Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications
By H. Tanigawa, E. Gaganidze, T. Hirose, M. Ando, S. Zinkle, R. Lindau, E. Diegele. 2017
151 citations recorded by the source corpus.
Reduced-activation ferritic/martensitic (RAFM) steel is the benchmark structural material for in-vessel components of fusion reactor. The current status of RAFM developments and evaluations is reviewed based on two leading RAFM steels, F82H and EUROFER-97. The applicability of various joining technologies for fabrication of fusion first wall and blanket structures, such as weld or diffusion bonding, is overviewed as well. The technical challenges and potential risks of utilizing RAFM steels as the structural material of in-vessel components are discussed, and possible mitigation methodology is introduced. The discussion suggests that deuterium–tritium fusion neutron irradiation effects currently need to be treated as an ambiguity factor which could be incorporated within the safety factor. The safety factor will be defined by the engineering design criteria which are not yet developed with regard to irradiation effects and some high temperature process, and the operating time condition of the in-vessel component will be defined by the condition at which those ambiguities due to neutron irradiation become too large to be acceptable, or by the critical condition at which 14 MeV fusion neutron irradiation effects is expected to become different from fission neutron irradiation effects.
Subfields: Materials Chemistry, Metals and Alloys
View Paper: https://www.semanticscholar.org/paper/552083cc03333860ec66f2634137deb8fe7a712a
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In Materials Chemistry
Citations in the corpus
- Additive manufacturing of steels: a review of achievements and challenges (2020, methodology): “[197] Tanigawa H, Gaganidze E, Hirose T, Ando M, Zinkle S, Lindau R, Diegele E (2017) Development of benchmark”
- European DEMO design strategy and consequences for materials (2017, background): “This in turn strongly impacts the selection of the materials and PFC technologies, the definition of operating conditions of the structural materials/components and the selection of coolants [48, 49].”
- Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications (2017, unknown): “…steels such as F82H or EUROFER97 is considered to be adequate only for fusion neutron doses of 20-50 dpa based on void swelling at ~400-500 o C [8, 9, 30], and even lower allowable doses might occur at lower or higher temperatures due to radiation hardening/embrittlement and high temperature…”