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Onuki, Akira; Kobayashi, Noboru
Dai-45-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu, 1, p.3 - 4, 2008/05
no abstracts in English
Kamide, Hideki; Kimura, Nobuyuki; Ezure, Toshiki; Uchibori, Akihiro; Hayashi, Kenji; Fukuda, Takeshi*; Takata, Takashi*
no journal, ,
Gas entrainment at free surface in a reactor vessel is one of the significant issues in a design of a compact sodium cooled fast reactor. VUV laser is planned to apply visualization of liquid-gas surface shape during the gas entrainment in a sodium test. The sodium experiments were carried out for the onset criteria of the gas entrainment due to a free surface vortex. Water experiment using the same geometry with that in the sodium test was also performed. Onset condition maps in the sodium and water tests were in good agreement.
Kureta, Masatoshi; Kumada, Hiroaki; Kume, Etsuo; Someya, Satoshi*; Okamoto, Koji*
no journal, ,
The paper proposes a new measurement technique named as dynamic neutron computer tomography (CT). The purpose of the development is to visualize and measure the three-dimensional velocity distribution in liquid metal flow based on high-speed neutron radiography and CT techniques. The dynamic neutron CT system generates six neutron beams and neutron radiography images at the same time. And the images are recorded by three set of high-speed video camera systems in the neutron irradiation room of the research reactor JRR-4. Consecutive instantaneous CT value 3D distributions were visualized using a fundamental rotating test section for the dynamic neutron CT test with the developed system.
Takeda, Tetsuaki*; Nakagawa, Shigeaki
no journal, ,
The Generation IV International Forum, or GIF, was chartered in July 2001 to lead the collaborative efforts of the world's leading nuclear technology nations to develop next generation nuclear energy systems to meet the world's future energy needs. The Very-High-Temperature Reactor (VHTR) is the next step in the evolutionary development of high-temperature reactors (HTRs) and is primarily dedicated to the cogeneration of electricity and hydrogen from only heat and water by using thermo-chemical, electro-chemical or hybrid processes. This paper described the current status of thermo-hydraulics studies for technological development of the Very-High-Temperature Reactor System.
Ezato, Koichiro; Akiba, Masato
no journal, ,
In-vessel components such as Blanket and Divertor in a fusion reactor has a function of exhausting high heat and particle loads in order to maintain the structural soundness of the reactor. In the International Thermonuclear Test Reactor called ITER, build by ITER Organization under the framework of collaboration of seven parties including Japan, first wall of blanket and diverter receive as high heat flux as 0.5 MW/m
and 20 MW/m, respectively. This paper intends to present current status of technological development of in-vessel components from the viewpoint of thermal hydraulics.
Kurihara, Akikazu; Shimoyama, Kazuhito; Monde, Masanori*; Ohshima, Hiroyuki
no journal, ,
Sodium reacts chemically with water in case of unexpected tube failure of steam generator (SG) in fast breeder reactor (FBR), exoergic reaction produced reaction field with high temperature and high corrosive (sodium-water reaction). Adjacent tubes in the field have possibility of rupture by inner pressure. It is integral to predict the event with high accuracy that we understand characteristics of heat transfer inside tube in detail. Experimental study has been carried out and clarify characteristics of heat flux and temperature on inner wall under low mass flow rate and high subcooling.
Ohshima, Hiroyuki; Kamide, Hideki
no journal, ,
The Fast reactor Cycle Technology development (FaCT) project is being performed in Japan Atomic Energy Agency toward early commercialization of the fast reactor cycle for the stable supply of energy and resolution of global environmental problems. This paper briefly describes the thermal-hydraulic problems to be solved in the design study of the commercialized sodium-cooled fast reactor, which is carried out in the project, and introduces the current status of the corresponding researches.