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Journal Articles

First wall and divertor engineering research for power plant in JAERI

Suzuki, Satoshi; Ezato, Koichiro; Hirose, Takanori; Sato, Kazuyoshi; Yoshida, Hajime; Enoeda, Mikio; Akiba, Masato

Fusion Engineering and Design, 81(1-7), p.93 - 103, 2006/02

 Times Cited Count:13 Percentile:65.10(Nuclear Science & Technology)

This paper presents an R&D activity on the plasma facing components (PFCs), such as first wall and divertor, for the fusion power plant. The PFCs of the power plant will be subjected to heavy neutron irradiation and high heat/particle flux from plasma during the continuous operation. In the present design of the PFCs, the candidate structural material is a reduced activation ferritic-martensitic steel, F82H, from the viewpoints of low activation and high robustness against neutron irradiation, and the candidate armor material is tungsten from the low sputtering yield and low tritium retention points of view. To realize the PFCs using such materials, JAERI has bee extensively conducting R&Ds on; (1) high performance cooling tube, (2) tungsten armor materials, (3) selection of a bonding technique for F82H and tungsten materials and (4) evaluation of structural integrity. Recent achievements on these R&Ds are presented.

Journal Articles

ITER relevant high heat flux testing on plasma facing surfaces

Hirai, Takeshi*; Ezato, Koichiro; Majerus, P.*

Materials Transactions, 46(3), p.412 - 424, 2005/03

 Times Cited Count:112 Percentile:89.22(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of ITER divertor

Ezato, Koichiro

Koon Gakkai-Shi, 30(5), p.248 - 255, 2004/09

no abstracts in English

Journal Articles

Overview on materials R&D activities in Japan towards ITER construction and operation

Takatsu, Hideyuki; Sato, Kazuyoshi; Hamada, Kazuya; Nakahira, Masataka; Suzuki, Satoshi; Nakajima, Hideo; Kuroda, Toshimasa*; Nishitani, Takeo; Shikama, Tatsuo*; Shu, Wataru

Journal of Nuclear Materials, 329-333(1), p.178 - 182, 2004/08

 Times Cited Count:2 Percentile:16.97(Materials Science, Multidisciplinary)

This paper presents an overview on ITER-supporting materials research and development activities and major achievements in Japan during the period from the Co-ordinated Technical Activities to date. In view of the completed engineering design of ITER during the Engineering Design Activities period, research and development efforts since then have been focused: those for reduction of component fabrication cost; those in support of domestic preparations of a structural technical code for construction; those necessary for operation, and been extended to component-level testing rather than pure material testing. They cover materials Research and Development for in-vessel components, vacuum vessel, cryogenic steels of superconducting mgnet and diagnostics components. Major achievements in each research and development area are highlighted and their impact or implication to the design, construction and operation of ITER is presented.

Journal Articles

Progress of boundary plasma investigation toward ITER

Shimada, Michiya

Purazuma, Kaku Yugo Gakkai-Shi, 80(3), p.222 - 226, 2004/03

Discussion is made on objectives of edge plasma and plasma-wall interaction studies, divertor performance projection of ITER and key R&D issues on plasma-wall interaction including material issues, tritium retention, and transient events like ELMs and disruptions. A perspective of future development is discussed for the purpose of projection to and control of ITER plasma.

Journal Articles

Present research status on divertor and plasma facing components for fusion power plants

Suzuki, Satoshi; Ueda, Yoshio*; Tokunaga, Kazutoshi*; Sato, Kazuyoshi; Akiba, Masato

Fusion Science and Technology, 44(1), p.41 - 48, 2003/07

 Times Cited Count:30 Percentile:85.30(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Numerical simulation of runaway electron effect on plasma facing components

; ; Kunugi, Tomoaki*; Akiba, Masato

JAERI-Research 98-033, 35 Pages, 1998/07

JAERI-Research-98-033.pdf:1.37MB

no abstracts in English

Journal Articles

High heat flux component of ITER

; Akiba, Masato

Purazuma, Kaku Yugo Gakkai-Shi, 73(6), p.581 - 587, 1997/06

no abstracts in English

Journal Articles

Runaway electron effects

H.-W.Bartels*; Kunugi, Tomoaki; A.J.Russo*

Atomic and Plasma-Material Interaction Data for Fusion, Vol. 5, 0, p.225 - 244, 1994/00

no abstracts in English

JAEA Reports

Experimental and analytical studies of high heat flux components for Fusion Experimental Reactor

Araki, Masanori

JAERI-M 93-073, 132 Pages, 1993/03

JAERI-M-93-073.pdf:4.03MB

no abstracts in English

Journal Articles

Effects of runaway electrons on plasma facing components

Kunugi, Tomoaki

Fusion Engineering and Design, 23, p.329 - 339, 1993/00

 Times Cited Count:6 Percentile:52.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

10th Topical Meeting on the Technology of Fusion Energy,Boston,7-12,June,1992

; ; Seki, Yasushi

Purazuma, Kaku Yugo Gakkai-Shi, 68(5), p.511 - 515, 1992/11

no abstracts in English

Journal Articles

Thermal response of bonded CFC/OFHC divertor mock-ups for Fusion Experimental Reactors under large numbers of cyclic high heat loads

Araki, Masanori; Akiba, Masato; Dairaku, Masayuki; ; Ise, Hideo*; Seki, Masahiro; ;

Journal of Nuclear Science and Technology, 29(9), p.901 - 908, 1992/09

no abstracts in English

Journal Articles

The Simulation of the energy deposition from runaway electrons in plasma facing components with EGS4

Kunugi, Tomoaki; Akiba, Masato; Ogawa, Masuro; ;

Fusion Technology, 21, p.1868 - 1872, 1992/05

no abstracts in English

Journal Articles

Experimental and analytical results of carbon based materials under thermal shock heat loads for fusion application

Araki, Masanori; Akiba, Masato; Seki, Masahiro; Dairaku, Masayuki; Ise, Hideo*; Yamazaki, Seiichiro*; Tanaka, Shigeru;

Fusion Engineering and Design, 19, p.101 - 109, 1992/00

 Times Cited Count:15 Percentile:78.14(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental and analytical studies on thermal erosion of carbon-based materials with high thermal conductivity

Akiba, Masato; Araki, Masanori; ; Ise, Hideo*; Nakamura, Kazuyuki; ; Dairaku, Masayuki; Tanaka, Shigeru

Journal of Nuclear Materials, 191-194, p.373 - 376, 1992/00

no abstracts in English

Journal Articles

Entry-length effect on the thermal-hydraulic design of plasma-facing components of fusion reactors, Part II; MHD flow

M.Z.Hasan*; Kunugi, Tomoaki

Fusion Technology, 19, p.1030 - 1035, 1991/05

no abstracts in English

Journal Articles

Entry-length effect on the thermal-hydraulic design of plasma-facing components of fusion reactors, Part I; Non-MHD flow

Kunugi, Tomoaki; M.Z.Hasan*

Fusion Technology, 19, p.1024 - 1029, 1991/05

no abstracts in English

18 (Records 1-18 displayed on this page)
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