Title :
Compatibility of ITER candidate materials with static gallium
Author :
Luebbers, P.R. ; Chopra, O.K.
Author_Institution :
Div. of Energy Technol., Argonne Nat. Lab., IL, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
Corrosion tests have been conducted to determine the compatibility of gallium with candidate structural materials for the International Thermonuclear Experimental Reactor (ITER) first wall/blanket systems, e.g., Type 316 stainless steel (SS), Inconel 625, and Nb-5 Mo-1 Zr. The results indicate that Type 316 SS is least resistant to corrosion in static gallium and Nb-5 Mo-1 Zr alloy is most resistant. At 400°C, corrosion rates for Type 316 SS, Inconel 625, and Nb-5 Mo-1 Zr alloy are ≈4.0, 0.5, and 0.03 mm/yr, respectively. Iron, nickel, and chromium react rapidly with gallium. Iron shows greater corrosion than nickel at 400°C (⩾88 and 18 mm/yr, respectively). The present study indicates that at temperatures up to 400°C, corrosion occurs primarily by dissolution and is accompanied by formation of metal/gallium intermetallic compounds. The growth of intermetallic compounds may control the overall rate of corrosion
Keywords :
austenitic stainless steel; chromium alloys; corrosion; fusion reactor blankets; fusion reactor materials; fusion reactors; gallium; molybdenum alloys; nickel alloys; niobium alloys; zirconium alloys; 400 C; ITER candidate materials; Inconel 625; International Thermonuclear Experimental Reactor; Nb-5 Mo-1 Zr; NbZrMo; Ni-Cr; Type 316 stainless steel; candidate structural materials; compatibility; corrosion tests; dissolution; first wall/blanket systems; intermetallic compounds; static Ga; Building materials; Conducting materials; Corrosion; Gallium alloys; Intermetallic; Iron; Materials testing; Nickel; System testing; Zirconium;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534210
