Effect of Silicon Content on the Corrosion Resistance and Radiation- Induced Embrittlement of Materials for Advanced Heavy Liquid Metal Nuclear Systems

Authors

Ajit K. Roy, University of Nevada, Las VegasFollow

Document Type

Annual Report

Publication Date

2006

Publisher

University of Nevada, Las Vegas

Publisher Location

Las Vegas (Nev.)

First page number:

44

Last page number:

45

Abstract

This task is primarily focused on the evaluation of the effect of Si content on the susceptibility of modified 9Cr-1Mo-0.24V steel to stress corrosion cracking (SCC) and localized cracking in both molten lead-bismuth eutectic (LBE) and an aqueous solution of acidic pH.

Further, significant efforts are in progress to characterize the deformation mechanism of modified T91 grade steel as a function of temperature and strain rate. Simultaneously, surface analyses of the tested materials are ongoing using state-of-the-art techniques including scanning electron microscopy (SEM) and transmission electron microscopy (TEM).

Keywords

Corrosion and anti-corrosives; Eutectic alloys; Lead-bismuth alloys; Martensitic stainless steel; Nuclear reactors — Materials — Testing; Silicon; Steel – Embrittlement; Stress corrosion

Controlled Subject

Corrosion and anti-corrosives--Testing; Eutectic alloys; Nuclear reactors--Materials--Testing

Disciplines

Materials Science and Engineering | Metallurgy | Nuclear Engineering | Oil, Gas, and Energy

File Format

pdf

File Size

218 KB

Language

English

Rights

IN COPYRIGHT. For more information about this rights statement, please visit http://rightsstatements.org/vocab/InC/1.0/

Repository Citation

Roy, A. K. (2006). Effect of Silicon Content on the Corrosion Resistance and Radiation- Induced Embrittlement of Materials for Advanced Heavy Liquid Metal Nuclear Systems. 44-45.
Available at: https://digitalscholarship.unlv.edu/hrc_trp_sciences_materials/134