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Study of Microstructure, Hydrogen Solubility, and Corrosion of Ta-Modified Zr–1Nb Alloys for Nuclear Applications
Modified Zr–1Nb alloys with Ta additionsTa addition is a potential strategy to improve structural alloys for nuclear reactors. The effects of Ta on...
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Development of Advanced Nuclear Structural Materials for Sustainable Energy Development
Structural materials used in nuclear reactors face many challenges due to elevated temperature operation, high neutron flux induced transmutations...
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Comparison of calculated and measured radionuclide inventory of a Zircaloy-4 cladding tube plenum section
Cladding tubes of water-cooled nuclear reactors are usually made of Zircaloy and are an important retaining element for radionuclides present in the...
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Experimental investigation and correlation of elevated temperature mechanical behaviour of Zr-2.5Nb alloy
In the current work, the high-temperature deformation behaviour of Zr-2.5Nb alloys used in pressurized heavy water reactors has been studied....
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Effect of Friction Coefficient and Feed Rates on Residual Stresses of Zr-4 Processed by Swaging
Zirconium alloy has been extensively used as a cladding material in nuclear power reactors due to its low neutron absorption cross section, excellent...
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Structural Materials in Nuclear Energy Sector
The nuclear energy sector makes use of a variety of materials for different functions. These are mostly alloys with different metals, some compounds...
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Orientation-Dependent Tensile Flow Behavior of Zircaloy-4 at Room Temperature
Present work describes a correlation between texture and sample orientation-based flow parameters of three different zircaloy-4 sheet materials. The...
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The Phase Transitions Behavior during Hydrogenation and Defect Structure Investigation in an E110 Zirconium Alloy with a Hydride Rim
AbstractIn this work, we have investigated the defect structure of an E110 zirconium alloy after saturation with hydrogen by means of the...
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Effect of the Stressed State on the Phase Transformations in Zirconium-Based Alloys
AbstractThe crystallographic aspects of the phase transformations in zirconium alloys under compressive stresses are studied, and the changes in the...
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Biaxial fatigue property enhancement of gradient ultra-fine-grained Zircaloy-4 prepared by surface mechanical rolling treatment
Surface mechanical rolling treatment (SMRT) was applied to modify the microstructure and biaxial fatigue properties of Zircaloy-4 tubes. Gradient...
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Recent Advances in Joining of Zirconium and Zirconium Alloy for Nuclear Industry
Due to its moderate mechanical properties, low neutron absorption, excellent processability, superior irradiation, and corrosion resistance, as well...
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Total Reflection X-ray Fluorescence: Suitability and Applications for Material Characterization
Total Reflection X-Ray Fluorescence (TXRF) is a sophisticated advanced version of Energy Dispersive X-ray Fluorescence (EDXRF). It is an advanced...
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Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review
The US Department of Energy is working with fuel vendors to develop accident tolerant fuels (ATF) for the current fleet of light water reactors...
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Wear
WearWear of SG tubesTube has been presented in the chapter dedicated to SG issues (Chap. 6 ). Some typical...
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High-temperature steam oxidation behavior of an FeCrAl alloy with controlled addition of Mo
The high-temperature steam oxidation behavior of Fe-13Cr-6Al-xMo (x = 1, 2, 3 or 4) is assessed from 1000 to 1300 °C. The oxidation film is dominated...
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The Oxidization Behavior of Zr–2.5Nb(wt%) Alloy in Dry Air
The oxidation behavior of Zr–2.5Nb alloy at 500 °C, 600 °C and 700 °C from 0.5 to 24 h in a tubular furnace with dry air was systematically...
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Advanced High-Temperature Structural Materials in Petrochemical, Metallurgical, Power, and Aerospace Sectors—An Overview
Metallic materials for structural applications are designed to withstand mechanical forces of high and varying amplitude in static or dynamic loading...
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Tensile and Fracture Behaviour of Zr-4 Alloy Processed Through Swaging
Production of Zirconium alloys for nuclear power reactor comprises of a number of steps during swaging and each step influences microstructural and...
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Effect of Inhomogeneous Nucleation of Hydride at α/β Phase Boundary on Microstructure Evolution of Zr–2.5 wt%Nb Pressure Tube
We analyzed the microstructural characteristics such as number density and length and width of hydrides in Zr–2.5 wt%Nb pressure tube. The hydrogen...
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The Influence of Specimen Surface Roughness and Temperature of Steam Injection on Breakaway Oxidation Behavior of Zry-4 Fuel Cladding in Steam at 1273 K
The steam oxidation behavior of Zr-based Zircaloy-4 fuel cladding was studied at 1273 K with two different surface roughness levels. Steam was...
