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Physics and operation oriented activities in preparation of the JT-60SA tokamak exploitation

Autor: H. Sasao, T. Bolzonella, D. C. McDonald, Lorenzo Figini, Peter Lang, A. Boboc, G. Pautasso, R. Neu, V. Vitale, J.F. Artaud, G. De Tommasi, C. Gil, A. Kojima, Akihiko Isayama, S. Saarelma, Patrick Maget, Yasunori Kawano, Y. Miyata, L. Pigatto, Carlo Sozzi, Timothy Goodman, Paolo Bettini, David Terranova, M. Romanelli, B. Pégourié, E. de la Luna, Manabu Takechi, K. Galazka, Maiko Yoshida, F. Orsitto, A. Mele, J. Garcia, J. Galdon, Ryota Imazawa, Paola Platania, S. Clement-Lorenzo, Hajime Urano, Go Matsunaga, W. Stepniewski, M. Enoeda, Hisato Kawashima, L. Garzotti, Masakatsu Fukumoto, M. Toma, Daniela Farina, Kazuo Hoshino, S. Soare, M. Scannapiego, Yutaka Kamada, S. Sakurai, Paolo Innocente, K. Shinohara, M. Dibon, H. Kubo, R. Zagórski, S. Mastrostefano, O. Asztalos, D. Ricci, K. Itami, Stefano Coda, T. Kobayashi, Gergö Pokol, Daniel Dunai, Kenji Tanaka, A. Moro, Giuseppe Marchiori, C. Gleason-González, S. Nowak, Tamás Szepesi, Chr. Day, N. Hayashi, Filippo Sartori, Ph. Lauber, Jesús Vega, D. Douai, T. Nakano, K. Shimizu, E. Barbato, Nuno Cruz, G. Giruzzi, Shunsuke Ide, M. Wischmeier, Alfredo Pironti, Fabio Villone, Shinichi Moriyama, Kensaku Kamiya, M. Garcia-Munoz, Massimiliano Mattei, E. Joffrin, J. Shiraishi, T. Suzuki, Gustavo Granucci, T. Wakatsuki, Andreas Bierwage, Y. Suzuki

Publikováno v: Nuclear Fusion
Nuclear fusion (Online) 57 (2017): 085001-1–085001-21. doi:10.1088/1741-4326/aa7962
info:cnr-pdr/source/autori:Giruzzi G.; Yoshida M.; Artaud J.F.; Asztalos O.; Barbato E.; Bettini P.; Bierwage A.; Boboc A.; Bolzonella T.; Clement-Lorenzo S.; Coda S.; Cruz N.; Day C.; De Tommasi G.; Dibon M.; Douai D.; Dunai D.; Enoeda M.; Farina D.; Figini L.; Fukumoto M.; Galazka K.; Galdon J.; Garcia J.; Garcia-Munoz M.; Garzotti L.; Gil C.; Gleason-Gonzalez C.; Goodman T.; Granucci G.; Hayashi N.; Hoshino K.; Ide S.; Imazawa R.; Innocente P.; Isayama A.; Itami K.; Joffrin E.; Kamada Y.; Kamiya K.; Kawano Y.; Kawashima H.; Kobayashi T.; Kojima A.; Kubo H.; Lang P.; Lauber P.; De La Luna E.; Maget P.; Marchiori G.; Mastrostefano S.; Matsunaga G.; Mattei M.; McDonald D.C.; Mele A.; Miyata Y.; Moriyama S.; Moro A.; Nakano T.; Neu R.; Nowak S.; Orsitto F.P.; Pautasso G.; Pegourie B.; Pigatto L.; Pironti A.; Platania P.; Pokol G.I.; Ricci D.; Romanelli M.; Saarelma S.; Sakurai S.; Sartori F.; Sasao H.; Scannapiego M.; Shimizu K.; Shinohara K.; Shiraishi J.; Soare S.; Sozzi C.; Stepniewski W.; Suzuki T.; Suzuki Y.; Szepesi T.; Takechi M.; Tanaka K.; Terranova D.; Toma M.; Urano H.; Vega J.; Villone F.; Vitale V.; Wakatsuki T.; Wischmeier M.; Zagorski R./titolo:Physics and operation oriented activities in preparation of the JT-60SA tokamak exploitation/doi:10.1088%2F1741-4326%2Faa7962/rivista:Nuclear fusion (Online)/anno:2017/pagina_da:085001-1/pagina_a:085001-21/intervallo_pagine:085001-1–085001-21/volume:57
idUS. Depósito de Investigación de la Universidad de Sevilla
instname
idUS: Depósito de Investigación de la Universidad de Sevilla
Universidad de Sevilla (US)
Nuclear fusion, 57 (8), Art. Nr. 085001

