Information on ITER project, 37

Ueno, Kenichi; Koizumi, Koichi; Moriyama, Setsuko

Purazuma, Kaku Yugo Gakkai-Shi, 89(1), P. 57, 2013/01

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2013_01/jspf2013_01-57.pdf

no abstracts in English

ITER technical term bilingual glossary year 2008 first half edition

Sato, Koichi; Seki, Fumiko*; Hasegawa, Shiori*; Sengoku, Akio; Kitazawa, Sin-iti; Neyatani, Yuzuru; Koizumi, Koichi

JAEA-Data/Code 2008-019, 43 Pages, 2008/09

JAEA-Data-Code-2008-019.pdf:1.17MB

On October 24th, 2007, the Agreement on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project (the "ITER Agreement") came into force, and Japan Atomic Energy Agency (JAEA) was appointed to a Domestic Agency (DA). The DA will contribute to the ITER construction in cooperation with ITER Organization (IO) where many ITER-specific technical terms and abbreviations were used. This book is a collection of those terms and abbreviations translated to Japanese.

Tensile and fatigue strength of a through-wall-electron-beam-welded joint for the vacuum vessel of a fusion reactor

Suzuki, Takayuki*; Usami, Saburo*; Kimura, Takae*; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Proceedings of 55th Annual Assembly of International Institute of Welding (IIW2002), 16 Pages, 2002/06

A new type of welded joint for the outer wall and rib of a double-walled vacuum vessel of a fusion reactor has been developed. The joint is manufactured by through-wall electron-beam welding (TW-EBW), in which the beam is injected from the outside of the outer wall. Static and fatigue tests are carried out on one-bead-specimens under an axial load and two-bead-specimens under a bending load. The experimental results are analytically investigated by FEM. Although this joint is partially penetrated, the net yield strength of the bead is increased by the plastic constraint due to triaxial tensile stress in the weldment. This phenomenon reduces the mean equivalent stress on the bead cross section, and the gross strength of the joint is close to that of a full thickness welded joint. The fatigue-strength reduction factor for low-cycle fatigue life is a little larger than four. The calculated fatigue-crack growth rate in the joint is conservatively calculated by using the maximum stress intensity factor of the crack and the fatigue-crack growth rate given in ASME Code Section XI.

Development of fabrication technology for ITER vacuum vessel

Nakahira, Masataka; Shibanuma, Kiyoshi; Kajiura, Soji*; Shibui, Masanao*; Koizumi, Koichi; Takeda, Nobukazu; Kakudate, Satoshi; Taguchi, Ko*; Oka, Kiyoshi; Obara, Kenjiro; et al.

JAERI-Tech 2002-029, 27 Pages, 2002/03

JAERI-Tech-2002-029.pdf:2.04MB

The ITER vacuum vessel (VV) R&D has progressed with the international collaborative efforts by the Japan, Russia and US Parties during the Engineering Design Activities (EDA). Fabrication and testing of a full-scale VV sector model and a port extension have yielded critical information on the fabrication and assembly technologies of the vacuum vessel, magnitude of welding distortions, dimensional accuracy and achievable tolerances during sector fabrication and field assembly. In particular, the dimensional tolerances of 3 mm for VV sector fabrication and 10 mm for VV sector field assembly have been achieved and satisfied the requirements of 5 mm and 20 mm, respectively. Also, the basic feasibility of the remote welding robot has been demonstrated. This report presents detailed fabrication and assembly technologies such as welding technology applicable to the thick wall without large distortion, field joint welding technology between sectors and remote welding technology through the VV R&D project.

Fatigue behavior on weldment of austenitic stainless steel for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Fusion Engineering and Design, 58-59, p.869 - 873, 2001/11

https://doi.org/10.1016/S0920-3796(01)00490-2

no abstracts in English

Fusion reactor technology; Challenge to future energy

Seki, Masahiro; Hishinuma, Akimichi; Kurihara, Kenichi; Akiba, Masato; Abe, Tetsuya; Ishitsuka, Etsuo; Imai, Tsuyoshi; Enoeda, Mikio; Ohira, Shigeru; Okumura, Yoshikazu; et al.

Kaku Yugoro Kogaku Gairon; Mirai Enerugi Eno Chosen, 246 Pages, 2001/09

no abstracts in English

Progress and achievements on the R&D activities for ITER vacuum vessel

Nakahira, Masataka; Takahashi, Hiroyuki*; Koizumi, Koichi; Onozuka, Masanori*; Ioki, Kimihiro*

Nuclear Fusion, 41(4), p.375 - 380, 2001/04

https://doi.org/10.1088/0029-5515/41/4/303

no abstracts in English

Fusion technology development for ITER in JAERI

Seki, Masahiro; Tsuji, Hiroshi; Ohara, Yoshihiro; Akiba, Masato; Okumura, Yoshikazu; Imai, Tsuyoshi; Nishi, Masataka; Koizumi, Koichi; Takeuchi, Hiroshi

Fusion Technology, 39(2-Part.2), p.367 - 373, 2001/03

no abstracts in English

Development of colored alumilite dosimeter for high radiation use

Obara, Kenjiro; Tada, Eisuke; Koizumi, Koichi; Yagi, Toshiaki; Morita, Yosuke

Proceedings of Radiation Effects on Components and Systems (RADECS 2000), p.214 - 218, 2000/09

no abstracts in English

Basic experiments for the mechanically attached blanket module installation by the ITER remote vehicle-type manipulator

Yoshimi, Takashi*; Kakudate, Satoshi; Oka, Kiyoshi; Hiyama, Masayuki; Taguchi, Ko*; Shibanuma, Kiyoshi; Koizumi, Koichi

Robotikusu, Mekatoronikusu Koenkai '00 Koen Rombunshu, (2P2-11-006), p.1 - 2, 2000/05

no abstracts in English