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Journal Articles

2016 Professional Engineer (PE) test preparation course "Nuclear and Radiation Technical Disciplines"

Takahashi, Naoki; Yoshinaka, Kazuyuki; Harada, Akio; Yamanaka, Atsushi; Ueno, Takashi; Kurihara, Ryoichi; Suzuki, Soju; Takamatsu, Misao; Maeda, Shigetaka; Iseki, Atsushi; et al.

Nippon Genshiryoku Gakkai Homu Peji (Internet), 64 Pages, 2016/00

no abstracts in English

Journal Articles

Journal Articles

Explanation of question and answer in special subject examination of the first test for professional engineer "nuclear and radiation" executed in 2010 fiscal year, Part 2; Nuclear section

Natsume, Tomohiro*; Nakano, Makoto*; Harada, Akio; Yamanaka, Atsushi; Kurihara, Ryoichi

Genshiryoku eye, 57(4), p.72 - 76, 2011/04

no abstracts in English

Journal Articles

Commentaries for third secondary national examination on fiscal 2010 for the professional engineer of nuclear and radiation; Commentaries (Part 1) including key point for elective examinations

Sasaki, Satoru; Suto, Toshiyuki; Harada, Akio; Kurihara, Ryoichi; Yamamoto, Kazuyoshi; Tsuchida, Noboru; Shimizu, Isamu; Nomura, Toshibumi

Genshiryoku eye, 57(1), p.66 - 75, 2011/01

no abstracts in English

Journal Articles

Design study of superconducting coils for the fusion DEMO plant at JAERI

Isono, Takaaki; Koizumi, Norikiyo; Okuno, Kiyoshi; Kurihara, Ryoichi; Nishio, Satoshi; Tobita, Kenji

Fusion Engineering and Design, 81(8-14), p.1257 - 1261, 2006/02

 Times Cited Count:4 Percentile:66.5(Nuclear Science & Technology)

In order to realize an economically competitive power generation system, generation of a higher field is required. Toroidal Field (TF) coils of fusion DEMO plant at JAERI are required to generate magnetic field of 16 to 20 T. To realize this high field, advanced superconducting materials, such as Nb$$_3$$Al and high temperature superconductor (HTS), are considered. HTS has enough performance in a 20-T field at 4 K, and a forced-cooled type HTS conductor using a silver alloy sheathed Bi-2212 round wire has been proposed. Required areas of superconductor, structure, stabilizer, coolant and insulator in the cross section of coil winding have been calculated. However, there are many technical issues to be solved, such as accurate temperature control during heat treatment in an atmosphere of oxygen. On the other hand, a large coil using Nb$$_3$$Al has been developed by JAERI, and major technology to fabricate a 16-T Nb$$_3$$Al coil was developed. Validity and issues of grading the winding area are discussed, and there is a possibility to increase a field up to around 17 T using the method.

Journal Articles

Design study of fusion DEMO plant at JAERI

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Sato, Masayasu; Isono, Takaaki; Sakurai, Shinji; Nakamura, Hirofumi; Sato, Satoshi; Suzuki, Satoshi; Ando, Masami; et al.

Fusion Engineering and Design, 81(8-14), p.1151 - 1158, 2006/02

 Times Cited Count:111 Percentile:0.77(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Future prospect and issues of nuclear fusion power reactor, in case of the first wall

Kurihara, Ryoichi

Gijutsushi, (466), p.64 - 67, 2006/01

Research and development of nuclear fusion reactors have been internationally conducted to obtain the energy source in the middle of 21st century. The nuclear fusion reactor has safer characteristics than the nuclear fission reactor. But its structural materials are subjected many severe mechanical conditions such as very high temperature, 14MeV neutron flux. This paper describes the prospect and issues in the fusion power reactor design study from the point of view of the first wall.

Journal Articles

Nuclear power and radiation section

Onodera, Junichi; Kurihara, Ryoichi; Seki, Yasushi

Gijutsushi Ichiji Shiken No Keiko To Taisaku; Denki Denshi, Joho Kogaku, Genshiryoku, Hoshasen Bumon Hen, p.137 - 178, 2005/08

In 2004, "Nuclear Power and Radiation Section" has been established in the National Qualification of Professional Engineer. A reference material to help those who will take the preliminary examination is produced.

