Creep rupture strength of heat affected zone for 9Cr ferritic heat resisting steels

Nuclear Engineering and Design

Volumn 196, Issue 1, 2000, Pages 51-61

  Otoguro, Y ^a   Matsubara, M ^a   Itoh, I ^a   Nakazawa, T ^a  

^a GUNMA UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CARBIDES; CHROMIUM ALLOYS; COAGULATION; CREEP; FERRITE; GRAIN GROWTH; GRAIN SIZE AND SHAPE; HARDNESS; HEAT AFFECTED ZONE; STRENGTH OF MATERIALS; SUPERALLOYS; WELDS;

CREEP RUPTURE STRENGTH;

STEEL;

EID: 0033888780     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00232-0     Document Type: Article

References (8)

1. Fujita T., Asakura K., Sawada T. et al. Creep rupture strength and microstructure of low C-10Cr-2Mo heat resisting steels with V and Nb. Metall. Trans. A. 12A:1981;1071-1078.
2. Gunz, G., Pellicani, F., Houts, J., et al., 1978. Main characteristics of 9% chromium-2% molybdenum-niobium-vanadium steel tubes/influence of variations of composition and thermal treatment. In: Proceedings of International Conference on Ferritic Steels for Fast Breeder Reactor Steam Generators. BNES, London, pp. 164-170.
3. Hashimoto, K., Yamanaka, M., Otoguro, Y., et al., 1983. Newly developed 9Cr-2Mo-Nb-V Steel, Proceedings of Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technology, 19-23 June, Snowbird, Utah.
4. King, R.T., Egnell, L., 1978. Historical development of steels containing 8-10% Cr and 0-2% Mo and future directions for LMFBR applications. In: Proceedings of International Conference on Ferritic Steels for Fast Breeder Reactor Steam Generators. BNES, London, pp. 74-81.
5. Otoguro Y., Yagi N., Kumagi S. et al. Reduced activation Cr-W ferritic heat-resisting steels, current advances in materials and processes. Rep. ISIJ Meeting. 2(3):1989;840.
6. Otoguro Y., Itah I., Ohta T. et al. Influences of Nb and C content on creep rupture strength of a 9Cr-1Mo-V-Nb steel with simulated HAZ heating. J. High Press. Inst. Jpn. 32(1):1994;4-12.
7. Scott, J.L., Bloom, E.E., Grossbeck, M.L., et al., 1980. Progress in the development of the blanket structural material for fusion reactors. In: Proceedings of the Fourth Topical Meeting on the Technology of Controlled Nuclear Fusion, 14-17 October. Pennsylvania, pp. 1661-1672.
8. Yukitoshi T., Nishida K., Oda T. et al. Low alloy high-strength steel for boiler tubes (low C-9Cr-2Mo). J. Press. Vessel Technol. 98:1976;173-178.