Recent advance progress of HL-3 experiments
Since the first plasma realized in 2020, a series of key systems on HL-3 (known as HL-2M before) tokamak have been equipped/upgraded, including in-vessel components (the first wall, lower divertor, and toroidal cryogenic/water-cooling/baking/glow discharge systems, etc.), auxiliary heating system of...
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| Veröffentlicht in: | Nuclear fusion 2024-11, Vol.64 (11), p.112021 |
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| creator | Duan, X.R. Xu, M. Zhong, W.L. Ji, X.Q. Chen, W. Shi, Z.B. Liu, X.L. Lu, B. Li, B. Wang, Y.Q. Li, J.Q. Zheng, G.Y. Liu, Yong Yang, Q.W. Yan, L.W. Cai, L.J. Li, Q. Liu, Y. Bai, X.Y. Cao, Z. Chen, X. Chen, H.T. Chen, Y.H. Dong, G.Q. Du, H.L. Fan, D.M. Gao, J.M. Geng, S.F. Hao, G.Z. He, H.M. Huang, M. Jiang, M. Ke, R. Liang, A.S. Li, J.X. Li, Qing Li, Yongge Li, L.C. Li, H.J. Li, W.B. Liu, D.Q. Long, T. Lu, L.F. Nie, L. Shi, P.W. Peng, J.F. Sun, A.P. Sun, T.F. Tong, R.H. Wei, H.L. Wang, S. Xiao, G.L. Xiao, X.P. Xue, L. Xu, H.B. Yang, Z.Y. Yu, D.L. Yu, L.M. Zhang, Y.P. Zheng, X. Zhang, L. Zhang, Y. Zhang, F. Zhang, X.L. |
| description | Since the first plasma realized in 2020, a series of key systems on HL-3 (known as HL-2M before) tokamak have been equipped/upgraded, including in-vessel components (the first wall, lower divertor, and toroidal cryogenic/water-cooling/baking/glow discharge systems, etc.), auxiliary heating system of 11 MW, and 28 diagnostic systems (to measure the plasma density, electron temperature, radiation, magnetic field, etc.). Magnet field systems were commissioned firstly for divertor plasma discharges. During the 2nd experimental campaign of HL-3 tokamak, several great progresses have been achieved. Firstly, the successful operation with plasma current larger than 1 MA was achieved under a divertor configuration. Secondly, the advanced divertor concept with two distinct snowflake configurations was realized. It is found that the distribution of ion saturation current and heat flux on bottom plate becomes wide due to magnetic surface expansion, demonstrating the advantage of such configuration in the heat flux mitigation. In addition, using the combination of NBI, ECRH and LHCD, the standard sawtoothing high confinement mode of megampere plasma was firstly accessed on the HL-3. The successful commissioning of HL-3 is beneficial for the initial operation of ITER. |
| doi_str_mv | 10.1088/1741-4326/ad6e9e |
| format | Article |
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Magnet field systems were commissioned firstly for divertor plasma discharges. During the 2nd experimental campaign of HL-3 tokamak, several great progresses have been achieved. Firstly, the successful operation with plasma current larger than 1 MA was achieved under a divertor configuration. Secondly, the advanced divertor concept with two distinct snowflake configurations was realized. It is found that the distribution of ion saturation current and heat flux on bottom plate becomes wide due to magnetic surface expansion, demonstrating the advantage of such configuration in the heat flux mitigation. In addition, using the combination of NBI, ECRH and LHCD, the standard sawtoothing high confinement mode of megampere plasma was firstly accessed on the HL-3. The successful commissioning of HL-3 is beneficial for the initial operation of ITER.</description><identifier>ISSN: 0029-5515</identifier><identifier>EISSN: 1741-4326</identifier><identifier>DOI: 10.1088/1741-4326/ad6e9e</identifier><identifier>CODEN: NUFUAU</identifier><language>eng</language><publisher>United States: IOP Publishing</publisher><subject>1 MA plasma ; advanced divertor ; H-mode ; HL-3 experiment ; INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY ; tokamak</subject><ispartof>Nuclear fusion, 2024-11, Vol.64 (11), p.112021</ispartof><rights>2024 The Author(s). 