Residual stresses in a welded zircaloy cold neutron source containment vessel

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dc.contributor.authorBendeich, PJen_AU
dc.contributor.authorLuzin, Ven_AU
dc.contributor.authorLaw, Men_AU
dc.date.accessioned2025-07-25T13:03:43Zen_AU
dc.date.available2025-07-25T13:03:43Zen_AU
dc.date.issued2012-09-10en_AU
dc.date.statistics2024-11en_AU
dc.descriptionPhysical copies of the abstract book held by ANSTO Library at DDC: 620.1123/20. Some papers from conference have been published in Materials Science Forum Vol. 777 available here: https://doi.org/10.4028/www.scientific.net/MSF.777en_AU
dc.description.abstractZirconium alloys are widely used in the nuclear industry because of their relative high strength, neutron transparency, resistance to high neutron-irradiation environment and corrosion resistance. One application for Zirconium alloy Zr-2.5Nb is the vacuum confinement vessel utilised in the cold neutron source of the OPAL research reactor at ANSTO. Having a total length of more the 3 meters, it is made of two sections joined using electron beam welding. The weld and the nearby regions are critical for the performance and integrity of the component and therefore understanding of the residual stresses development within the weld is important in connection to (i) evolution of fine dual phase α/b microstructure and crystallographic texture (ii) and stress-related radiation induced phenomena, such as grain growth, creep and sub-critical crack growth by delayed hydride cracking. The stresses were measured in and around an electron beam weld produced during the development of this component of the OPAL Cold Neutron Source. The effects of a large grain size in the weld were reduced by taking advantage of rotational symmetry and rotating the sample to increase the swept volume. Due to the heat-treatment after welding, the stresses were very low, less than 10% of the yield strength of the material, in both the hoop and axial directions. As a result of phase transformation effects during the welding process the final stresses are compressive in the weld, which reduces the likelihood of fracture or of hydride formation in this region. The highest stresses are in the parent material adjacent to the weld where the toughness is expected to be higher than in the weld material.en_AU
dc.identifier.booktitleMECA SENS 2013 : 7th International Conference on Mechanical Stress Evaluation by Neutron and Synchrotron Radiation.en_AU
dc.identifier.citationBendeich, P., Luzin, V., & Law. M. (2012). Residual stresses in a welded zircaloy cold neutron source containment vessel. Presentation to MECA SENS 2013: 7th International Conference on Mechanical Stress Evaluation by Neutron and Synchrotron Radiation, 10-12 September 2012, Sydney, Australia, (pp. 60).en_AU
dc.identifier.conferenceenddate2012-09-12en_AU
dc.identifier.conferencenameMECA SENS 2013 : 7th International Conference on Mechanical Stress Evaluation by Neutron and Synchrotron Radiationen_AU
dc.identifier.conferenceplaceLucas Heights, New South Walesen_AU
dc.identifier.conferencestartdate2012-09-10en_AU
dc.identifier.editorsAustralian Nuclear Science and Technology Organisationen_AU
dc.identifier.pagination60en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/16344en_AU
dc.publisherAustralian Nuclear Science and Technology Organisationen_AU
dc.subjectZirconium alloysen_AU
dc.subjectNeutronsen_AU
dc.subjectCorrosion resistanceen_AU
dc.subjectCold neutronsen_AU
dc.subjectWeldingen_AU
dc.subjectBeamsen_AU
dc.subjectHydridesen_AU
dc.subjectCracksen_AU
dc.titleResidual stresses in a welded zircaloy cold neutron source containment vesselen_AU
dc.typeConference Abstracten_AU
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