English:	Toshikazu Takeda, W.F.G. van Rooijen, Katsuhisa Yamaguchi, Masayoshi Uno, Yuji Arita, Hiroyasu Mochizuki.

Language

English

Journal/Book name

Japanese:	Science and Technology of Nuclear Installations
English:	Science and Technology of Nuclear Installations

Volume, Number, Page

Vol. 2012 1-13

Published date

Jan. 2012

Publisher

Japanese:
English:

Conference name

Japanese:
English:

Conference site

Japanese:
English:

DOI