High nickel austenitic stainless steels resistant to...

C - Chemistry – Metallurgy – 22 – C

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C22C 38/40 (2006.01) C21D 1/26 (2006.01) C21D 6/00 (2006.01) C22C 30/00 (2006.01) C22C 38/44 (2006.01) C21D 8/00 (2006.01)

Patent

CA 2204031

The present invention aims at providing structural materials having a resistance to degradation by the neutron irradiation, causing no SCC in an environment in light-water reactors even after subjecting to the neutron irradiation of approximately at least 1 x 10 22 n/cm2 (E > 1 MeV), and having thermal expansion coefficients approximately similar to that of structural materials. High nickel austenitic stainless steels having a resistance to degradation by the neutron irradiation can be produced by subjecting stainles steels having compositions (by weight %) of 0.005 to 0.08 % of carbon, at most 0.3 % of Mn, at most 0.2 % of (Si + P + S), 25 to 40 % of Ni, 25 to 40 % of Cr, at most 3 % of Mo or at most 5 % of (Mo + W), at most 0.3 % of Nb + Ta, at most 0.3 % of Ti, at most 0.001 % of B and the balance of Fe to a solution- annealing treatment at a temperature of 1000 to 1150°C.

Acier inoxydable austénitique à forte teneur en nickel résistant aux dégradations imputables à l'irradiation neutronique, destiné à servir de matériau structurel présentant une telle résistance à ces dégradations qu'il n'est pas susceptible de subir des fissures de corrosion sous contraintes dans les conditions d'utilisation des réacteurs de faible poids après avoir subi une irradiation neutronique sous une dose d'environ 1 x 10<22> n/cm<2> (E > 1 MeV). On élabore cet acier en soumettant à un recuit d'homogénéisation au stade solide, à une température comprise entre 1.000 et 1.150 DEG C, un acier inoxydable renfermant, en poids, de 0,005 à 0,08 % de C, au plus 0,3 % de Mn, au plus 0,2 de % Si + P + S, de 25-40 % de Ni, de 25-40 % de Cr, au plus 3 % de Mo ou au plus 5 % de Mo + W, au plus 0,3 % de Nb + Ta, au plus 0,3 % de Ti, au plus 0,001 % de B, le reste étant constitué de Fe.

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