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Fusion</addtitle><description>Since the first plasma realized in 2020, a series of key systems on HL-3 (known as HL-2M before) tokamak have been equipped/upgraded, including in-vessel components (the first wall, lower divertor, and toroidal cryogenic/water-cooling/baking/glow discharge systems, etc.), auxiliary heating system of 11 MW, and 28 diagnostic systems (to measure the plasma density, electron temperature, radiation, magnetic field, etc.). Magnet field systems were commissioned firstly for divertor plasma discharges. During the 2nd experimental campaign of HL-3 tokamak, several great progresses have been achieved. Firstly, the successful operation with plasma current larger than 1 MA was achieved under a divertor configuration. Secondly, the advanced divertor concept with two distinct snowflake configurations was realized. It is found that the distribution of ion saturation current and heat flux on bottom plate becomes wide due to magnetic surface expansion, demonstrating the advantage of such configuration in the heat flux mitigation. In addition, using the combination of NBI, ECRH and LHCD, the standard sawtoothing high confinement mode of megampere plasma was firstly accessed on the HL-3. 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A.S.</creatorcontrib><creatorcontrib>Li, J.X.</creatorcontrib><creatorcontrib>Li, Qing</creatorcontrib><creatorcontrib>Li, Yongge</creatorcontrib><creatorcontrib>Li, L.C.</creatorcontrib><creatorcontrib>Li, H.J.</creatorcontrib><creatorcontrib>Li, W.B.</creatorcontrib><creatorcontrib>Liu, D.Q.</creatorcontrib><creatorcontrib>Long, T.</creatorcontrib><creatorcontrib>Lu, L.F.</creatorcontrib><creatorcontrib>Nie, L.</creatorcontrib><creatorcontrib>Shi, P.W.</creatorcontrib><creatorcontrib>Peng, J.F.</creatorcontrib><creatorcontrib>Sun, A.P.</creatorcontrib><creatorcontrib>Sun, T.F.</creatorcontrib><creatorcontrib>Tong, R.H.</creatorcontrib><creatorcontrib>Wei, H.L.</creatorcontrib><creatorcontrib>Wang, S.</creatorcontrib><creatorcontrib>Xiao, G.L.</creatorcontrib><creatorcontrib>Xiao, X.P.</creatorcontrib><creatorcontrib>Xue, L.</creatorcontrib><creatorcontrib>Xu, H.B.</creatorcontrib><creatorcontrib>Yang, Z.Y.</creatorcontrib><creatorcontrib>Yu, D.L.</creatorcontrib><creatorcontrib>Yu, L.M.</creatorcontrib><creatorcontrib>Zhang, Y.P.</creatorcontrib><creatorcontrib>Zheng, X.</creatorcontrib><creatorcontrib>Zhang, L.</creatorcontrib><creatorcontrib>Zhang, Y.</creatorcontrib><creatorcontrib>Zhang, F.</creatorcontrib><creatorcontrib>Zhang, X.L.</creatorcontrib><creatorcontrib>HL-3 Team & Collaborators</creatorcontrib><creatorcontrib>Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)</creatorcontrib><collection>IOP Publishing Free Content</collection><collection>IOPscience (Open Access)</collection><collection>CrossRef</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><collection>DOAJ Directory of Open Access Journals</collection><jtitle>Nuclear fusion</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Duan, X.R.</au><au>Xu, M.</au><au>Zhong, W.L.</au><au>Ji, X.Q.</au><au>Chen, W.</au><au>Shi, Z.B.</au><au>Liu, X.L.</au><au>Lu, B.</au><au>Li, B.</au><au>Wang, Y.Q.</au><au>Li, J.Q.</au><au>Zheng, G.Y.</au><au>Liu, Yong</au><au>Yang, Q.W.</au><au>Yan, L.W.</au><au>Cai, L.J.</au><au>Li, Q.</au><au>Liu, Y.</au><au>Bai, X.Y.</au><au>Cao, Z.</au><au>Chen, X.</au><au>Chen, H.T.</au><au>Chen, Y.H.</au><au>Dong, G.Q.</au><au>Du, H.L.</au><au>Fan, D.M.</au><au>Gao, J.M.</au><au>Geng, S.F.</au><au>Hao, G.Z.</au><au>He, H.M.</au><au>Huang, M.</au><au>Jiang, M.</au><au>Ke, R.</au><au>Liang, A.S.</au><au>Li, J.X.</au><au>Li, Qing</au><au>Li, Yongge</au><au>Li, L.C.</au><au>Li, H.J.</au><au>Li, W.B.</au><au>Liu, D.Q.</au><au>Long, T.</au><au>Lu, L.F.</au><au>Nie, L.</au><au>Shi, P.W.</au><au>Peng, J.F.</au><au>Sun, A.P.</au><au>Sun, T.F.