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Watanabe, Kazuhito; Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Uto, Hiroyasu; Sakamoto, Yoshiteru; Araki, Takao*; Asano, Shiro*; Asano, Kazuhito*
Proceedings of 26th IEEE Symposium on Fusion Engineering (SOFE 2015), 6 Pages, 2016/06
Safety studies of a water-cooled fusion DEMO reactor have been performed. In the event of the blanket cooling pipe break outside the vacuum vessel, i.e. ex-vacuum vessel loss of coolant accident (ex-VV LOCA), the pressurized steam and air may lead to damage reactor building walls which have confinement function, and to release the radioactive materials to the environment. In response to this accident, we proposed three cases of confinement strategies. In each case, the pressure and thermal loads to the confinement boundaries and total mass of tritium released to outside the boundaries were analyzed by accident analysis code MELCOR modified for fusion reactor. These analyses developed design parameters to maintain the integrity of the confinement boundaries.
Sakamoto, Yoshiteru
no journal, ,
The development strategy for the establishment of technology bases required for Japanese DEMO is presented, especially the element of diagnostics and control systems. The core issue is to focus clusters of essential and applicable diagnostics based upon performance and operating results of diagnostics developed and prepared in ITER because of various constraints due to high irradiation field in DEMO. In particular, it is necessary to show the prospect of the DEMO relevant diagnostics through the development of essential diagnostics for burning control and radiation-proofed components, and improvement of accuracy of equilibrium control by magnetic measurements as well as to develop the real time operation control simulator.
Tommasi, G. D.*; Farthing, J.*; Joffrin, E.*; Vega, J.*; Vitale, V.*; Clement, S.*; Sartori, F.*; Kubo, Hirotaka; Nakajima, Noriyoshi*; Ozeki, Takahisa
no journal, ,
The ITER Remote Experimentation Centre is one of the projects currently under implementation within the International Fusion Energy Research Centre. The final objective of the REC is to allow researchers to take part in the experimentation on ITER from a remote location. This includes the possibility to receive in real-time information about the status of the machine and experimental data and to interact with the machine control room. This paper first gives an overview on the current status of the REC project, and then it focuses on a proposal for the REC demonstration to be carried out in collaboration with European Tokamaks. Finally, a possible implementation plan for the demonstration is discussed.
