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Journal Articles

Neutronics design of the low aspect ratio tokamak reactor, VECTOR

Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*

Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.09.059

Times Cited Count：13 Percentile：65.77(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutron shielding and blanket neutronics study on low aspect ratio tokamak reactor

Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi

Denki Gakkai Rombunshi, A, 125(11), p.943 - 946, 2005/11

https://doi.org/10.1541/ieejfms.125.943

Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.

Journal Articles

Development of fabrication technology of ITER shielding blanket

Enoeda, Mikio

Koon Gakkai-Shi, 30(5), p.256 - 262, 2004/09

http://ci.nii.ac.jp/naid/10029252387

Fabrication technologies for ITER in-vessel components, especially the shielding blanket with the separable first wall panel has been developed. Hot Isostatic Pressing (HIP) has been applied to the bonding of Cu-alloy/stainless steel and beryllium/Cu-alloy. First wall mock-ups fabricated by using HIP were tested under high heat fluxes and showed sufficient heat removal and thermal fatigue performance. Water jet and electrical discharge machining have been applied to manufacture slots into the first wall panel and the shield block. With these technologies, a first wall panel prototype and a shielding block 1/2 mock-up were successfully fabricated.

JAEA Reports

Fabrication of the full scale separable first wall of ITER shielding blanket

Kosaku, Yasuo; Kuroda, Toshimasa*; Hatano, Toshihisa; Enoeda, Mikio; Miki, Nobuharu*; Akiba, Masato

JAERI-Tech 2002-078, 58 Pages, 2002/10

JAERI-Tech-2002-078.pdf:19.38MB

Shielding blanket for ITER-FEAT applies the unique first wall structure which is separable from the shield block for the purpose of radio-active waste reduction in the maintenance work and cost reduction in fabrication process. Also, it is required to have various types of slots in both of the first wall and the shield block, to reduce the eddy current for reduction of electro-magnetic force in disruption events. This report summarizes the achievement of such R&Ds as, slit grooving techniques for Be/DSCu/SS first wall panel and SS shield block, demonstration of Be armor joining to the real scal first wall panel, and demonstration of full scale first wall panel.

JAEA Reports