Study on normal operation and failure of pressure control for CN HCCB TBS primary coolant system
Based on the design requirement of the test blanket module (TBM) and the design parameters of the helium coolant system (HCS) primary loop, the preliminary design of the pressure control system (PCS), including control logic and main parameters, has been completed. The one-dimensional thermal hydrau...
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| Veröffentlicht in: | Fusion engineering and design 2019-07, Vol.144, p.154-159 |
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| creator | Wang, Xiaoyong Ye, Xingfu Zhang, Hongxiang Wang, Xiaoyu Liu, Jie Yan, Yongjiang Zhao, Zhengning |
| description | Based on the design requirement of the test blanket module (TBM) and the design parameters of the helium coolant system (HCS) primary loop, the preliminary design of the pressure control system (PCS), including control logic and main parameters, has been completed. The one-dimensional thermal hydraulic model has been created based on the PCS. According to the operation scenario of international thermal nuclear experimental reactor (ITER), several operating cases, including normal operating cases and PCS failure cases, have been studied. The results show that the PCS design is feasible and the inlet pressure of the TBM can be controlled to remain around 8 MPa. The PCS failures impact the pressure of the HCS as well as the inlet pressure of the TBM severely, while the impacts on the temperature of the TBM are not significant. |
| doi_str_mv | 10.1016/j.fusengdes.2019.05.010 |
| format | Article |
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The one-dimensional thermal hydraulic model has been created based on the PCS. According to the operation scenario of international thermal nuclear experimental reactor (ITER), several operating cases, including normal operating cases and PCS failure cases, have been studied. The results show that the PCS design is feasible and the inlet pressure of the TBM can be controlled to remain around 8 MPa. The PCS failures impact the pressure of the HCS as well as the inlet pressure of the TBM severely, while the impacts on the temperature of the TBM are not significant.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2019.05.010</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Control systems design ; Design parameters ; Experimental nuclear reactors ; HCCB-TBS ; Helium coolant system ; Hydraulic models ; Inlet pressure ; Preliminary designs ; Pressure control system ; Thermal hydraulic analysis</subject><ispartof>Fusion engineering and design, 2019-07, Vol.144, p.154-159</ispartof><rights>2019 Elsevier B.V.</rights><rights>Copyright Elsevier Science Ltd. 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The PCS failures impact the pressure of the HCS as well as the inlet pressure of the TBM severely, while the impacts on the temperature of the TBM are not significant.</description><subject>Control systems design</subject><subject>Design parameters</subject><subject>Experimental nuclear reactors</subject><subject>HCCB-TBS</subject><subject>Helium coolant system</subject><subject>Hydraulic models</subject><subject>Inlet pressure</subject><subject>Preliminary designs</subject><subject>Pressure control system</subject><subject>Thermal hydraulic analysis</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2019</creationdate><recordtype>article</recordtype><recordid>eNqFkF1LwzAUhoMoOKe_wYDXrUnTNs3lVtQJQy82r2M-paVrZpIK-_dmbHgrBJKT877n4wHgHqMcI1w_9rmdghm_tAl5gTDLUZUjjC7ADDeUZBSz-hLMECtQRiirr8FNCD1CmKYzA5-bOOkDdCMcnd-JAbq98SJ26UOMGlrRDZM30Fm49yaE41u5MXo3QOs8bN_gqm2XcLvcJEG3E_6Q8m4QY4ThEKLZ3YIrK4Zg7s73HHw8P23bVbZ-f3ltF-tMEVbHrCRlU1FLdYFLjTWjtJZGESW0LWWTYsYKyWRlNSlNWWKkaimxIlQqRm0lyRw8nOruvfueTIi8d5MfU0teEMIajBKCpKInlfIuBG8sP0_NMeJHnLznfzj5ESdHFU84k3Nxcpq0xE9nPA-qM6MyuvNGRa5d92-NX9BngxQ</recordid><startdate>20190701</startdate><enddate>20190701</enddate><creator>Wang, Xiaoyong</creator><creator>Ye, Xingfu</creator><creator>Zhang, Hongxiang</creator><creator>Wang, Xiaoyu</creator><creator>Liu, Jie</creator><creator>Yan, Yongjiang</creator><creator>Zhao, Zhengning</creator><general>Elsevier B.V</general><general>Elsevier Science Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20190701</creationdate><title>Study on normal operation and failure of pressure control for CN HCCB TBS primary coolant system</title><author>Wang, Xiaoyong ; Ye, Xingfu ; Zhang, Hongxiang ; Wang, Xiaoyu ; Liu, Jie ; Yan, Yongjiang ; Zhao, Zhengning</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c396t-434857f7d214d1d9776bec3cadf4b8d97992b9b5fd34e4410c6bb1c37bc97f5b3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2019</creationdate><topic>Control systems design</topic><topic>Design parameters</topic><topic>Experimental nuclear reactors</topic><topic>HCCB-TBS</topic><topic>Helium coolant system</topic><topic>Hydraulic models</topic><topic>Inlet pressure</topic><topic>Preliminary designs</topic><topic>Pressure control system</topic><topic>Thermal hydraulic analysis</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Wang, Xiaoyong</creatorcontrib><creatorcontrib>Ye, Xingfu</creatorcontrib><creatorcontrib>Zhang, Hongxiang</creatorcontrib><creatorcontrib>Wang, Xiaoyu</creatorcontrib><creatorcontrib>Liu, Jie</creatorcontrib><creatorcontrib>Yan, Yongjiang</creatorcontrib><creatorcontrib>Zhao, Zhengning</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace 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>Wang, Xiaoyong</au><au>Ye, Xingfu</au><au>Zhang, Hongxiang</au><au>Wang, Xiaoyu</au><au>Liu, Jie</au><au>Yan, Yongjiang</au><au>Zhao, Zhengning</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Study on normal operation and failure of pressure control for CN HCCB TBS primary coolant system</atitle><jtitle>Fusion engineering and design</jtitle><date>2019-07-01</date><risdate>2019</risdate><volume>144</volume><spage>154</spage><epage>159</epage><pages>154-159</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>Based on the design requirement of the test blanket module (TBM) and the design parameters of the helium coolant system (HCS) primary loop, the preliminary design of the pressure control system (PCS), including control logic and main parameters, has been completed. 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| ispartof | Fusion engineering and design, 2019-07, Vol.144, p.154-159 |
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| language | eng |
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| source | Access via ScienceDirect (Elsevier) |
| subjects | Control systems design Design parameters Experimental nuclear reactors HCCB-TBS Helium coolant system Hydraulic models Inlet pressure Preliminary designs Pressure control system Thermal hydraulic analysis |
| title | Study on normal operation and failure of pressure control for CN HCCB TBS primary coolant system |
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