Products tagged with 'irradiation'

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Acceleration Of Long-Range Ordering in NiCrFe Alloys Using Proton Irradiation

Product Number: ED22-18352-SG

Author: Cole Evered, Nicholas Aerne, David J. Sprouster, Julie D. Tucker

Publication Date: 2022

$20.00

The extension of nuclear reactor lifetimes beyond 40 years requires the qualification of plant components to ensure performance past their initial design requirements. Nickel-based alloys containing chromium (NiCr) are of concern at these extended lifetimes, as these types of alloys form an embrittling precipitate phase. Below a critical temperature—which is above the normal 300-400⁰C reactor operating temperatures—NiCr alloys form a stable, fully coherent MoPt2-typelong-range ordered (LRO) phase with stoichiometry Ni2Cr.

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Life Beyond 80: Can Concrete Degradation’ Synergetic Modes Become Showstoppers for Light Water Reactors?

Product Number: ED22-17261-SG

Author: Yann Le Pape, Elena Tajuelo Rodriguez, Bethel Amani Cheniour, Mohammed Alnaggar, Paula Bran Anleu, Thomas M. Rosseel, David Arregui Mena, Adam Brooks

Publication Date: 2022

$20.00

The US light water reactor (LWR) fleet is a strategic US asset for meeting the demand for clean, sustained, and affordable energy. Extended operations are governed by endogenous (e.g., aging management, operation costs) and exogenous (e.g., natural gas, deployment of advanced nuclear reactors) economic factors but also by technical issues associated with doubling the original 40 year license period. Materials aging includes all critical components of the reactors, such as internals, reactor pressure vessel, cabling, and concrete structures.

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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.

Products tagged with 'irradiation'

Acceleration Of Long-Range Ordering in NiCrFe Alloys Using Proton Irradiation

Life Beyond 80: Can Concrete Degradation’ Synergetic Modes Become Showstoppers for Light Water Reactors?

Zr(Fe,Cr)2 Precipitate Amorphization and Iron Redistribution in Zircaloy-4 Using a Two-Step Proton Irradiation

Association for Materials Protection and Performance