Abstract
An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement achieved in LHD, a maximum magnetic field around 13 T with a current density around 30 A/mm2 and a neutron wall loading around 1.5 MW/m2. R&D on super-conducting magnet systems of large scale, high field and high current-density are new challenging targets based on the LHD. The development of new design tools has been started aiming at establishing a virtual power plant (VPP) and a virtual reality system for 3D design assisting. Next design issues are mainly on engineering optimization of the first wall thickness, the detailed 3D blanket system, and unscheduled replacements of breeder blankets.
| Original language | English |
|---|---|
| Pages (from-to) | 2703-2712 |
| Number of pages | 10 |
| Journal | Fusion Engineering and Design |
| Volume | 81 |
| Issue number | 23-24 |
| DOIs | |
| Publication status | Published - Nov 1 2006 |
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All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Cite this
Conceptual design activities and key issues on LHD-type reactor FFHR. / Sagara, A.; Mitarai, O.; Imagawa, S.; Morisaki, T.; Tanaka, T.; Mizuguchi, N.; Dolan, T.; Miyazawa, J.; Takahata, K.; Chikaraishi, H.; Yamada, S.; Seo, K.; Sakamoto, R.; Masuzaki, S.; Muroga, T.; Yamada, H.; Fukada, Satoshi; Hashizume, H.; Yamazaki, K.; Mito, T.; Kaneko, O.; Mutoh, T.; Ohyabu, N.; Noda, N.; Komori, A.; Sudo, S.; Motojima, O.
In: Fusion Engineering and Design, Vol. 81, No. 23-24, 01.11.2006, p. 2703-2712.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Conceptual design activities and key issues on LHD-type reactor FFHR
AU - Sagara, A.
AU - Mitarai, O.
AU - Imagawa, S.
AU - Morisaki, T.
AU - Tanaka, T.
AU - Mizuguchi, N.
AU - Dolan, T.
AU - Miyazawa, J.
AU - Takahata, K.
AU - Chikaraishi, H.
AU - Yamada, S.
AU - Seo, K.
AU - Sakamoto, R.
AU - Masuzaki, S.
AU - Muroga, T.
AU - Yamada, H.
AU - Fukada, Satoshi
AU - Hashizume, H.
AU - Yamazaki, K.
AU - Mito, T.
AU - Kaneko, O.
AU - Mutoh, T.
AU - Ohyabu, N.
AU - Noda, N.
AU - Komori, A.
AU - Sudo, S.
AU - Motojima, O.
PY - 2006/11/1
Y1 - 2006/11/1
N2 - An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement achieved in LHD, a maximum magnetic field around 13 T with a current density around 30 A/mm2 and a neutron wall loading around 1.5 MW/m2. R&D on super-conducting magnet systems of large scale, high field and high current-density are new challenging targets based on the LHD. The development of new design tools has been started aiming at establishing a virtual power plant (VPP) and a virtual reality system for 3D design assisting. Next design issues are mainly on engineering optimization of the first wall thickness, the detailed 3D blanket system, and unscheduled replacements of breeder blankets.
AB - An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement achieved in LHD, a maximum magnetic field around 13 T with a current density around 30 A/mm2 and a neutron wall loading around 1.5 MW/m2. R&D on super-conducting magnet systems of large scale, high field and high current-density are new challenging targets based on the LHD. The development of new design tools has been started aiming at establishing a virtual power plant (VPP) and a virtual reality system for 3D design assisting. Next design issues are mainly on engineering optimization of the first wall thickness, the detailed 3D blanket system, and unscheduled replacements of breeder blankets.
UR - http://www.scopus.com/inward/record.url?scp=33846025772&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=33846025772&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2006.07.057
DO - 10.1016/j.fusengdes.2006.07.057
M3 - Article
AN - SCOPUS:33846025772
VL - 81
SP - 2703
EP - 2712
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - 23-24
ER -