Author: Kunugi T. Takase K. Shibata M. Kurihara R. Seki Y.
Publisher: Elsevier
ISSN: 0920-3796
Source: Fusion Engineering and Design, Vol.42, Iss.1, 1998-09, pp. : 67-72
Disclaimer: Any content in publications that violate the sovereignty, the constitution or regulations of the PRC is not accepted or approved by CNPIEC.
Abstract
Related content
Validation of INTRA against the upgraded ingress-of-coolant event tests
By Yitbarek Z.
Fusion Engineering and Design, Vol. 69, Iss. 1, 2003-09 ,pp. :
Safety scenario and integrated thermofluid test
By Seki Y. Kurihara R. Nishio S. Ueda S. Aoki I. Ajima T. Kunugi T. Takase K. Shibata M.
Fusion Engineering and Design, Vol. 42, Iss. 1, 1998-09 ,pp. :
SourceOECD Nuclear Energy, Vol. 2004, Iss. 15, 2004-10 ,pp. :
Sodium as a coolant for fast reactors
Atomic Energy, Vol. 108, Iss. 4, 2010-08 ,pp. :