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BERYLLIUM CORROSION. Quarterly Report to United States Atomic Energy Commission for the Period September 25, 1962 to December 31, 1962

Technical Report ·
OSTI ID:4756979
Additional testing of samples of hot-pressed beryllium prepared from CR- grade powder (--200 mesh) confirmed that the higher purity beryllium shows poor corrosion resistance. Samples of extruded Brush QMV powder survived 162 days in 343 deg C water. Additional exposure resulted in accelerated corrosion. However, the indications are that the sudden breakdown in corroslon resistance may be due to some variable in the testing conditions. Samples exposed in water with a pH of over 8 generally exhibit poor corrosion resistance. However, lowering the pH did not insure good corrosion resistance. Failure of the samples in the autoclave shows no correlation with final pH. Contact of beryllium with stainless steel, platinum, zirconium, and Zircaloy-2 produced no evidence of any gross galvanic corrosion in high temperature water. Evidence was obtained that the occurrence of boiling on the surface of samples exposed in high temperature water is a cause of accelerated attack. However, water corrosion tests in autoclaves overpressurized with argon showed that failures still can occur. Metallic impurity additions were made to CR-grade (--200 mesh) powder by blending of the elemental powders for the purpose of determining which impurities are responsible for the improved corrosion resistance of beryllium prepared from the less pure commercial powders. (auth)
Research Organization:
Nuclear Metals, Inc., West Concord, Mass.
NSA Number:
NSA-17-014769
OSTI ID:
4756979
Report Number(s):
NMI-1908; EURAEC-579
Country of Publication:
United States
Language:
English

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Related Subjects

ACIDITY
ARGON
BERYLLIUM
BOILING
COMPACTING
CORROSION
EXTRUSION
FAILURES
HOT WORKING
IMPURITIES
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
PLATINUM
POWDERS
PRESSURE
PRESSURE VESSELS
STABILITY
STAINLESS STEELS
SURFACES
WATER
ZIRCALOY
ZIRCONIUM