Austenitic stainless steel, method for producing same and structure using same

Disclosed is an austenitic stainless steel with excellent stress corrosion cracking resistance which is characterized by consisting of, in weight%, C: 0.030% or less, Si: 0.1% or less, Mn: 2.0% or less, P: 0.03% or less, S: 0.002% or less, Ni: 11-26%, Cr: 17-30%, Mo: 3% or less, N: 0.01% or less and...

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Bibliographische Detailangaben
Hauptverfasser:	YONEZAWA TOSHIO, SAKAGUCHI YASUHIRO, OOKI SUGURU, TAKAMORI KENROU, KANASAKI HIROSHI, TANEIKE MASAKI, MIMAKIHIDEHITO, IWAMURA TOSHIHIKO, HIRANUMA NAOKI, SUZUKI SHUNICHI, ANAHARA NAOKI
Format:	Patent
Sprache:	chi ; eng
Schlagworte:	ALLOYS CHEMISTRY FERROUS OR NON-FERROUS ALLOYS GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUSMETALS OR ALLOYS MAKING METAL MALLEABLE BY DECARBURISATION, TEMPERING OR OTHERTREATMENTS METALLURGY METALLURGY OF IRON MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR POWER PLANT NUCLEAR REACTORS PHYSICS TREATMENT OF ALLOYS OR NON-FERROUS METALS
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Beschreibung
Zusammenfassung:	Disclosed is an austenitic stainless steel with excellent stress corrosion cracking resistance which is characterized by consisting of, in weight%, C: 0.030% or less, Si: 0.1% or less, Mn: 2.0% or less, P: 0.03% or less, S: 0.002% or less, Ni: 11-26%, Cr: 17-30%, Mo: 3% or less, N: 0.01% or less and the balance of Fe and unavoidable impurities. Also disclosed is a method for producing an austenitic stainless steel wherein a piece of the above-described austenitic stainless steel is subjected to a solution treatment at 1,000-1,150 1/2 C. Further disclosed are piping and reactor internal structures for nuclear reactors which employ the austenitic stainless steel.