ZIRCONIUM-NIOBIUM BINARY ALLOYS FOR BOILING WATER REACTOR SERVICE. PART II. CORROSION HYDROGEN EMBRITTLEMENT

Journal Article · Sat Jun 01 04:00:00 EDT 1963 · Journal of Nuclear Materials (Netherlands)

DOI:https://doi.org/10.1016/0022-3115(63)90170-3· OSTI ID:4691236

Klepfer, H H

Embrittlement by H produced during corrosion of spongebase, Zr -Ni binary alloys containing up to 4.2 wt% Nb was studied. Thin corrosion films in H/ sub 2/O and in steam were found to allow the passage of about 12% of the corrosionproduced H into the underlying metal; beta-quenched samples continued to show low pickup through thick oxide films, at least up to 454 mg/dm/sup 2/, in steam. Alpha-treated samples in steam showed about 25% pickup through thick films. Total H weight gains were equal to or less than those for Zircaloy-2 in all tests. Hydrogen solubility was apparently higher in the Zr-Nb alloys than in Zircaloy-2. Mechanical tests revealed a low susceptibility to corrosion H embrittlement in alpha-treated Zr --Nb alloys. Corrosion performance of the binaries in a simulated boiling water reactor environment was found to be poor, however. Average hydriding rates in higher order alloys containlng further additions of Fe, Cr, and Sb were not lower than those for the corresponding Zr - Nb binaries. (auth)

• Research Organization: General Electric Co., Pleasanton, Calif.
• NSA Number: NSA-17-032525
• OSTI ID: 4691236
• Journal Information: Journal of Nuclear Materials (Netherlands), Journal Name: Journal of Nuclear Materials (Netherlands) Vol. Vol: 9; ISSN JNUMA
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ALLOTROPY
ANTIMONY ALLOYS
BOILING
BRITTLENESS
CHROMIUM ALLOYS
CORROSION
FILMS
HEAT TREATMENTS
HYDROGEN
IRON ALLOYS
METALS, CERAMICS, AND OTHER MATERIALS
NIOBIUM ALLOYS
PERFORMANCE
PHASE DIAGRAMS
QUENCHING
REACTORS
SOLUBILITY
WATER COOLANT
ZIRCALOY
ZIRCONIUM ALLOYS