Chenglong Geng , Wei Xu , Zinan Feng , Weihai Wang , Xu Li , Chenlun Liao , Mengmeng Li , Xiancai Meng , Lizhen Liang , Chundong Hu
{"title":"紧凑型D-D中子发生器高性能钛靶的结构设计与热分析","authors":"Chenglong Geng , Wei Xu , Zinan Feng , Weihai Wang , Xu Li , Chenlun Liao , Mengmeng Li , Xiancai Meng , Lizhen Liang , Chundong Hu","doi":"10.1016/j.fusengdes.2025.115472","DOIUrl":null,"url":null,"abstract":"<div><div>The titanium target is key component in accelerator-driven neutron generators. During beam injection, heat is deposited on the target surface, resulting in increasing of the surface temperature of the target. Deuterium implanted in the titanium film of the target is released significantly when the temperature exceeds 200°C. This work presents three different cooling concepts and simulations of heat load and deformation for D-D neutron generator. The heat load removal capability is improved by optimizing the structure of the coolant channel inside the target. The maximum target surface temperature was controlled at 73.7°C when the deuterium beam injection power was 600 W via a double-spiral cooling structure. It was found the thermal power transferred to the coolant increases with the coolant flow up to coolant velocity equal to 19 m/s. Moreover, the depth of the target coolant channel does not affect the heat load removal capability. Finally, a 5 × 10<sup>8</sup> n/s neutron yield experiment with steady operation for 7 h was performed with the application of the double-spiral coolant structure titanium target.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115472"},"PeriodicalIF":2.0000,"publicationDate":"2025-09-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Structural design and thermal analysis of high-performance titanium targets for compact D-D neutron generator\",\"authors\":\"Chenglong Geng , Wei Xu , Zinan Feng , Weihai Wang , Xu Li , Chenlun Liao , Mengmeng Li , Xiancai Meng , Lizhen Liang , Chundong Hu\",\"doi\":\"10.1016/j.fusengdes.2025.115472\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The titanium target is key component in accelerator-driven neutron generators. During beam injection, heat is deposited on the target surface, resulting in increasing of the surface temperature of the target. Deuterium implanted in the titanium film of the target is released significantly when the temperature exceeds 200°C. This work presents three different cooling concepts and simulations of heat load and deformation for D-D neutron generator. The heat load removal capability is improved by optimizing the structure of the coolant channel inside the target. The maximum target surface temperature was controlled at 73.7°C when the deuterium beam injection power was 600 W via a double-spiral cooling structure. It was found the thermal power transferred to the coolant increases with the coolant flow up to coolant velocity equal to 19 m/s. Moreover, the depth of the target coolant channel does not affect the heat load removal capability. Finally, a 5 × 10<sup>8</sup> n/s neutron yield experiment with steady operation for 7 h was performed with the application of the double-spiral coolant structure titanium target.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"222 \",\"pages\":\"Article 115472\"},\"PeriodicalIF\":2.0000,\"publicationDate\":\"2025-09-29\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625006684\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625006684","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Structural design and thermal analysis of high-performance titanium targets for compact D-D neutron generator
The titanium target is key component in accelerator-driven neutron generators. During beam injection, heat is deposited on the target surface, resulting in increasing of the surface temperature of the target. Deuterium implanted in the titanium film of the target is released significantly when the temperature exceeds 200°C. This work presents three different cooling concepts and simulations of heat load and deformation for D-D neutron generator. The heat load removal capability is improved by optimizing the structure of the coolant channel inside the target. The maximum target surface temperature was controlled at 73.7°C when the deuterium beam injection power was 600 W via a double-spiral cooling structure. It was found the thermal power transferred to the coolant increases with the coolant flow up to coolant velocity equal to 19 m/s. Moreover, the depth of the target coolant channel does not affect the heat load removal capability. Finally, a 5 × 108 n/s neutron yield experiment with steady operation for 7 h was performed with the application of the double-spiral coolant structure titanium target.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.