</au><au>Tong, R.H.</au><au>Wei, H.L.</au><au>Wang, S.</au><au>Xiao, G.L.</au><au>Xiao, X.P.</au><au>Xue, L.</au><au>Xu, H.B.</au><au>Yang, Z.Y.</au><au>Yu, D.L.</au><au>Yu, L.M.</au><au>Zhang, Y.P.</au><au>Zheng, X.</au><au>Zhang, L.</au><au>Zhang, Y.</au><au>Zhang, F.</au><au>Zhang, X.L.</au><aucorp>HL-3 Team & Collaborators</aucorp><aucorp>Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Recent advance progress of HL-3 experiments</atitle><jtitle>Nuclear fusion</jtitle><stitle>NF</stitle><addtitle>Nucl. Fusion</addtitle><date>2024-11-01</date><risdate>2024</risdate><volume>64</volume><issue>11</issue><spage>112021</spage><pages>112021-</pages><issn>0029-5515</issn><eissn>1741-4326</eissn><coden>NUFUAU</coden><abstract>Since the first plasma realized in 2020, a series of key systems on HL-3 (known as HL-2M before) tokamak have been equipped/upgraded, including in-vessel components (the first wall, lower divertor, and toroidal cryogenic/water-cooling/baking/glow discharge systems, etc.), auxiliary heating system of 11 MW, and 28 diagnostic systems (to measure the plasma density, electron temperature, radiation, magnetic field, etc.). Magnet field systems were commissioned firstly for divertor plasma discharges. During the 2nd experimental campaign of HL-3 tokamak, several great progresses have been achieved. Firstly, the successful operation with plasma current larger than 1 MA was achieved under a divertor configuration. Secondly, the advanced divertor concept with two distinct snowflake configurations was realized. It is found that the distribution of ion saturation current and heat flux on bottom plate becomes wide due to magnetic surface expansion, demonstrating the advantage of such configuration in the heat flux mitigation. In addition, using the combination of NBI, ECRH and LHCD, the standard sawtoothing high confinement mode of megampere plasma was firstly accessed on the HL-3. The successful commissioning of HL-3 is beneficial for the initial operation of ITER.</abstract><cop>United States</cop><pub>IOP Publishing</pub><doi>10.1088/1741-4326/ad6e9e</doi><tpages>14</tpages><orcidid>https://orcid.org/0000-0002-0136-8953</orcidid><orcidid>https://orcid.org/0000-0001-6480-7004</orcidid><orcidid>https://orcid.org/0000-0002-4289-4060</orcidid><orcidid>https://orcid.org/0009-0001-3059-7026</orcidid><orcidid>https://orcid.org/0000-0003-2310-6134</orcidid><orcidid>https://orcid.org/0000-0002-2071-7741</orcidid><orcidid>https://orcid.org/0000-0002-9546-5139</orcidid><orcidid>https://orcid.org/0000-0002-9382-6295</orcidid><orcidid>https://orcid.org/0009-0000-4083-1552</orcidid><orcidid>https://orcid.org/0000-0003-0117-0098</orcidid><orcidid>https://orcid.org/0000-0002-1177-3063</orcidid><orcidid>https://orcid.org/0000000201368953</orcidid><orcidid>https://orcid.org/0000000293826295</orcidid><orcidid>https://orcid.org/0000000220717741</orcidid><orcidid>https://orcid.org/0009000130597026</orcidid><orcidid>https://orcid.org/0000000295465139</orcidid><orcidid>https://orcid.org/0000000164807004</orcidid><orcidid>https://orcid.org/0000000301170098</orcidid><orcidid>https://orcid.org/0009000040831552</orcidid><orcidid>https://orcid.org/0000000211773063</orcidid><orcidid>https://orcid.org/0000000323106134</orcidid><orcidid>https://orcid.org/0000000242894060</orcidid><oa>free_for_read</oa></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0029-5515 |
| ispartof | Nuclear fusion, 2024-11, Vol.64 (11), p.112021 |
| issn | 0029-5515 1741-4326 |
| language | eng |
| recordid | cdi_iop_journals_10_1088_1741_4326_ad6e9e |
| source | IOP Publishing Free Content; DOAJ Directory of Open Access Journals |
| subjects | 1 MA plasma advanced divertor H-mode HL-3 experiment INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY tokamak |
| title | Recent advance progress of HL-3 experiments |
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