ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. EVALUATION OF LONG TERM GAS CORROSION OF HEAT RESISTANT ALLOYS FOR USE AS GAS-COOLED REACTOR FUEL CLADDING

Technical Report · Mon Apr 01 04:00:00 EST 1963

OSTI ID:4695564

Brunhouse, J S; Titus, G W

Seven nickel-based alloys and one austenitic stainless steel alloy were tested for periods up to 10,000 hr at 1750 c- F and up to 4,000 hr at 1850 c- F in the ML-l reference coolant (99.5 vol% N/sub 2/ + 0.5 vol% O/sub 2/) and air to evaluate the materials and to provide design data for the selection of the fuel cladding for the ML-l reactor. Hastelloy X, Inconel 600, Inconel 702, Inconel 604, Hastelloy R-235, G-157, Nichrome V, Nichrome V-Cb, and AISI Type 310 stainless steel were examined for gas corrosion effects and internal microstructural changes after 1000, 2500, 5000, 7500, and 10,000 hr exposure. Samples were evaluated by weight change measurements, oxide penetration measurements, tensile testing, and metallographic examination. X-ray diffraction, x-ray fluorescence, and electron microscope analyses were performed primarily on Hastelloy X. The results showed that Hastelloy X has excellent oxidation and nitriding resistance at 1750 c- F and this material was recommended for use as cladding for the ML-1 fuel elements. (auth)

• Research Organization: Aerojet-General Nucleonics, San Ramon, Calif.
• NSA Number: NSA-17-025723
• OSTI ID: 4695564
• Report Number(s): IDO-28605
• Country of Publication: United States
• Language: English

Related Subjects

AIR
ALLOYS
ALUMINUM ALLOYS
AUSTENITE
CHROMIUM ALLOYS
COATING
CORROSION
DIFFRACTION
DIFFUSION
ELECTRON MICROSCOPY
FLUORESCENCE
FUEL CANS
FUEL ELEMENTS
GAS COOLANT
HASTELLOY
HEAT RESISTING METALS
HIGH TEMPERATURE
INCONEL ALLOYS
MATERIALS TESTING
MEASURED VALUES
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
ML-1
MOLYBDENUM ALLOYS
NICHROME
NICKEL ALLOYS
NIOBIUM ALLOYS
NITRIDES
NITROGEN
OXIDATION
OXYGEN
PLANNING
REACTORS
STABILITY
STAINLESS STEELS
TENSILE PROPERTIES
TITANIUM ALLOYS
USES
VARIATIONS
WEIGHT
X RADIATION