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Development of a high-heat flux cooling element with potential application in a near-term fusion power plant divertor

机译：高热通量冷却元件的开发及其在近期聚变电厂分流器中的潜在应用

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Nicholas Jack Robert; Ireland Peter; Hancock David; Robertson Dan;
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1. Development of a high-heat flux cooling element with potential application in a near-term fusion power plant divertor [J] . Nicholas Jack Robert, Ireland Peter, Hancock David, Fusion Engineering and Design . 2015,第OCTa期

机译：高热通量冷却元件的开发及其在近期聚变电厂分流器中的潜在应用
2. Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment [J] . Stork D., Agostini P., Boutard J. L., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2014,第1a3期

机译：为近期的DEMO聚变电厂开发结构，高热通量和面向等离子体的材料：欧盟评估
3. European development of He-cooled divertors for fusion power plants [J] . P. Norajitra, R. Giniyatulin, T. Ihli, Nuclear fusion . 2005,第11期

机译：欧洲开发用于聚变电站的氦冷分流器
4. Four near-term and advanced fusion power plants: systems analysis; economics; prime safety and environmental characteristics [C] . Cook I., Taylor N.P., Ward D.J. Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on . 2003

机译：四个近期和高级聚变电厂：系统分析;经济学;主要安全和环境特征
5. Inverse boundary element/genetic algorithm method for reconstruction of multi-dimensional heat flux distributions with film cooling applications. [D] . Silieti, Mahmood K. 2004

机译：逆边界元/遗传算法方法在薄膜冷却应用中重建多维热通量分布。
6. Maryland Power Plant Cooling-Water Intake Regulations and their Application in Evaluation of Adverse Environmental Impact [O] . Richard McLean, William A. Richkus, Stephen P. Schreiner, 2002

机译：马里兰州电厂冷却水进水法规及其在不良环境影响评估中的应用
7. Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment [O] . Stork, D., Agostini, P., Ibarra, A., 2014

机译：为近期的DEMO聚变电站开发结构，高热通量和面向等离子体的材料：欧盟评估
8. Fabrication and high heat flux test of divertor cooling elements [R] . Suzuki, S. , Araki, M. , Nakamura, K. , 1995

机译：偏滤器冷却元件的制造和高热通量测试

Development of a high-heat flux cooling element with potential application in a near-term fusion power plant divertor

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