A mock-up of a tritium pellet injector for ITER
The ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. T...
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| Veröffentlicht in: | Fusion engineering and design 2001-11, Vol.58, p.313-317 |
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| container_title | Fusion engineering and design |
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| creator | Viniar, I Saksaganskii, G Skoblikov, S Krasilnikov, I Pimanikhin, S |
| description | The ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. The rectangular rod 3×4 mm
2 from condensed protium was extruded within 1500 s at rate of ∼15 mm/s. Pellets ∼3 mm in size formed from the rod were accelerated up to 500 m/s by helium under a pressure of 1 MPa with an injection frequency of 1 and 2 Hz. The main injector subsystems and the current status of the work are described. |
| doi_str_mv | 10.1016/S0920-3796(01)00360-X |
| format | Article |
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2 from condensed protium was extruded within 1500 s at rate of ∼15 mm/s. Pellets ∼3 mm in size formed from the rod were accelerated up to 500 m/s by helium under a pressure of 1 MPa with an injection frequency of 1 and 2 Hz. The main injector subsystems and the current status of the work are described.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/S0920-3796(01)00360-X</identifier><language>eng</language><publisher>Elsevier B.V</publisher><subject>Experimental reactors ; Extruders ; ITER ; Mockups ; Pellet injector ; Pneumatic equipment ; Tokamak ; Tokamak devices ; Tritium</subject><ispartof>Fusion engineering and design, 2001-11, Vol.58, p.313-317</ispartof><rights>2001 Elsevier Science B.V.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c339t-56f8ec705a9ebd19b32a58ffd802e6c04153bffd2305dfc7c19436e5e803cd6a3</citedby><cites>FETCH-LOGICAL-c339t-56f8ec705a9ebd19b32a58ffd802e6c04153bffd2305dfc7c19436e5e803cd6a3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S092037960100360X$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,27901,27902,65306</link.rule.ids></links><search><creatorcontrib>Viniar, I</creatorcontrib><creatorcontrib>Saksaganskii, G</creatorcontrib><creatorcontrib>Skoblikov, S</creatorcontrib><creatorcontrib>Krasilnikov, I</creatorcontrib><creatorcontrib>Pimanikhin, S</creatorcontrib><title>A mock-up of a tritium pellet injector for ITER</title><title>Fusion engineering and design</title><description>The ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. The rectangular rod 3×4 mm
2 from condensed protium was extruded within 1500 s at rate of ∼15 mm/s. Pellets ∼3 mm in size formed from the rod were accelerated up to 500 m/s by helium under a pressure of 1 MPa with an injection frequency of 1 and 2 Hz. The main injector subsystems and the current status of the work are described.</description><subject>Experimental reactors</subject><subject>Extruders</subject><subject>ITER</subject><subject>Mockups</subject><subject>Pellet injector</subject><subject>Pneumatic equipment</subject><subject>Tokamak</subject><subject>Tokamak devices</subject><subject>Tritium</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2001</creationdate><recordtype>article</recordtype><recordid>eNqFkNFLwzAQxoMoOKd_gpA39aHu0jRp-yRjTB0MBJ2wt5CmF8hc15q0gv-92Sa-CnccB9933O8j5JrBPQMmJ29QppDwvJS3wO4AuIRkfUJGrMh5krNSnpLRn-ScXISwAWB5rBGZTGnTmo9k6Ghrqaa9d70bGtrhdos9dbsNmr711MZerOavl-TM6m3Aq985Ju-P89XsOVm-PC1m02ViOC_7REhboMlB6BKrmpUVT7UorK0LSFEayJjgVVxTDqK2JjeszLhEgQVwU0vNx-TmeLfz7eeAoVeNCyY-pXfYDkHlmZBZ5JNRKY5K49sQPFrVeddo_60YqH0-6pCP2sMrYOqQj1pH38PRhxHjy6FXwTjcGaydj8yqbt0_F34AoStrlw</recordid><startdate>20011101</startdate><enddate>20011101</enddate><creator>Viniar, I</creator><creator>Saksaganskii, G</creator><creator>Skoblikov, S</creator><creator>Krasilnikov, I</creator><creator>Pimanikhin, S</creator><general>Elsevier B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TC</scope></search><sort><creationdate>20011101</creationdate><title>A mock-up of a tritium pellet injector for ITER</title><author>Viniar, I ; Saksaganskii, G ; Skoblikov, S ; Krasilnikov, I ; Pimanikhin, S</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c339t-56f8ec705a9ebd19b32a58ffd802e6c04153bffd2305dfc7c19436e5e803cd6a3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2001</creationdate><topic>Experimental reactors</topic><topic>Extruders</topic><topic>ITER</topic><topic>Mockups</topic><topic>Pellet injector</topic><topic>Pneumatic equipment</topic><topic>Tokamak</topic><topic>Tokamak devices</topic><topic>Tritium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Viniar, I</creatorcontrib><creatorcontrib>Saksaganskii, G</creatorcontrib><creatorcontrib>Skoblikov, S</creatorcontrib><creatorcontrib>Krasilnikov, I</creatorcontrib><creatorcontrib>Pimanikhin, S</creatorcontrib><collection>CrossRef</collection><collection>Mechanical Engineering Abstracts</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Viniar, I</au><au>Saksaganskii, G</au><au>Skoblikov, S</au><au>Krasilnikov, I</au><au>Pimanikhin, S</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>A mock-up of a tritium pellet injector for ITER</atitle><jtitle>Fusion engineering and design</jtitle><date>2001-11-01</date><risdate>2001</risdate><volume>58</volume><spage>313</spage><epage>317</epage><pages>313-317</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>The ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. The rectangular rod 3×4 mm
2 from condensed protium was extruded within 1500 s at rate of ∼15 mm/s. Pellets ∼3 mm in size formed from the rod were accelerated up to 500 m/s by helium under a pressure of 1 MPa with an injection frequency of 1 and 2 Hz. The main injector subsystems and the current status of the work are described.</abstract><pub>Elsevier B.V</pub><doi>10.1016/S0920-3796(01)00360-X</doi><tpages>5</tpages></addata></record> |
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| ispartof | Fusion engineering and design, 2001-11, Vol.58, p.313-317 |
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| language | eng |
| recordid | cdi_proquest_miscellaneous_745648736 |
| source | Elsevier ScienceDirect Journals |
| subjects | Experimental reactors Extruders ITER Mockups Pellet injector Pneumatic equipment Tokamak Tokamak devices Tritium |
| title | A mock-up of a tritium pellet injector for ITER |
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