Creep and rupture behavior of a special grade Hastelloy-X in simulated HTGR helium

Journal Article · Wed Aug 01 04:00:00 EDT 1984 · Nucl. Technol.; (United States)

OSTI ID:6476849

Kurata, Y; Kondo, T; Ogawa, Y

Creep and rupture tests were conducted for Hastelloy-XR (a modified version of the conventional Hastelloy alloy X) at 800, 900, and 1000/sup 0/C in simulated high-temperature gas-cooled reactor helium. Creep testing machines with special control of helium chemistry were used. As a result, the scatter of creep-rupture data could be reduced, and the variability of creep-rupture behavior due to manufacturing history could be resolved. Results of metallography and carbon analysis of ruptured specimens showed that the material improved resistance to corrosion in the helium environment, and carbon intrusion during the steady-state creep stage was suppressed to a negligible level. Under refined test conditions combined with the quality controlled material, it was demonstrated that there was little significant difference between helium and air in the creep-rupture results obtained at 800 to 1000/sup 0/C up to about 10/sup 4/h. The importance of maintaining the protective function of the surface oxide film of alloys was stressed in securing reproducibility and predictability of long-time creep performance.

• Research Organization: Japan Atomic Energy Research Institute, Tokai Research Establishment Materials Engineering Laboratory, Tokai-mura, Naka-gun Ibaraki-ken, 319-11
• OSTI ID: 6476849
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 66:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

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