skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Evaporation behavior of Hastelloy-X alloys in simulated very high temperature reactor environments

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:6476649

A sequential analysis was made on the material degradations during exposure of nickel-base corrosionresistant austenitic alloys to simulated very high temperature reactor environments. The materials tested were two modified versions of Hastelloy-X in terms of both increased manganese content for improved compatibility and decreased manganese content for possible adverse effects. Quantitative analysis of the specimens after exposure for 1000 h at several temperature steps from 850 to 1050/sup 0/C have revealed the temperature-dependent aspects of the processes including the depletion of chromium and manganese due to oxidation, evaporation, and carbon transfer into and/or from the materials. The material with enriched manganese, developed and specified as Hastelloy-XR, showed enhanced resistance to loss of chromium in terms of both oxidation and evaporation.

Research Organization:
Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken
OSTI ID:
6476649
Journal Information:
Nucl. Technol.; (United States), Vol. 66:2
Country of Publication:
United States
Language:
English