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.

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

no abstracts in English

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

http://ci.nii.ac.jp/naid/40018753361

no abstracts in English

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

http://ci.nii.ac.jp/naid/40017411146

no abstracts in English

Explanation of question and answer in special subject examination of the first test for professional engineer "nuclear and radiation" executed in 2006 fiscal year, Part 2; Nuclear section

Kurihara, Ryoichi

Genshiryoku eye, 53(4), p.62 - 66, 2007/04

http://ci.nii.ac.jp/naid/40015390418

no abstracts in English

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

https://doi.org/10.1016/j.fusengdes.2005.08.078

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 NbAl 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 NbAl has been developed by JAERI, and major technology to fabricate a 16-T NbAl 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.

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

Kurihara, Ryoichi

Gijutsushi, (466), p.64 - 67, 2006/01

http://www.engineer.or.jp/dept/nucrad/open/materials/kurihara2005.pdf

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.

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.

Thermofluid analysis of free surface liquid divertor in tokamak fusion reactor

Kurihara, Ryoichi

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

https://doi.org/10.1016/S0920-3796(02)00171-0

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 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 25100 MW/m 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 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.

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

https://doi.org/10.1016/S0920-3796(01)00467-7

no abstracts in English

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

https://doi.org/10.1016/S0920-3796(00)00567-6

no abstracts in English