Sensitivity Study for Tritium Permeation in Helium-Cooled Lead-Lithium DEMO Blanket with the FUS-TPC Code
Author:
Affiliation:
1. Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, 76344, Germany
2. ENEA C.R. Brasimone, Camugnano, I-40032, Boulogne, Italy
3. Fusion for Energy (F4E), Barcelona, Spain
4. Politecnico di Torino, Turin, 10129, Italy
Publisher
Informa UK Limited
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST13-A19162
Reference11 articles.
1. A model for tritium transport in fusion reactor components: The FUS-TPC code
2. Tritium transfers and main operating parameters impact for demo lithium lead breeding blanket (HCLL)
3. Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant
4. L. A. SEDANO, Tritium Cycle Design for He-cooled blankets for DEMO, Report for the EFDA TASK TW4-TTB-COMPU, January 2006.
5. Hydrogen Isotopes Permeability in Eurofer 97 Martensitic Steel
Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. TRITIUM IN NUCLEAR FUSION SYSTEMS;International Journal of Ecosystems and Ecology Science (IJEES);2020-01-30
2. Tritium control in fusion reactor materials: A model for Tritium Extracting System;Fusion Engineering and Design;2015-10
3. Tritium Transport Issues for Helium-Cooled Breeding Blankets;IEEE Transactions on Plasma Science;2014-07
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