TY - JOUR
T1 - Optimization activities on design studies of LHD-type reactor FFHR
AU - Sagara, A.
AU - Mitarai, O.
AU - Tanaka, T.
AU - Imagawa, S.
AU - Kozaki, Y.
AU - Kobayashi, M.
AU - Morisaki, T.
AU - Watanabe, T.
AU - Takahata, K.
AU - Tamura, H.
AU - Yanagi, N.
AU - Nishimura, K.
AU - Chikaraishi, H.
AU - Yamada, S.
AU - Fukada, S.
AU - Masuzaki, S.
AU - Shishkin, A.
AU - Igitkhanov, Y.
AU - Goto, T.
AU - Ogawa, Y.
AU - Muroga, T.
AU - Mito, T.
AU - Motojima, O.
PY - 2008/12
Y1 - 2008/12
N2 - Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three candidates to secure the blanket space are proposed with the aim of reactor size optimization without deteriorating α-heating efficiency and by taking cost analyses into account. In this way the key engineering aspects are investigated; from 3D blanket designs, it is demonstrated that the peaking factor of the neutron wall loading is 1.2-1.3 and a blanket covering ratio of over 90% is possible by proposing discrete pumping with a semi-closed shield (DPSS) concept. Helical blanket shaping along the divertor field lines is the next big issue. For large superconducting magnet systems under the maximum nuclear heating of 200 W/m3, cable-in-conduit conductor (CICC) and alternative conductor designs are proposed with a robust design of cryogenic support posts. For access to ignited plasmas, new methods are proposed, in which a long rise-up time over 300 s reduces the heating power to 30 MW and a new proportional-integration-derivative (PID) control of the fueling can handle the thermally unstable plasma at high-density operation. This paper focuses on FFHR2m1, which is a modified version of FFHR.
AB - Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three candidates to secure the blanket space are proposed with the aim of reactor size optimization without deteriorating α-heating efficiency and by taking cost analyses into account. In this way the key engineering aspects are investigated; from 3D blanket designs, it is demonstrated that the peaking factor of the neutron wall loading is 1.2-1.3 and a blanket covering ratio of over 90% is possible by proposing discrete pumping with a semi-closed shield (DPSS) concept. Helical blanket shaping along the divertor field lines is the next big issue. For large superconducting magnet systems under the maximum nuclear heating of 200 W/m3, cable-in-conduit conductor (CICC) and alternative conductor designs are proposed with a robust design of cryogenic support posts. For access to ignited plasmas, new methods are proposed, in which a long rise-up time over 300 s reduces the heating power to 30 MW and a new proportional-integration-derivative (PID) control of the fueling can handle the thermally unstable plasma at high-density operation. This paper focuses on FFHR2m1, which is a modified version of FFHR.
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U2 - 10.1016/j.fusengdes.2008.07.029
DO - 10.1016/j.fusengdes.2008.07.029
M3 - Article
AN - SCOPUS:57049164236
VL - 83
SP - 1690
EP - 1695
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - 10-12
ER -