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Journal Articles

Mechanical properties of small size specimens of F82H steel

Wakai, Eiichi; Otsuka, Hideo*; Matsukawa, Shingo; Furuya, Kazuyuki*; Tanigawa, Hiroyasu; Oka, Keiichiro*; Onuki, Somei*; Yamamoto, Toshio*; Takada, Fumiki; Jitsukawa, Shiro

Fusion Engineering and Design, 81(8-14), p.1077 - 1084, 2006/02

 Times Cited Count:11 Percentile:59.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of sequential charged particle reaction experiments for fusion reactors

Yamauchi, Michinori*; Hori, Junichi*; Ochiai, Kentaro; Sato, Satoshi; Nishitani, Takeo; Kawasaki, Hiromitsu*

Fusion Engineering and Design, 81(8-14), p.1577 - 1582, 2006/02

 Times Cited Count:1 Percentile:9.80(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of FEMAG; Calculation code of magnetic field generated by ferritic plates in the tokamak devices

Urata, Kazuhiro*

JAERI-Data/Code 2003-005, 36 Pages, 2003/03

JAERI-Data-Code-2003-005.pdf:2.96MB

In design of the fusion devises in which ferritic steel is planned to use as the plasma facing material and/or the inserts for ripple reduction, the appreciation of the error field effect and the optimization of ferritic plate arrangement to reduce the toroidal field ripple require calculation of ferritic magnetic field. However iterative calculations by the non-linearity in B-H curve disturbs high-speed calculation. In the strong toroidal magnetic field in the tokamak, fully magnetic saturation of ferritic steel occurs. Hence a distribution of magnetic charges as magnetic field source is determined straightforward. Additionally objective ferritic steel geometry is limited to the thin plate and they are installed along the toroidal magnetic field. Taking them into account, high-speed calculation code FEMAG has been developed. In this report, the formalization of FEMAG, how to use FEMAG, and the validity check in comparison with a 3D FEM code, with the measurements of the magnetic field in JFT-2M are described. The presented examples are design studies for JT-60 modification.

Journal Articles

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

Jitsukawa, Shiro; Tamura, Manabu*; Van der Schaaf, B.*; Klueh, R. L.*; Alamo, A.*; Petersen, C.*; Schirra, M.*; Spaetig, P.*; Odette, G. R.*; Tavassoli, A. A.*; et al.

Journal of Nuclear Materials, 307-311(Part1), p.179 - 186, 2002/12

 Times Cited Count:170 Percentile:99.28(Materials Science, Multidisciplinary)

Reduced activation ferritic/martensitic steel is the primary candidate structural material for ITER Test Blanket Modules and DEMOnstration fusion reactor because of its excellent dimensional stability under irradiation and lower residual activity as compared with the Ni bearing steels such as the austenitic stainless steels. In this paper, microstructural features, tensile, fracture toughness, creep and fatigue properties of a reduced activation martensitic steel F82H (8Cr-2W-0.04Ta-0.1C) are reported before and after irradiation, in addition to the design concept used for development of this alloy. A large number of collaborative test results including those generated under the IEA working group implementing agreements are collected and are used to evaluate the feasibility of use of F82H steel as one of the reference alloys. The effect of metallurgical variables on the irradiation hardening is reviewed and compared with the results obtained from irradiation experiments.

Journal Articles

Composition adjustment of low activation materials for shallow land burial

Seki, Yasushi; Tabara, Takashi*; Aoki, Isao; Ueda, Shuzo; Nishio, Satoshi; Kurihara, Ryoichi

Fusion Engineering and Design, 48(3-4), p.435 - 441, 2000/09

 Times Cited Count:1 Percentile:11.91(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of activation cross section change on the shallow land burial fraction of low activation materials for fusion reactors

Seki, Yasushi; Aoki, Isao; Ueda, Shuzo; Nishio, Satoshi; Kurihara, Ryoichi; Tabara, Takashi*

Fusion Technology, 34(3), p.353 - 357, 1998/11

no abstracts in English

Journal Articles

Tokamak reactor assessments in Europe:SEAFP/SEAL

Seki, Yasushi

Purazuma, Kaku Yugo Gakkai-Shi, 74(9), p.939 - 943, 1998/09

no abstracts in English

Journal Articles

Social acceptability and scientific prospect of fusion energy, 7; Safety

Seki, Yasushi

Purazuma, Kaku Yugo Gakkai-Shi, 74(8), p.795 - 801, 1998/08

no abstracts in English

JAEA Reports

Concept study of the Steady State Tokamak Reactor(SSTR)

JAERI-M 91-081, 607 Pages, 1991/06

JAERI-M-91-081.pdf:15.66MB

no abstracts in English

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