2019
DOI: 10.1016/j.jmapro.2019.01.048
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Co-extrusion of Zircaloy-2 and Zr-Sn alloy for double clad tube manufacturing: Numerical simulation and experimental validation

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Cited by 7 publications
(5 citation statements)
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“…Furthermore, the total elongation of the multilayered structures was lower than that of the single co-extruded plates and was attributed to the increased fraction of intermetallic compounds. The bimetallic billet assembly for conventional extrusion is typically achieved through compound casting, where the core is cast first then the shell [7,8] or is fusion-welded along the core-shell interface [9] to promote good metallurgical bonding in the cladded tubes. For instance, Chen et al [7] fabricated bimetallic billets through the compound-casting process using 7075 Al as the core and 6060 as the cladding, then completed hot co-extrusion of the cast billets.…”
Section: Introductionmentioning
confidence: 99%
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“…Furthermore, the total elongation of the multilayered structures was lower than that of the single co-extruded plates and was attributed to the increased fraction of intermetallic compounds. The bimetallic billet assembly for conventional extrusion is typically achieved through compound casting, where the core is cast first then the shell [7,8] or is fusion-welded along the core-shell interface [9] to promote good metallurgical bonding in the cladded tubes. For instance, Chen et al [7] fabricated bimetallic billets through the compound-casting process using 7075 Al as the core and 6060 as the cladding, then completed hot co-extrusion of the cast billets.…”
Section: Introductionmentioning
confidence: 99%
“…The extrudates exhibited a defect-free, metallurgically bonded interface between the core and cladding. The importance of fusion-welded bimetallic billets can be noted through the co-extrusion of Zircaloy-2 and Zr-Sn carried out by Jha et al [9]. The absence of welding and degassing for the bimetallic billets led to the formation of voids along the core-cladding interface, while adding these steps during billet preparation led to a defectfree interface.…”
Section: Introductionmentioning
confidence: 99%
“…Zr-2 (98% Zr, 1.6% Sn, 0.15% Fe, 0.1% Cr, 0.05% Ni) (Nishino et al, 1996;Masterson, 2017), SiC (48.3% Si, 51.7% C) (Sauder et al, 2013), and VC (80.9% V, 19.1% C) were developed as fuel cladding in LWRs to solve this undesired situation in reactor life and energy production. Zr-2, SiC, and VC have outstanding properties of not spreading cracks throughout the cladding, irradiation stability, low stress levels, the ability to maintain their mechanical properties and chemical inactivity at high temperatures, and resistance to vapor oxidation (Williams et al, 1996;Edsinger and Murty, 2001;Korkut et al, 2016;Jha et al, 2019;Singh et al, 2019). In nuclear reactors, a low thermal neutron absorption cross-section is preferred to increase energy production.…”
Section: Introductionmentioning
confidence: 99%
“…Zirconium alloy extrusion methods are widely used in the production of pipes and other components needed in nuclear power, but in this case, the starting alloys for the commercial extrusion process were castings. For example, the cladding tubes are fabricated from tube-reduced extrusions (TREX) using the Pilger process [22,23]. The main problem impeding the prepared zirconium mixtures and carrying out the extrusion process is the flammability of zirconium powders [24].…”
Section: Introductionmentioning
confidence: 99%