JAEA Reports

Integrity of the first wall in fusion reactors

Kurihara, Ryoichi

JAERI-Tech 2004-052, 39 Pages, 2004/07

JAERI-Tech-2004-052.pdf:2.1MB

The problems in the thermal structural design of the plasma facing component such as the blanket first wall and the divertor plate which receives very high heat flux were examined in the design of the fusion power reactors. Compact high fusion power reactor must give high heat flux and high-speed neutron flux from the plasma to the first wall and the divertor plate. In this environmental situation, the micro cracks should be generated in material of the first wall. Structural integrity of the first wall would be very low during the operation of the reactor, if those micro-cracks grow in a crack having significant size by the fatigue or the creep. The crack penetration in the first wall can be a factor which threatens the safety of the fusion power reactor. This paper summarizes the problems on the structural integrity in the first wall made of the SiC/SiC composite material or the ferritic steel.

JAEA Reports

Literature survey of thermal-hydraulic studies on super-critical pressurized water

Kurihara, Ryoichi; Watanabe, Kenichi*; Konishi, Satoshi

JAERI-Review 2003-020, 37 Pages, 2003/07

JAERI-Review-2003-020.pdf:2.08MB

no abstracts in English

Journal Articles

Thermofluid analysis of free surface liquid divertor in tokamak fusion reactor

Kurihara, Ryoichi

Fusion Engineering and Design, 61-62, p.209 - 216, 2002/11

 Times Cited Count:3 Percentile:75.07(Nuclear Science & Technology)

To attain high fusion power density, the divertor must suffer high heat flux from the fusion plasma. It is very difficult to remove a high heat flux more than 20 MW/m$$^{2}$$ using the only solid divertor plate from the viewpoint of severe mechanical state such as thermal stress and crack growth. Therefore, a concept of liquid divertor is proposed to remove high heat flux by liquid films flowing on a solid wall. This paper mainly descries a preliminary thermofluid analysis of the free surface liquid flow, made of the FliBe molten salt, using the finite element analysis code ADINA-F. The heat flux of 25$$sim$$100 MW/m$$^{2}$$ was given on the free surface liquid of the flow. I explored a possibility of applying the secondary flow to enhance the heat transfer of the liquid flow suffering high heat flux. This analysis shows that the heat flux of 100 MW/m$$^{2}$$ can be removed by inducing the secondary flow in the free surface liquid FLiBe. And this paper shows that the liquid divertor using solid-liquid multi-phase flow makes possible large heat removal by utilizing the latent heat of fusion of solid phase.

Journal Articles

Tritium issues toward fusion plants

Konishi, Satoshi; Tobita, Kenji; Nishio, Satoshi; Okada, Hidetoshi*; Kurihara, Ryoichi

Fusion Science and Technology, 41(3), p.817 - 820, 2002/05

no abstracts in English

Journal Articles

Design of the toroidal field coil for A-SSTR2 using high Tc superconductor

Ando, Toshinari; Kato, Takashi; Ushigusa, Kenkichi; Nishio, Satoshi; Kurihara, Ryoichi; Aoki, Isao; Hamada, Kazuya; Tsuji, Hiroshi; Hasegawa, Mitsuru*; Naito, Shuji*

Fusion Engineering and Design, 58-59, p.13 - 16, 2001/11

 Times Cited Count:9 Percentile:41.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical analysis on ingress of coolant event in vacuum vessel using modified TRAC-BF1

Kurihara, Ryoichi; Ajima, Toshio*; Ueda, Shuzo; Seki, Yasushi

Journal of Nuclear Science and Technology, 38(7), p.571 - 576, 2001/07

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fracture mechanics evaluation of a crack generated in SiC/SiC composite first wall

Kurihara, Ryoichi; Ueda, Shuzo; Nishio, Satoshi; Seki, Yasushi

Fusion Engineering and Design, 54(3-4), p.465 - 471, 2001/04

 Times Cited Count:10 Percentile:38.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal stress analyses in first wall subjected to high heat flux from fusion plasma

Kurihara, Ryoichi; Nishio, Satoshi; Konishi, Satoshi

Thermal Stresses 2001, p.81 - 84, 2001/00

no abstracts in English

57 (Records 1-20 displayed on this page)