Nuclear energy (Technical topic); Development of ITER toroidal field (TF) coil

Hemmi, Tsutomu; Kajitani, Hideki; Takano, Katsutoshi; Matsui, Kunihiro; Koizumi, Norikiyo

Yosetsu Gakkai-Shi, 83(6), p.497 - 502, 2014/09

https://doi.org/10.2207/jjws.83.497

JAEA, serving as the Japan Domestic Agency (JADA) in the ITER project, is responsible for the procurement of 9 TF coils. In the TF coil, the radial plate (RP) structure is selected to improve electrical and mechanical reliability of the electrical insulation. Since the superconductor is degraded by the bending strain of 0.1% after the reaction heat-treatment, the conductor is inserted into the RP after winding to D-shape and the heat-treatment. To insert the conductor into the RP, the winding and RP groove length must be controlled with accuracy of 0.02% (7 mm on the 1 turn of 34 m). Accordingly, the targets for solving this issue are as follows: (1) Development of manufacturing procedure of the RP; (2) Development of winding head to achieve highly accurate winding; (3) Estimation of the conductor elongation after the heat-treatment. Therefore, JAEA can establish manufacturing plan for the TF coil as a result of the R&D for these targets.

Developments of direct bonded laser crystals

Sugiyama, Akira

Yosetsu Gakkai-Shi, 75(3), p.175 - 179, 2006/04

http://ci.nii.ac.jp/naid/40007293205

Laser applications, with respect to short laser pulse interaction with matter, have been widely investigated not only in scientific but also industrial fields. To realize such kind of laser applications, high-heat-removal laser crystals are indispensable to reduce thermal load caused by the intense optical pumping of laser diode arrays. For the establishment of high-heat-removal laser crystals, the study of laser crystal bonding in the atomic layer level without the use of adhesives has been strongly required. In this report, our originally developed direct bonding methods, the magnified inspection for the bonded area, and optical performance of the bonded crystals are described in detail.

Status of fusion reactor development; Especially on reactor wall and high heat flux

Yosetsu Gakkai-Shi, 56(3), p.162 - 171, 1987/03

http://ci.nii.ac.jp/naid/110003403113

no abstracts in English

Annual review of nuclear engineering 1971

Yosetsu Gakkai-Shi, 42(5), p.71 - 72, 1973/05

http://ci.nii.ac.jp/naid/110003392268

no abstracts in English

Some Problems of Overlaid Cladding in a Nuclear Reactor Pressure Vessel, Report 2 ; Metallurgical Studies on Overlaid Cladding of a Reactor Pressure Vessel

; ;

Yosetsu Gakkai-Shi, 41(12), p.1402 - 1409, 1972/00

http://ci.nii.ac.jp/naid/110003391892

no abstracts in English

Neutro Irradiation Test on Reactor Pressure Vessel Steel (A302B Steel) Weldment

; ;

Yosetsu Gakkai-Shi, 38(6), p.608 - 614, 1969/00

http://ci.nii.ac.jp/naid/110003391181

no abstracts in English

A view of the welding technology in Japan; Nuclear power

Yosetsu Gakkai-Shi, 34(5), p.493 - 495, 1965/00

http://ci.nii.ac.jp/naid/110003402439

no abstracts in English

Apparatus and sunface tension on Sn-Pb alloy system

;

Yosetsu Gakkai-Shi, 33(6), p.458 - 461, 1964/00

http://ci.nii.ac.jp/naid/110003389396

no abstracts in English

Studies on the porosity in welding joints, 3rd report; Results of experimental welding

; ; Ando, Yoshio*

Yosetsu Gakkai-Shi, 31(12), p.980 - 985, 1962/00

http://ci.nii.ac.jp/naid/110003402345

no abstracts in English

Studies on the porosity in welding joints, 1; Relation between welding procedure and results of gas analysis in aluminium alloy

Ando, Yoshio*; ;

Yosetsu Gakkai-Shi, 29(4), p.326 - 332, 1960/00

https://doi.org/10.2207/qjjws1943.29.326

no abstracts in English