ARC reactor – Neutron irradiation analysis
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference47 articles.
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3. Comparison of 16 MeV proton, 14 MeV neutron and fission neutron damage in copper;Mitchell;J. Nucl. Mater.,1973
4. Low-dose neutron irradiation damage in FCC and BCC metals;English;J. Nucl. Mater.,1982
5. Neutron-Induced Activation of Materials for the First Wall of Conceptual Fusion Reactors;Khursheed,1989
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2. Effect of the various tritium breeding materials on the tritium breeding ratio in ARC fusion reactor;International Journal of Energy Studies;2023-06-23
3. Review of commercial nuclear fusion projects;Frontiers in Energy Research;2023-06-07
4. FERMI: Fusion Energy Reactor Models Integrator;Fusion Science and Technology;2023-03-20
5. Development of an object-oriented, thermal-hydraulics model for ARC FLiBe loop safety assessment;Fusion Engineering and Design;2022-05
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