BERYLLIUM CORROSION. Quarterly Report to United States Atomic Energy Commission for the Period July 25, 1962 to September 25, 1962

Technical Report · Tue Oct 30 04:00:00 EST 1962

OSTI ID:4747994

Pemsler, J P; Kneppel, D S

Samples of Brush QMV Be powder, hot-pressed or extruded, have shown no indication of accelerated corrosion after exposures up to 145 days in 343 deg C water. Some localized attack in the form of pits occurred in the first few days of exposure but thereafter the progress of attack was arrested. No improvement in the corrosion resistance of differenL types of Be in water at 343 deg C was obtained by pre-oxidation of Be. Extrusions of commercial compacts with varying BeO contents show erratic corrosion behavior. Most of the samples have lasted for 35 days with no signs of accelerated attack. Thus far no correlation is apparent between BeO content and corrosion behavior in 343 deg C water. High purity Be samples show extremely poor corrosion resistance. Cast and extruded Be alloys of Ni and Cr were corrosion tested, but the appearance of the samples indicated segregation. Previous work had shown that Be--Ni alloys were very promising in corrosion behavior. Corrosion test results in 650 deg C steam at atmospheric pressure do not appear to correlate with results obtained in 343 deg C water. (auth)

• Research Organization: Nuclear Metals, Inc., Concord, Mass.
• NSA Number: NSA-17-006568
• OSTI ID: 4747994
• Report Number(s): NMI-1905; EURAEC-506
• Country of Publication: United States
• Language: English

Related Subjects

BERYLLIUM
BERYLLIUM ALLOYS
CHROMIUM ALLOYS
CORROSION
CORROSION PROTECTION
DEFECTS
DISTRIBUTION
EXTRUSION
HIGH TEMPERATURE
IMPURITIES
MEASURED VALUES
METALS, CERAMICS, AND OTHER MATERIALS
NICKEL ALLOYS
OXIDATION
SEGREGATION
SINTERED MATERIALS
STEAM
WATER