Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor
Designs for a conceptual design of fusion–fission hybrid fuel breeder reactors with that use a helium-cooled high power density blanket has attractiveness have conceptual attractiveness. Helium gas is a good coolant for the fuel zone of the blanket in such a reactor in terms of neutronics performanc...
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Veröffentlicht in: | Fusion engineering and design 2010-12, Vol.85 (10), p.2232-2236 |
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creator | Jin, Ming Bai, Yunqing Jiang, Jieqiong |
description | Designs for a conceptual design of fusion–fission hybrid fuel breeder reactors with that use a helium-cooled high power density blanket has attractiveness have conceptual attractiveness. Helium gas is a good coolant for the fuel zone of the blanket in such a reactor in terms of neutronics performance. However, it is difficult to use helium gas as a coolant to carry away a high power density heat regime due to its low heat-carrying capacity. This paper proposed a scheme of for a helium-cooled high power density blanket for a fusion–fission hybrid reactor with about 100
MW/m
3 average power density in the fuel zone. The preliminary feasibility of this scheme was demonstrated by calculating and numerically simulating the pumping power, temperature and stress distribution. |
doi_str_mv | 10.1016/j.fusengdes.2010.08.046 |
format | Article |
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MW/m
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MW/m
3 average power density in the fuel zone. The preliminary feasibility of this scheme was demonstrated by calculating and numerically simulating the pumping power, temperature and stress distribution.</description><subject>Applied sciences</subject><subject>Blanket</subject><subject>Blanketing</subject><subject>Breeder reactors</subject><subject>Controled nuclear fusion plants</subject><subject>Coolants</subject><subject>Density</subject><subject>Design engineering</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fuels</subject><subject>Fusion-fission hybrid reactors</subject><subject>Helium</subject><subject>High power density</subject><subject>Hybrid reactor</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Mathematical analysis</subject><subject>Thermal-hydraulic</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2010</creationdate><recordtype>article</recordtype><recordid>eNqFkEtuFDEQhi0EEkPgDHiDsuqJH0O7vYwiEpAiZZOsLbddnvbgaU9c3UTNKnfghpwEjybKFsmWq6zvr8dPyGfO1pzx9mK3DjPCuPWAa8HqL-vWbNO-ISveKdkortu3ZMW0YI1Uun1PPiDuGOOqnhX5fT9A2dvUDIsvdk7RIa2V4nakdvT12rRgRJprTgdIcd43LucEng5xO9BDfoJSFSPGaaF9suNPmGjIpeJ1rpjHv89_QsRjRIelL9HTAtZNuXwk74JNCJ9e3jPycP3t_up7c3t38-Pq8rZxUqmp0Z2Um7qp5o6BAK1b6x1X1lpXMxWc70UvJRMBFEjFW-eZ6L92m66VwAKXZ-T8VPdQ8uMMOJl9RAepzgp5RtO1uvqiOaukOpGuZMQCwRxK3NuyGM7M0WyzM69mm6PZhnWmml2VX156WHQ2hWJHF_FVLqSSGylE5S5PHNSFf0UoBl2E0YGPBdxkfI7_7fUP81CdHQ</recordid><startdate>20101201</startdate><enddate>20101201</enddate><creator>Jin, Ming</creator><creator>Bai, Yunqing</creator><creator>Jiang, Jieqiong</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20101201</creationdate><title>Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor</title><author>Jin, Ming ; Bai, Yunqing ; Jiang, Jieqiong</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c377t-9833410191c0e2e996adc17aaac2e97fcdb2b3302fe7e3716cd02b584863e0f13</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2010</creationdate><topic>Applied sciences</topic><topic>Blanket</topic><topic>Blanketing</topic><topic>Breeder reactors</topic><topic>Controled nuclear fusion plants</topic><topic>Coolants</topic><topic>Density</topic><topic>Design engineering</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fuels</topic><topic>Fusion-fission hybrid reactors</topic><topic>Helium</topic><topic>High power density</topic><topic>Hybrid reactor</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Mathematical analysis</topic><topic>Thermal-hydraulic</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Jin, Ming</creatorcontrib><creatorcontrib>Bai, Yunqing</creatorcontrib><creatorcontrib>Jiang, Jieqiong</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Jin, Ming</au><au>Bai, Yunqing</au><au>Jiang, Jieqiong</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor</atitle><jtitle>Fusion engineering and design</jtitle><date>2010-12-01</date><risdate>2010</risdate><volume>85</volume><issue>10</issue><spage>2232</spage><epage>2236</epage><pages>2232-2236</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><coden>FEDEEE</coden><abstract>Designs for a conceptual design of fusion–fission hybrid fuel breeder reactors with that use a helium-cooled high power density blanket has attractiveness have conceptual attractiveness. 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MW/m
3 average power density in the fuel zone. The preliminary feasibility of this scheme was demonstrated by calculating and numerically simulating the pumping power, temperature and stress distribution.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2010.08.046</doi><tpages>5</tpages></addata></record> |
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subjects | Applied sciences Blanket Blanketing Breeder reactors Controled nuclear fusion plants Coolants Density Design engineering Energy Energy. Thermal use of fuels Exact sciences and technology Fuels Fusion-fission hybrid reactors Helium High power density Hybrid reactor Installations for energy generation and conversion: thermal and electrical energy Mathematical analysis Thermal-hydraulic |
title | Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor |
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