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JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2010 (Joint research)

Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.

JAEA-Technology 2011-031, 123 Pages, 2012/01

JAEA-Technology-2011-031.pdf:16.08MB

The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.

Oral presentation

R&D project on irradiation damage management technology for structural materials of long-life nuclear plant; R&D of irradiation damage indicator and irradiation damage management

Wakai, Eiichi; Takada, Fumiki; Takaya, Shigeru; Kato, Shoichi; Kitazawa, Sin-iti; Okubo, Nariaki; Suzudo, Tomoaki; Fujii, Kimio; Yoshitake, Tsunemitsu; Kaji, Yoshiyuki; et al.

no journal, , 

no abstracts in English

Oral presentation

Research and development of high power wideband diplexer for ECCD system

Atsumi, Kohei*; Sugawara, Shuhei*; Yamaguchi, Tomoki*; Saigusa, Mikio*; Oda, Yasuhisa; Takahashi, Koji; Kajiwara, Ken; Sakamoto, Keishi

no journal, , 

no abstracts in English

Oral presentation

Proposal of new type diplexer for ECCD system

Saigusa, Mikio*; Sugawara, Shuhei*; Atsumi, Kohei*; Oda, Yasuhisa; Yamaguchi, Tomoki*; Sakamoto, Keishi

no journal, , 

Oral presentation

Development of high power wideband diplexer for ECCD system in fusion devise

Sugawara, Shuhei*; Atsumi, Kohei*; Yamaguchi, Tomoki*; Saigusa, Mikio*; Oda, Yasuhisa; Takahashi, Koji; Kajiwara, Ken; Sakamoto, Keishi

no journal, , 

Oral presentation

Conceptual design of next generation MTR

Nagata, Hiroshi; Yamaura, Takayuki; Naka, Michihiro; Kawamata, Kazuo; Izumo, Hironobu; Hori, Naohiko; Nagao, Yoshiharu; Kusunoki, Tsuyoshi; Kaminaga, Masanori; Komori, Yoshihiro; et al.

no journal, , 

Conceptual design of the high-performance and low-cost next generation materials testing reactor which will be assumed to introduce to the nuclear power plant introduction country started from 2010 in the JAEA. Japanese atomic energy-related companies participate in this project, and this activity role as the environmental management and nuclear human resource development for the new research reactor designs. 10 MW thermal power by plate type fuel elements and swimming pool type was assumed as a design base. High safety, high cost performance, high reactor operation rate, high technology irradiation are targets of this conceptual design.

Oral presentation

A Study of unwanted higher orer modes in waveguide resonance ring diplexer for high power millimeter wave

Oda, Yasuhisa; Sugawara, Shuhei*; Atsumi, Kohei*; Yamaguchi, Tomoki*; Saigusa, Mikio*; Sakamoto, Keishi

no journal, , 

no abstracts in English

Oral presentation

Dopant effect of simulated nuclear fuel, ceria solid solution on electron density distribution

Taguchi, Tomitsugu; Miwa, Shuhei; Igawa, Naoki; Birumachi, Atsushi; Yamaguchi, Kenji; Osaka, Masahiko

no journal, , 

The crystal structure and electron density distribution of simulated nuclear fuel, ceria solid solution were analyzed by the Rietveld method and the maximum entropy method using X-ray powder diffraction. The crystal structure was refined with the space group, ${it Fm-3m}$, the same as UO$$_{2}$$. We observed that the electron density distributed between metal- oxygen site and oxygen-oxygen sites with the isosuface level of 0.4 e/$AA $^{3}$$. Two-dimentional electron density distribution maps on (004) plain of the ceria solid solutions indicate that the shape and density of the electron diffusion path were affected by the dopants.

Oral presentation

New Reactor Cavity Cooling System (RCCS) having passive safety features, 2; Experimental study on heat transfer characteristics using a scale model

Sato, Noriyasu*; Yamaguchi, Shuhei*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Last year, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

Oral presentation

Study on heat transfer characteristics of reactor cavity cooling system with passive safety features; Experimental investigation using a scaled model

Yamaguchi, Shuhei*; Sato, Noriyasu*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. In 205, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

Oral presentation

An Experimental investigation on heat transfer characteristics using a scaled model of a reactor cavity cooling system with passive safety features

Yamaguchi, Shuhei*; Sato, Noriyasu*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Last year, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

Oral presentation

Investigation on heat transfer characteristics of reactor cavity cooling system for HTGR

Hosomi, Seisuke*; Yamaguchi, Shuhei*; Akashi, Tomoyasu*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. After building the scale-down heat removal test facility, we conducted experiments and analyses to understand the heat-transfer characteristics. As a result, we could assess effect of radiation and natural convection quantitatively for passive decay heat removal from the RPV.

Oral presentation

Effects of DPA and helium production on radiation damage microstructures and the mechanical properties in irradiated austenitic stainless steels and ferritic steel

Wakai, Eiichi; Takaya, Shigeru; Nagae, Yuji; Suzudo, Tomoaki; Hirade, Tetsuya; Matsui, Yoshinori; Nogami, Shuhei*; Hasegawa, Akira*; Abe, Hiroaki*; Iwai, Takeo*; et al.

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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