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Title: MPA Materials Matter December 2017


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  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
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Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
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Resource Type:
Technical Report
Country of Publication:
United States
36 MATERIALS SCIENCE; LANL; MPA Materials Matter; Newsletter of the Materials Physics and Applications Division; ADEPS Communications

Citation Formats

Kippen, Karen Elizabeth. MPA Materials Matter December 2017. United States: N. p., 2017. Web. doi:10.2172/1414159.
Kippen, Karen Elizabeth. MPA Materials Matter December 2017. United States. doi:10.2172/1414159.
Kippen, Karen Elizabeth. 2017. "MPA Materials Matter December 2017". United States. doi:10.2172/1414159.
title = {MPA Materials Matter December 2017},
author = {Kippen, Karen Elizabeth},
abstractNote = {No abstract provided.},
doi = {10.2172/1414159},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2017,
month =

Technical Report:

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  • No abstract provided.
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  • Understanding of reactor material behavior in extreme environments is vital not only to the development of new materials for the next generation nuclear reactors, but also to the extension of the operating lifetimes of the current fleet of nuclear reactors. To this end, this project conducted a suite of unique experimental techniques, augmented by a mesoscale computational framework, to understand and predict the long-term effects of irradiation, temperature, and stress on material microstructures and their macroscopic behavior. The experimental techniques and computational tools were demonstrated on two distinctive types of reactor materials, namely, Zr alloys and high-Cr martensitic steels. Thesemore » materials are chosen as the test beds because they are the archetypes of high-performance reactor materials (cladding, wrappers, ducts, pressure vessel, piping, etc.). To fill the knowledge gaps, and to meet the technology needs, a suite of innovative in situ transmission electron microscopy (TEM) characterization techniques (heating, heavy ion irradiation, He implantation, quantitative small-scale mechanical testing, and various combinations thereof) were developed and used to elucidate and map the fundamental mechanisms of microstructure evolution in both Zr and Cr alloys for a wide range environmental boundary conditions in the thermal-mechanical-irradiation input space. Knowledge gained from the experimental observations of the active mechanisms and the role of local microstructural defects on the response of the material has been incorporated into a mathematically rigorous and comprehensive three-dimensional mesoscale framework capable of accounting for the compositional variation, microstructural evolution and localized deformation (radiation damage) to predict aging and degradation of key reactor materials operating in extreme environments. Predictions from this mesoscale framework were compared with the in situ TEM observations to validate the model.« less