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Titolo:
Optimized chemical composition, working and heat treatment condition for resistance to irradiation assisted stress corrosion cracking of cold worked 316 and high-chromium austenitic stainless steel
Autore:
Yonezawa, T; Iwamura, T; Fujimoto, K; Ajiki, K;
Indirizzi:
Mitsubishi Heavy Ind Ltd, Takasago R&D Ctr, Takasago, Hyogo 6768686, JapanMitsubishi Heavy Ind Ltd Takasago Hyogo Japan 6768686 yogo 6768686, Japan Mitsubishi Heavy Ind Ltd, Kobe Shipyard & Machinery Works, Kobe, Hyogo 6628585, Japan Mitsubishi Heavy Ind Ltd Kobe Hyogo Japan 6628585 e, Hyogo 6628585, Japan
Titolo Testata:
JOURNAL OF THE JAPAN INSTITUTE OF METALS
fascicolo: 5, volume: 64, anno: 2000,
pagine: 413 - 422
SICI:
0021-4876(200005)64:5<413:OCCWAH>2.0.ZU;2-Q
Fonte:
ISI
Lingua:
JPN
Keywords:
pressurized water reactor(PWR); stainless steel; irradiation assisted stress corrosion cracking(IASCC); stress corrosion cracking(SCC); grain boundary; carbides; primary water stress corrosion cracking(PWSCC);
Tipo documento:
Article
Natura:
Periodico
Settore Disciplinare:
Engineering, Computing & Technology
Citazioni:
12
Recensione:
Indirizzi per estratti:
Indirizzo: Yonezawa, T Mitsubishi Heavy Ind Ltd, Takasago R&D Ctr, Takasago, Hyogo 6768686, Japan Mitsubishi Heavy Ind Ltd Takasago Hyogo Japan 6768686 , Japan
Citazione:
T. Yonezawa et al., "Optimized chemical composition, working and heat treatment condition for resistance to irradiation assisted stress corrosion cracking of cold worked 316 and high-chromium austenitic stainless steel", J JPN METAL, 64(5), 2000, pp. 413-422

Abstract

The authors have reported that the primary water stress corrosion cracking(PWSCC) in baffle former bolts made of austenitic stainless steels for PWRafter long-term operation is caused by irradiation-induced grain boundary segregation. The resistance to PWSCC of simulated austenitic stainless steels whose chemical compositions are simulated to the grain boundary chemical compositionof 316 stainless steel after irradiation increased with decrease of the silicon content, increases of the chromium content, and precipitation of M23C6 carbides at the grain boundaries. In order to develop resistance to irradiation assisted stress corrosion cracking in austenitic stainless steels, optimized chemical compositions and heat treatment conditions for 316CW and high-chromium austenitic stainless steels for PWR baffle former bolts were investigated. For 316CW stainless steel, ultra-low-impurities and high-chromium content are beneficial. About 20% cold working before aging and after solution treatment has also been recommended to recover sensitization and make M23C6 carbides coherent with the matrix at the grain boundaries. Heating at 700 to 725 degrees C for 20 to 50 h was selected as a suitable aging procedure. Cold working of 5 to 10% after aging produced the required mechanical properties. The optimized composition of the high-chromium austenitic stainless steel contents 30% chromium, 30% nickel, and ultralow impurity levels. This composition also reduces the difference between its thermal expansion coefficient and that of 304 stainless steel for baffle plates. Aging at 700 to 725 degrees C for longer than 40 h and cold working of 10 to 15% after aging wereselected to meet mechanical property specifications.

ASDD Area Sistemi Dipartimentali e Documentali, Università di Bologna, Catalogo delle riviste ed altri periodici
Documento generato il 29/03/20 alle ore 08:46:42