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Zirconium alloy

About: Zirconium alloy is a research topic. Over the lifetime, 6548 publications have been published within this topic receiving 78954 citations. The topic is also known as: zircaloy.


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Journal Article
TL;DR: In this paper, a detailed microscopic examination of incipient i.d. cladding defects in some Maine Yankee Core I fuel rods determined that these defects and clad penetrations in related rods were caused by a PCI mechanism that was promoted by chemical species, i.e., stress corrosion cracking.
Abstract: Results of three related projects undertaken to elucidate the mechanism of Zircaloy cladding fracture caused by pellet-cladding interaction (PCI) in water reactor fuel rods are described. A detailed microscopic examination of incipient i.d. cladding defects in some Maine Yankee Core I fuel rods determined that these defects and clad penetrations in related rods were caused by a PCI mechanism that was promoted by chemical species, i.e., stress corrosion cracking (SCC). A consideration of the internal fuel rod chemistry and fission product distribution indicates that one potential agent for SCC of Zircaloy cladding is iodine released from CsI deposited on the i.d. surface and another is cadmium metal. A simple analytical model of crack propagation in Zircaloy cladding based on linear elastic fracture mechanics indicates two possible rate-controlling events, depending on the value of the stress intensification K/sub ISCC/. If K/sub ISCC/ for irradiated Zircaloy is very low, i.e., on the order of 2.2 to 3.3 MN/m/sup 3///sup 2/ (2 to 3 ksi ..sqrt..in.), crack growth is relatively easy, and hence the rate-limiting step must be the nucleation of sharp cracks in the cladding i.d. surface. However, if K/sub ISCC/ for irradiated Zircaloy is relatively large, i.e., greater than or equalmore » to 11 MN/m/sup 3///sup 2/ (10 ksi ..sqrt..in.), a high interfacial friction coefficient, for example, caused by fuel-clad bonding, would be required to propagate the i.d. defect.« less

34 citations

Patent
28 Jan 1983
TL;DR: This article modified standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in a product having superior high temperature steam corrosion resistance.
Abstract: Modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.

34 citations

Journal ArticleDOI
TL;DR: In this paper, a simple instability condition based on the Ziegler's continuum principles is extended for delineating the regions of unstable metal flow/occurrence of fracture or defects, utilizing the flow stress data of Zr-2.5Nb-0.5Cu.
Abstract: For the development of processing maps to zirconium alloys, a simple instability condition based on the Ziegler's continuum principles as applied to large plastic flow is extended for delineating the regions of unstable metal flow/occurrence of fracture or defects, utilizing the flow stress data of Zr-2.5Nb-0.5Cu. An attempt is made to fit the measured flow stress data in a constitutive equation, useful in the finite element process models. Instability maps at different strain levels were superimposed while delineating the unstable regions in the processing maps. This phenomenon takes into account the dependence of strain rate sensitivity and strain hardening coefficient of the material on the plastic instability during hot deformation. The applicability of the developed processing map has been examined by comparing with the reported microstructural observations of the deformed compression specimens of various zirconium alloys. It is found that the processing map is practically usable in the real fabrication process for the zirconium alloys.

34 citations

01 Sep 1980
TL;DR: In this article, the authors present an assessment of damage to light-water-reactor fuel during a reactivity-initiated accident and comments on the adequacy of the present Nuclear Regulatory Commission design requirements.
Abstract: This article presents an assessment of damage to light-water-reactor fuel during a reactivity-initiated accident and comments on the adequacy of the present Nuclear Regulatory Commission design requirements. Results from early experiments in the Special Power Excursion Reactor Test (SPERT) are reviewed and compared with results from recent computer simulations and Power Burst Facility tests. A progression of fuel-rod and cladding damage events is presented. High-strain-rate deformation of relatively cool irradiated cladding early in the transient can result in fracture at a radial average peak fuel enthalpy of approx. 140 cal/g UO/sub 2/. Volume expansion of previously irradiated fuel on melting can cause deformation and rupture of the cladding and coolant channel blockage at higher peak enthalpies. When cladding temperatures reach values near the melting point, variations in coolant conditions around and along the rod cause thickening and thinning of the cladding. The regions of cladding wall thinning are subsequently oxidized to brittle oxygen-stabilized alpha Zircaloy and zirconium dioxide and fracture during quenching when the radial average peak fuel enthalpy is 250 cal/g UO/sub 2/ or above. The mode of rod failure is strongly affected by previous irradiation and peak fuel enthalpy.

33 citations

Journal ArticleDOI
TL;DR: In this article, the texture and grain-boundary characteristics of oxide are dependent on the texture of metal substrate, and intrinsic factors affecting the oxide microstructure are presented. And a thermodynamic model is developed to analyze the nucleation and the stress-induced reorientation of intergranular hydrides.

33 citations


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Performance
Metrics
No. of papers in the topic in previous years
YearPapers
202395
2022215
2021137
2020164
2019194
2018219