Plasma domains and development of operation scenarios in JT-60SA

Ide, Shunsuke; Hayashi, Nobuhiko; Honda, Mitsuru; Urano, Hajime; Suzuki, Takahiro; Miyata, Yoshiaki; Aiba, Nobuyuki; Shiraishi, Junya; Kurita, Genichi; Fujita, Takaaki

Plasma and Fusion Research (Internet), 7(Sp.1), p.2403131_1 - 2403131_4, 2012/09

https://doi.org/10.1585/pfr.7.2403131

no abstracts in English

Estimation of decay heat in fusion DEMO reactor

Someya, Yoji; Tobita, Kenji

Plasma and Fusion Research (Internet), 7(Sp.1), p.2405066_1 - 2405066_4, 2012/07

https://doi.org/10.1585/pfr.7.2405066

Decay heat of activated materials is important in safety of fusion DEMO reactor. Effects of decay heat for main components of the SlimCS DEMO reactor are studied. The main reactor components consist of the inboard (IB) and outboard (OB) blanket modules, and divertor. The decay heats of IB blanket, OB blanket and divertor are calculated by a design code for radioactive, ACT-4. The dominant radioactive nuclide determining the decay heat is short-lived nuclide at the immediately after the shutdown of operation. Therefore, the decay heat depends in a large part on neutron flux after the shout down. On the other hand, the dominant reaction determining the decay heat is (n, ) reaction. When thermal neutron is decreased, the decay heat is decreased in the blanket and divertor. Methods of reducing the decay heat are (1) decreased thermal neutron and (2) decreased the fusion power. Finally, a detailed estimation of between (1) and (2) is discussed from view point of fusion DEMO reactor.

Analysis of ECRH pre-ionization for plasma start-up in JT-60SA

Hada, Kazuyoshi*; Nagasaki, Kazunobu*; Masuda, Kai*; Kinjo, Ryota*; Ide, Shunsuke; Isayama, Akihiko

Plasma and Fusion Research (Internet), 7(Sp.1), p.2403104_1 - 2403104_5, 2012/07

https://doi.org/10.1585/pfr.7.2403104

no abstracts in English

Recent results from the development of the electron cyclotron heating system for JT-60SA toward high-power long-pulse operations

Isayama, Akihiko; Kobayashi, Takayuki; Yokokura, Kenji; Shimono, Mitsugu; Sawahata, Masayuki; Suzuki, Sadaaki; Terakado, Masayuki; Hiranai, Shinichi; Wada, Kenji; Hinata, Jun; et al.

Plasma and Fusion Research (Internet), 7(Sp.1), p.2405029_1 - 2405029_5, 2012/05

http://www.jspf.or.jp/PFR/PFR_articles/pfr2012S1/pfr2012_07-2405029.html

no abstracts in English

Neutron diffraction study of internal strain in NbSn Cable-In-Conduit Conductors

Hemmi, Tsutomu; Harjo, S.; Nunoya, Yoshihiko; Kajitani, Hideki; Koizumi, Norikiyo; Nakajima, Hideo; Aizawa, Kazuya; Machiya, Shutaro*; Osamura, Kozo*

no journal, , 

Internal strain in Cable-In-Conduit Conductors (CICC) is caused by differences in the coefficients of thermal expansion between NbSn strands and the stainless steel jacket over a temperature range of 5 - 923 K. In addition, transverse electromagnetic loading is generated by a current of 68 kA and a magnetic field of 11.8 T in the case of ITER TF coils. The performances of NbSn strands change significantly, depending on the presence of strain. The presence of internal strain in NbSn cables is important to evaluate the superconducting performance. However, the strain of strands in the conductor has not been measured so far because of the cabling configuration and their location in a jacket. Internal strain can be determined by neutron diffraction measurement using Takumi of J-PARC. Test results of the neutron diffraction and the role of the neutron diffraction measurement for the investigation of Tcs degradation of short conductor sample will be presented and discussed.

Proposal of new type diplexer for ECCD system

Saigusa, Mikio*; Sugawara, Shuhei*; Atsumi, Kohei*; Oda, Yasuhisa; Yamaguchi, Tomoki*; Sakamoto, Keishi

no journal, ,