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Aizawa, Kosuke; Kotake, Shoji; Chikazawa, Yoshitaka; Ara, Kuniaki; Araseki, Hideo*; Aizawa, Rie*; Ota, Hiroyuki*
Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9402_1 - 9402_8, 2009/05
This paper describes a future innovative design options with a parallel electromagnetic pump (EMP) system as the main circulating pump of the JSFR design. A conceptual design of EMPs integrated with an intermediate heat exchanger (IHX) is carried out. The major design parameters are consistent with the current JSFR design, where the main flow rate is 630 m/min and the flow halving time is the same of the mechanical pump with the similar reliability. As a result of several design studies, a five parallel EMPs with IHX system has been selected from the geometry suitability for JSFR design. The EMP advantages comparing with mechanical pumps are investigated from the views of in-service inspection, maintenance and reliability. Numerical analysis with two dimensional MHD codes is conducted on a former experiment of a 160 m/min flow rate EMP. The overall trend of the experimental data and the numerical results agrees with that in small-scale EMPs.
Doda, Norihiro; Araseki, Hideo; Nabeshima, Kunihiko; Takata, Takashi; Tanaka, Masaaki; Ohshima, Hiroyuki
no journal, ,
JAEA has started the development of a multi-level plant simulation system as a powerful tool for the design studies of sodium-cooled fast reactors. This system enables from highly-efficient to highly-accurate analyses of various operating statuses including normal operation, abnormal transient and accidents by employing multi-level models, and is able to respond flexibly to most of the design options. The conceptual design of the new system, the coupling method of codes as a key of the system development, and the development plan are reported in this presentation.
Doda, Norihiro; Araseki, Hideo; Nabeshima, Kunihiko; Takata, Takashi; Tanaka, Masaaki; Ohshima, Hiroyuki
no journal, ,
JAEA has developed a multi-level plant simulation system to enhance a safety assessment technology for sodium cooled fast reactor. The system, in which high-efficient plant dynamics analyses with a one-dimensional system code and high-accurate local phenomena analyses with multi-dimensional codes are coupled, may apply to the various design options of sodium cooled reactor. In this report, the present status in the development of the basic functions in the system are reported.