Local deformation analysis in martensite layer of high-strength multilayered steel composite using synchrotron X-ray diffraction

Ojima, Mayumi*; Shiro, Ayumi*; Suzuki, Hiroshi; Inoue, Junya*; Shobu, Takahisa; Xu, P. G.; Akita, Koichi; Nambu, Shoichi*; Koseki, Toshihiko*

Zairyo, 66(6), p.420 - 426, 2017/06

https://doi.org/10.2472/jsms.66.420

Conceptual design of the SlimCS fusion DEMO reactor

Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.

JAEA-Research 2010-019, 194 Pages, 2010/08

JAEA-Research-2010-019-01.pdf:48.47MB
JAEA-Research-2010-019-02.pdf:19.4MB

This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.

Compact DEMO, SlimCS; Design progress and issues

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.

Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07

https://doi.org/10.1088/0029-5515/49/7/075029

Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).

Microstructure evaluation of multilayered steel after tensile deformation

Xu, P. G.; Akita, Koichi; Suzuki, Hiroshi; Ojima, Mayumi*; Nambu, Shoichi*; Inoue, Junya*; Koseki, Toshihiko*

no journal, , 

Strain and texture evaluation of multilayered steel after tensile deformation

Xu, P. G.; Akita, Koichi; Suzuki, Hiroshi; Ojima, Mayumi*; Inoue, Junya*; Nambu, Shoichi*; Vogel, S. C.*; Koseki, Toshihiko*

no journal, , 

Distribution of strain in multilayered steel sheet during tensile deformation

Ojima, Mayumi*; Inoue, Junya*; Anto, Fuka*; Nambu, Shoichi*; Koseki, Toshihiko*; Xu, P. G.; Shiro, Ayumi; Akita, Koichi; Shobu, Takahisa; Suzuki, Hiroshi

no journal, , 

no abstracts in English