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Products tagged with 'zirconium'

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Picture for A New Bimetallic Solution To Manage Corrosion In Nitric Acid Plants
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51318-11284-A New Bimetallic Solution To Manage Corrosion In Nitric Acid Plants

Product Number: 51318-11284-SG
Author: Angela Philipp / Daniel Gullberg
Publication Date: 2018
$20.00

With the development of a bimetallic tube with an inner tube made of zirconium (R60702) and an outer tube in UNS S31002, it was possible to manage the challenge to provide zirconium-level performance at an affordable price.
Picture for Corrosion Behavior of Metal-Ceramic Composites
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Corrosion Behavior of Metal-Ceramic Composites

Product Number: 51321-16931-SG
Author: Kentaro Lunn; Vilupanur Ravi
Publication Date: 2021
$20.00
Picture for Fatigue Properties of Zirconium and Zirconium Alloys and their Application in Design and FFS
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Fatigue Properties of Zirconium and Zirconium Alloys and their Application in Design and FFS

Product Number: 51323-19188-SG
Author: Nathaniel G. Sutton, Phillip E. Prueter
Publication Date: 2023
$20.00

Zirconium and Zirconium alloys have been used successfully in a range of corrosive environments, both as base materials and as cladding on other backing materials. Zirconium is used extensively as fuel-rod “cladding” in nuclear reactors. In the chemical process industries, Zirconium and its alloys are used in urea production, acetic acid and vinyl acetate production, and various sulfuric, hydrochloric, and organic acid services.
Picture for Investigating The Mechanisms Of Irradiation Creep Using TEM With In-Situ Ion Irradiation And Straining
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Investigating Irradiation Creep of Zircaloy-4 Using In-Situ Proton Irradiation and Transmission Electron Microscopy

Product Number: Ed22-18344-SG
Author: Conor Gillen, Graeme Greaves, Rhys Thomas, Adeel Shaikh, Robert Harrison, Alistair Norris, Alistair Garner, Aidan Cole-Baker
Publication Date: 2022
$20.00

Zirconium alloys are used in civil nuclear reactors as fuel cladding, due to their relatively low neutron absorption cross section and being ability to maintain integrity during operation in a challenging environment – under elevated temperature, in corrosive water, under stress, and while being bombarded with different types of irradiation. In anisotropic materials, such as the hexagonal close packed Zr crystal structure, irradiation-induced defects diffuse at different rates in different crystallographic directions.
Picture for Simulation Of Neutron Irradiation Effects On Zr(Fe,Cr)2 Precipitates In Zircaloy-4 Using A Two-Step Proton Irradiation
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Zr(Fe,Cr)2 Precipitate Amorphization and Iron Redistribution in Zircaloy-4 Using a Two-Step Proton Irradiation

Product Number: ED22-17211-SG
Author: Peng Wang, Gary S. Was
Publication Date: 2022
$20.00

The corrosion of zirconium-based alloys is a service life-limiting factor in fuel rod performance. Mechanistic understanding of the corrosion process under reactor irradiation conditions still alludes to the nuclear industry. Pre-transition corrosion behavior of Zircaloy-4 has been reported to show a minimal effect from the irradiation environment, and the in-reactor corrosion kinetics is athermal and similar to the ex-situ autoclave corrosion exposure. However, the post-transition in-reactor corrosion kinetics depends on temperature and neutron flux. As discussed by Kammenzind et al. in Ref., the long-term post-transition corrosion rates of Zircaloy-4 are significantly accelerated in a PWR radiation environment over that observed with non-irradiated specimens in an autoclave environment.
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