Long-term test results of promising new zirconium alloys. [Ozhennite 0. 5]

Conference · Fri Jan 01 04:00:00 EST 1982 · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)

OSTI ID:6312994

Castaldelli, L; Fizzotti, C; Lunde, L

A series of new alloys has been long-term tested in different nuclear reactors and environments together with other alloys, including Zr-2.5Nb, Ozhennite 0.5, and Zircaloy-2. One of the new alloys with the composition of Zr-1Nb-1Sn-0.5Fe has significantly improved properties. The zirconium-niobium alloys have corrosion properties similar to Zircaloy-2 in the temperature range 240 to 400 degree C while they are better at 450 degree C and above. Elongation was markedly reduced by irradiation in all the alloys. Uniform elongations of about 1 percent were observed in the 2.5Nb alloys while the highest uniform elongation of 2 to 3 percent was shown by the Zr-1Nb-1Sn-0.5Fe alloy. 18 refs.

• Research Organization: CNEN, Rome, Italy
• OSTI ID: 6312994
• Report Number(s): CONF-800834-
• Conference Information: Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360101 -- Metals & Alloys-- Preparation & Fabrication
360105* -- Metals & Alloys-- Corrosion & Erosion
ALCOHOLS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CORROSION
CRACKS
ELEMENTS
HALOGENS
HEAT TREATMENTS
HIGH TEMPERATURE
HYDROXY COMPOUNDS
IODINE
IRON ADDITIONS
IRON ALLOYS
METHANOL
NIOBIUM ALLOYS
NONMETALS
ORGANIC COMPOUNDS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TIN ALLOYS
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS