Progress of advanced material tokamak experiment (AMTEX) program on JFT-2M
Application testing of the low activation ferritic steel to plasma is in progress in the JFT-2M tokamak. The toroidal field ripple reduction with ferritic insertion between the vacuum vessel and the toroidal field coils (1st stage) was successfully demonstrated. So far, no deteriorating effects of f...
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| Veröffentlicht in: | Fusion engineering and design 2001-10, Vol.56, p.837-841 |
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| container_title | Fusion engineering and design |
| container_volume | 56 |
| creator | Kimura, H Sato, M Kawashima, H Isei, N Tsuzuki, K Ogawa, H Ogawa, T Miura, Y Yamamoto, M Shibata, T Akiyama, T Miyachi, K |
| description | Application testing of the low activation ferritic steel to plasma is in progress in the JFT-2M tokamak. The toroidal field ripple reduction with ferritic insertion between the vacuum vessel and the toroidal field coils (1st stage) was successfully demonstrated. So far, no deteriorating effects of ferritic boards (FBs) inside the vacuum vessel has been observed in the pre-testing on compatibility with plasma (2nd stage). The density limit was improved by more than a factor of 1.6 after boronization with inside FBs. Design and preparation works are in progress for the testing on compatibility with plasma (3rd stage), where inside wall of the vacuum vessel will be fully covered with ferritic steel. |
| doi_str_mv | 10.1016/S0920-3796(01)00362-3 |
| format | Article |
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The toroidal field ripple reduction with ferritic insertion between the vacuum vessel and the toroidal field coils (1st stage) was successfully demonstrated. So far, no deteriorating effects of ferritic boards (FBs) inside the vacuum vessel has been observed in the pre-testing on compatibility with plasma (2nd stage). The density limit was improved by more than a factor of 1.6 after boronization with inside FBs. Design and preparation works are in progress for the testing on compatibility with plasma (3rd stage), where inside wall of the vacuum vessel will be fully covered with ferritic steel.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/S0920-3796(01)00362-3</identifier><identifier>CODEN: FEDEEE</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. 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The toroidal field ripple reduction with ferritic insertion between the vacuum vessel and the toroidal field coils (1st stage) was successfully demonstrated. So far, no deteriorating effects of ferritic boards (FBs) inside the vacuum vessel has been observed in the pre-testing on compatibility with plasma (2nd stage). The density limit was improved by more than a factor of 1.6 after boronization with inside FBs. Design and preparation works are in progress for the testing on compatibility with plasma (3rd stage), where inside wall of the vacuum vessel will be fully covered with ferritic steel.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Ferrites</subject><subject>Ferritic steel</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Machine design</subject><subject>Plasma</subject><subject>Plasma applications</subject><subject>Plasma density</subject><subject>Steel</subject><subject>Tokamak</subject><subject>Toroidal field coils</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2001</creationdate><recordtype>article</recordtype><recordid>eNqFkNtKxDAQhoMouB4eQciNqBfVyaFJeyWyeERRcAXvwmw6lWq7XZMq-vZmXdFLITAQvn8OH2M7Ag4FCHN0D6WETNnS7IM4AFBGZmqFjURhVWZFaVbZ6BdZZxsxPgMIm96IXd2F_ilQjLyvOVbvOPNU8Q4HCg22fOhfsMMXTh_z9NHRbOD7JzeT08cDPl8EseP9jF-dTTJ5s8XWamwjbf_UTfZwdjoZX2TXt-eX45PrzGtlhywvDQjKpUSEtI8lqb1BLEVRVr6orFQF1FVRTEFrkWvM1VRTlXvjCwPTQqpNtrfsmzZ4faM4uK6JntoWZ9S_RWe1NkrmSicyX5I-9DEGqt08HYHh0wlwC3XuW51beHEg3Lc6p1Ju92cCRo9tHZKVJv6FlZbWKEjc8ZKjdO57Q8FF39DCYBPID67qm38mfQF2Z4As</recordid><startdate>20011001</startdate><enddate>20011001</enddate><creator>Kimura, H</creator><creator>Sato, M</creator><creator>Kawashima, H</creator><creator>Isei, N</creator><creator>Tsuzuki, K</creator><creator>Ogawa, H</creator><creator>Ogawa, T</creator><creator>Miura, Y</creator><creator>Yamamoto, M</creator><creator>Shibata, T</creator><creator>Akiyama, T</creator><creator>Miyachi, K</creator><general>Elsevier B.V</general><general>Elsevier Science</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TC</scope></search><sort><creationdate>20011001</creationdate><title>Progress of advanced material tokamak experiment (AMTEX) program on JFT-2M</title><author>Kimura, H ; Sato, M ; Kawashima, H ; Isei, N ; Tsuzuki, K ; Ogawa, H ; Ogawa, T ; Miura, Y ; Yamamoto, M ; Shibata, T ; Akiyama, T ; Miyachi, K</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c437t-59601e522aa07967e24c6aa9189dc8d72380fd88b044154a53b4ed5c6c860b823</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2001</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. 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| ispartof | Fusion engineering and design, 2001-10, Vol.56, p.837-841 |
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| language | eng |
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| source | ScienceDirect Journals (5 years ago - present) |
| subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Ferrites Ferritic steel Installations for energy generation and conversion: thermal and electrical energy Machine design Plasma Plasma applications Plasma density Steel Tokamak Toroidal field coils |
| title | Progress of advanced material tokamak experiment (AMTEX) program on JFT-2M |
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