The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2020 and is expected to give substantial contributions to both ITER and DEMO scenario optimisation. A broad set of prepara

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cc560aa376430f92829628557ba4627c

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Physics and operation oriented activities in preparation of the JT-60SA tokamak exploitation

Autor: Giruzzi G., M. Yoshida, J.F. Artaud, E. Barbato, P. Bettini, A. Bierwage, A. Boboc, T. Bolzonella, S. Clement-Lorenzo, S. Coda, N. Cruz, Chr. Day, G. De Tommasi, M. Dibon, D. Douai, D. Dunai, M. Enoeda, L. Figini, M. Fukumoto, K. Galazka, J. Galdon, J. Garcia, M. Garcia-Muñoz, L. Garzotti, C. Gleason-Gonzalez, T. Goodman, G. Granucci, N. Hayashi, K. Hoshino, S. Ide, P. Innocente, A. Isayama, E. Joffrin, Y. Kamada, K. Kamiya, H. Kawashima, T. Kobayashi, A. Kojima, H. Kubo, P. Lang, Ph. Lauber, E. de la Luna, P. Maget, S. Mastrostefano, G. Matsunaga, M. Mattei, D.C. McDonald, A. Mele, Y. Miyata, S. Moriyama, A. Moro, T. Nakano, R. Neu, S. Nowak, F.P. Orsitto, G. Pautasso, B. Pégourié, L. Pigatto, A. Pironti, P. Platania, D. Ricci, M. Romanelli, S. Saarelma, S. Sakurai, F. Sartori, M. Scannapiego, K. Shimizu, K. Shinohara, J. Shiraishi, S. Soare, C. Sozzi, W. Stepniewski, T. Suzuki, Y. Suzuki, T. Szepesi, M. Takechi, K. Tanaka, D. Terranova, M. Toma, H. Urano, J. Vega, F. Villone, V. Vitale, T. Wakatsuki, M. Wischmeier, R. Zagórski

Publikováno v: 26th IAEA Fusion Energy Conference, Kyoto, Japan, 17-22 October 2016
info:cnr-pdr/source/autori:Giruzzi G.; M. Yoshida; J.F. Artaud; E. Barbato; P. Bettini; A. Bierwage; A. Boboc; T. Bolzonella; S. Clement-Lorenzo; S. Coda; N. Cruz; Chr. Day; G. De Tommasi; M. Dibon; D. Douai; D. Dunai; M. Enoeda; L. Figini; M. Fukumoto; K. Galazka; J. Galdon; J. Garcia; M. Garcia-Muñoz; L. Garzotti; C. Gleason-Gonzalez; T. Goodman; G. Granucci; N. Hayashi; K. Hoshino; S. Ide; P. Innocente; A. Isayama; E. Joffrin; Y. Kamada; K. Kamiya; H. Kawashima; T. Kobayashi; A. Kojima; H. Kubo; P. Lang; Ph. Lauber; E. de la Luna; P. Maget; S. Mastrostefano; G. Matsunaga; M. Mattei; D.C. McDonald; A. Mele; Y. Miyata; S. Moriyama; A. Moro; T. Nakano; R. Neu; S. Nowak; F.P. Orsitto; G. Pautasso; B. Pégourié; L. Pigatto; A. Pironti; P. Platania; D. Ricci; M. Romanelli; S. Saarelma; S. Sakurai; F. Sartori; M. Scannapiego; K. Shimizu; K. Shinohara; J. Shiraishi; S. Soare; C. Sozzi; W. Stepniewski; T. Suzuki; Y. Suzuki; T. Szepesi; M. Takechi; K. Tanaka; D. Terranova; M. Toma; H. Urano; J. Vega; F. Villone; V. Vitale; T. Wakatsuki; M. Wischmeier; R. Zagórski/congresso_nome:26th IAEA Fusion Energy Conference/congresso_luogo:Kyoto, Japan/congresso_data:17-22 October 2016/anno:2016/pagina_da:/pagina_a:/intervallo_pagine

The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2019 and is expected to give substantial contributions to both ITER and DEMO scenario optimization. A broad set of prepara

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=cnr_________::22450c179ab0feee3cd5d7892d368b9b
http://www.cnr.it/prodotto/i/368302

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Torus configuration and materials selection on a fusion DEMO reactor, SlimCS

Autor: K. Tobita, S. Nishio, H. Tanigawa, M. Enoeda, T. Isono, H. Nakamura, D. Tsuru, S. Suzuki, T. Hayashi, K. Tsuchiya, T. Nishitani

Publikováno v: Journal of Nuclear Materials. :888-892

SlimCS is the conceptual design of a compact fusion DEMO plant assuming technologies foreseeable in 2020–2030s. For continuity of blanket technology from the Japanese ITER-TBM, the prime option of blanket is water-cooled solid breeder with Li 2 TiO

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::751c3e375989bf7d7b508d8450d174bf
https://doi.org/10.1016/j.jnucmat.2008.12.197

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SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid

Autor: K Tobita, S Nishio, M Sato, S Sakurai, T Hayashi, Y.K Shibama, T Isono, M Enoeda, H Nakamura, S Sato, K Ezato, T Hirose, S Ide, T Inoue, Y Kamada, Y Kawamura, H Kawashima, N Koizumi, G Kurita, Y Nakamura, K Mouri, T Nishitani, J Ohmori, N Oyama, K Sakamoto, S Suzuki, T Suzuki, H Tanigawa, K Tsuchiya, D Tsuru

Publikováno v: Nuclear Fusion. 47:892-899

The concept for a compact DEMO reactor named 'SlimCS' is presented. Distinctive features of the concept are low aspect ratio (A = 2.6) and use of a reduced-size centre solenoid (CS) which has the function of plasma shaping rather than poloidal flux s

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ee9390aca79fa105c5f45dc232252356
https://doi.org/10.1088/0029-5515/47/8/022

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Design study of fusion DEMO plant at JAERI

Publikováno v: Fusion Engineering and Design. 81:1151-1158

Three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9cafc2accf505db8fb4afbaa77b9b73e
https://doi.org/10.1016/j.fusengdes.2005.08.058

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ITER test-blanket safety assessment

Autor: M. Fütterer, H.-W. Bartels, K. McCarthy, M. Enoeda, K. Kleefeldt

Publikováno v: Fusion Engineering and Design. 54:331-336

One of the missions of the International Thermonuclear Experimental Reactor (ITER) project is to serve as a test bed for various test blanket concepts. Part of the design for these test modules is to assess their impact on the safety of ITER. This pa

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d2ffce505da51c2ab0da792989997600
https://doi.org/10.1016/s0920-3796(00)00565-2

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Improvement of tritium accountancy technology for ITER fuel cycle safety enhancement

Autor: S O'hira, T Hayashi, H Nakamura, K Kobayashi, T Tadokoro, T Itoh, T Yamanishi, Y Kawamura, Y Iwai, T Arita, T Maruyama, T Kakuta, S Konishi, M Enoeda, M Yamada, T Suzuki, M Nishi, T Nagashima, M Ohta

Publikováno v: Nuclear Fusion. 40:519-525

In order to improve the safe handling and control of tritium for the ITER fuel cycle, effective in situ tritium accounting methods have been developed at the Tritium Process Laboratory in the Japan Atomic Energy Research Institute under one of the IT

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4bbd78df4fbdc5e4525d796abff07918
https://doi.org/10.1088/0029-5515/40/3y/312

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Development of a tritium fuel processing system using an electrolytic reactor for ITER

Autor: T Yamanishi, Y Kawamura, Y Iwai, T Arita, T Maruyama, T Kakuta, S Konishi, M Enoeda, S Ohira, T Hayashi, H Nakamura, K Kobayashi, T Tadokoro, T Ito, M Yamada, T Suzuki, M Nishi, T Nagashima, M Ohta

Publikováno v: Nuclear Fusion. 40:515-518

A system composed of a palladium diffuser and an electrolytic reactor has been proposed and then developed for the fuel cleanup system of ITER. The performance of the system has been studied in detail in a stand-alone test. A fuel simulation loop of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5e9743365d9d7ca79f3f9bc5a5f44470
https://doi.org/10.1088/0029-5515/40/3y/311

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Tritium Safety in the Design of the ITER Tritium Processing Systems

Autor: M. Enoeda, D. F. Holland, J.E. Koonce, O. K. Kveton

Publikováno v: Fusion Technology. 28:865-870

The design of the ITER tritium systems must ensure that the public is protected from operational and accidental tritium release and that worker exposures are minimized. The ITER public exposure limits are consistent with international recommendations

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::00dfcd511f8bd7d7d8045620a67fc489
https://doi.org/10.13182/fst95-a30513

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