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The effect of neutron irradiation on the mechanical properties of welded zircaloy-2

Technical Report:

Abstract

Zircaloy-2 tensile specimens, subsize impact bars and representative spigot welds were subjected to three NRX cycles in the X-5 loop. Average loop temperature was 260{sup o}C over the three cycles. One group of tensile specimens was heat-treated in vacuum at 900{sup o}C for 40 minutes, another group contained welded areas in the centre of the gauge length and a third group was hydrided after welding. Notches of the impact specimens were located in the fusion zone of the weld, Spigot welds were made on autoclaved and unautoclaved simulated production assemblies. The transition temperature of Zircaloy-2 increased appreciably upon welding. This was accompanied by a decrease in absorbed energy values for all temperatures between 0{sup o} and 300{sup o}C. Neutron irradiation had no effect on the impact properties of welded. Zircaloy-2. Welding decreased the uniform and total elongation at room temperature and at 260{sup o}C, and increased the 260{sup o}C PL, YS and UTS. Hydriding to a nominal 100 ppm hydrogen had no effect on the unirradiated tensile properties at either test temperature. The heat treatment decreased the strength properties but did not affect the ductility. Neutron irradiation increased the YS of the welded and hydrided material by 20% and the  More>>
Authors:
Publication Date:
Jul 15, 1962
Product Type:
Technical Report
Report Number:
AECL-1566; CRGM-1093
Resource Relation:
Other Information: 30 refs., 7 tabs., 19 figs.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; IRRADIATION; NEUTRON FLUX; NRX REACTOR; TENSILE PROPERTIES; WELDED JOINTS; ZIRCALOY 2
OSTI ID:
22034842
Research Organizations:
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
TRN: CA1200129123848
Availability:
Available from INIS in electronic form
Submitting Site:
CANN
Size:
52 page(s)
Announcement Date:
Feb 04, 2013

Technical Report:

Citation Formats

Evans, D G. The effect of neutron irradiation on the mechanical properties of welded zircaloy-2. Canada: N. p., 1962. Web.
Evans, D G. The effect of neutron irradiation on the mechanical properties of welded zircaloy-2. Canada.
Evans, D G. 1962. "The effect of neutron irradiation on the mechanical properties of welded zircaloy-2." Canada.
@misc{etde_22034842,
title = {The effect of neutron irradiation on the mechanical properties of welded zircaloy-2}
author = {Evans, D G}
abstractNote = {Zircaloy-2 tensile specimens, subsize impact bars and representative spigot welds were subjected to three NRX cycles in the X-5 loop. Average loop temperature was 260{sup o}C over the three cycles. One group of tensile specimens was heat-treated in vacuum at 900{sup o}C for 40 minutes, another group contained welded areas in the centre of the gauge length and a third group was hydrided after welding. Notches of the impact specimens were located in the fusion zone of the weld, Spigot welds were made on autoclaved and unautoclaved simulated production assemblies. The transition temperature of Zircaloy-2 increased appreciably upon welding. This was accompanied by a decrease in absorbed energy values for all temperatures between 0{sup o} and 300{sup o}C. Neutron irradiation had no effect on the impact properties of welded. Zircaloy-2. Welding decreased the uniform and total elongation at room temperature and at 260{sup o}C, and increased the 260{sup o}C PL, YS and UTS. Hydriding to a nominal 100 ppm hydrogen had no effect on the unirradiated tensile properties at either test temperature. The heat treatment decreased the strength properties but did not affect the ductility. Neutron irradiation increased the YS of the welded and hydrided material by 20% and the heat treated YS by 40%. Irradiation also increased the 260{sup o}C strength properties of the as-welded material. It was found that the unautoclaved spigot welds had a generally higher tensile strength than the autoclaved and welded specimens. For specimens welded in either condition, the outer welds of the 19-element bundle had a lower average breaking load than the inner welds. Neutron irradiation had no effect on the tensile strength of these welds. It was also demonstrated that a cup-and-cone type of fracture could be produced in a bend test. These fractures were similar to those observed in irradiated fuel bundles which had been damaged during transfer operations. A large amount of scatter rendered some results inconclusive. This was especially the case for the room-temperature as-welded results and for the majority of the total and uniform elongation measurements. (author)}
place = {Canada}
year = {1962}
month = {Jul}
}